Explore: Pressurized Water Reactors
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AI-Generated Overview About “pressurized-water-reactors”:
Books Results
Source: The Open Library
The Open Library Search Results
Search results from The Open Library
1The "calculated" loss-of-coolant accident
By L. J. Ybarrondo

“The "calculated" loss-of-coolant accident” Metadata:
- Title: ➤ The "calculated" loss-of-coolant accident
- Author: L. J. Ybarrondo
- Language: English
- Number of Pages: Median: 99
- Publisher: ➤ American Institute of Chemical Engineers
- Publish Date: 1972
- Publish Location: New York
“The "calculated" loss-of-coolant accident” Subjects and Themes:
- Subjects: ➤ Nuclear reactors - Cooling - Safety measures - Pressurized water reactors - Boiling water reactors - Loss of coolant
Edition Identifiers:
- The Open Library ID: OL19457681M - OL13953461M - OL19850073M - OL5299398M - OL43140954M
- Online Computer Library Center (OCLC) ID: 363668
- Library of Congress Control Number (LCCN): 72080270
Access and General Info:
- First Year Published: 1972
- Is Full Text Available: Yes
- Is The Book Public: No
- Access Status: Borrowable
Online Access
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2Standard technical specifications
By U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation.
“Standard technical specifications” Metadata:
- Title: ➤ Standard technical specifications
- Author: ➤ U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation.
- Language: English
- Publisher: ➤ The Commission - U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation - Supt. of Docs., U.S. G.P.O. distributor - The Office - Supt. of Docs., U.S. G.P.O. [distributor
- Publish Date: 1991 - 1992 - 1995 - 2001
- Publish Location: ➤ [Washington, D.C.] - [Washington, DC] - Washington, DC
“Standard technical specifications” Subjects and Themes:
- Subjects: ➤ Boiling water reactors - Combustion Engineering, inc - Design and construction - General Electric Company - Nuclear power plants - Pressurized water reactors - Specifications - Westinghouse Electric Corporation
- Places: United States
Edition Identifiers:
- The Open Library ID: ➤ OL17791135M - OL17791024M - OL15418115M - OL17660871M - OL14684855M - OL17660810M - OL17660909M - OL17791025M - OL17783693M - OL14691702M - OL14679702M - OL17678325M - OL17678324M - OL14679704M - OL17803758M - OL15290891M - OL17660870M - OL14691701M - OL16043448M - OL17112533M
- Online Computer Library Center (OCLC) ID: ➤ 24089523 - 35162361 - 34020259 - 34020796 - 34020585 - 24280991 - 24281004 - 35162433
Author's Alternative Names:
"U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation"Access and General Info:
- First Year Published: 1991
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
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3Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors
By John H Jackson, Denise Paraventi and Michael Wright

“Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors” Metadata:
- Title: ➤ Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors
- Authors: John H JacksonDenise ParaventiMichael Wright
- Number of Pages: Median: 1308
- Publisher: Springer
- Publish Date: 2017 - 2018 - 2019
“Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors” Subjects and Themes:
- Subjects: Nuclear power plants - Pressurized water reactors
Edition Identifiers:
- The Open Library ID: ➤ OL28319878M - OL28177196M - OL28246227M - OL28337374M - OL28240195M - OL30195623M - OL27944641M - OL28188979M
- All ISBNs: ➤ 9783319786728 - 9783319708133 - 3030046389 - 3319708139 - 9783319672434 - 9783030046385 - 3319684531 - 9783319883984 - 3319883984 - 3319786725 - 3319899554 - 9783319899558 - 9783319684536 - 3319672436 - 3319886061 - 9783319886060
Access and General Info:
- First Year Published: 2017
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
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4Proceedings of the Institution of Mechanical Engineers
By IMechE (Institution of Mechanical Engineers)

“Proceedings of the Institution of Mechanical Engineers” Metadata:
- Title: ➤ Proceedings of the Institution of Mechanical Engineers
- Author: ➤ IMechE (Institution of Mechanical Engineers)
- Language: English
- Number of Pages: Median: 214
- Publisher: ➤ Mechanical Engineering Publications for IMechE - Published for IMechE by Mechanical Engineering Publications - Wiley
- Publish Date: 1994
- Publish Location: ➤ Bury St. Edmunds - Bury St. Edmunds, England - Bury St. Edmunds, Suffolk
“Proceedings of the Institution of Mechanical Engineers” Subjects and Themes:
- Subjects: ➤ Congresses - Nuclear power plants - Pressurized water reactors - Compressors - Compressed air - Industrial applications - Automobiles, electronic equipment - Nuclear energy - Mechanical engineering
Edition Identifiers:
- The Open Library ID: ➤ OL11605678M - OL20518298M - OL11605679M - OL20518333M - OL22619688M - OL11605682M
- All ISBNs: ➤ 9780852989074 - 0852989040 - 9780852989043 - 0852989032 - 0852989075 - 9780852989036
Author's Alternative Names:
"Institution of Mechanical Engineers", "Inst. Mech. Eng.", "Institution of Mechanical Engineers.", "Institution of Mechanical Engineers (Great Britain)", "Institution of mechanical Engineers.", "Institution Of Mechanical Engineers", "Great Britain Institution Of Mechanical Engineers", "IMechE", "Institution Of Mechanical Engineers (Great Britain)" and "Institution Of Mechanical Engineers."Access and General Info:
- First Year Published: 1994
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
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5Safety Features of Operating Light Water Reactors of Western Design
By M. Gavrilas
“Safety Features of Operating Light Water Reactors of Western Design” Metadata:
- Title: ➤ Safety Features of Operating Light Water Reactors of Western Design
- Author: M. Gavrilas
- Language: English
- Number of Pages: Median: 311
- Publisher: Taylor & Francis Group
- Publish Date: 2017 - 2018
“Safety Features of Operating Light Water Reactors of Western Design” Subjects and Themes:
- Subjects: ➤ Light water reactors - Safety measures - Design - Pressurized water reactors - Boiling water reactors - Réacteurs à eau légère - Sécurité - Mesures - Réacteurs à eau sous pression - Réacteurs à eau bouillante
Edition Identifiers:
- The Open Library ID: OL28897801M - OL33734271M - OL33748107M - OL33780276M - OL33732175M
- Online Computer Library Center (OCLC) ID: 1031055102
- All ISBNs: ➤ 135109341X - 1351084968 - 9781351076517 - 9781351093415 - 9781351084963 - 1315897415 - 9781315897417 - 9781351101868 - 1351101862 - 1351076515
Access and General Info:
- First Year Published: 2017
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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6Assessment of the TRAC-M codes using Flecht-Seaset reflood and steam cooling data
By F. Odar
“Assessment of the TRAC-M codes using Flecht-Seaset reflood and steam cooling data” Metadata:
- Title: ➤ Assessment of the TRAC-M codes using Flecht-Seaset reflood and steam cooling data
- Author: F. Odar
- Language: English
- Number of Pages: Median: 82
- Publisher: ➤ U.S. Nuclear Regulatory Commission - Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 2001
- Publish Location: Washington, DC
“Assessment of the TRAC-M codes using Flecht-Seaset reflood and steam cooling data” Subjects and Themes:
- Subjects: ➤ Computer programs - Pressurized water reactors - Thermodynamics - Loss of coolant - Steam-boilers - Cooling
Edition Identifiers:
- The Open Library ID: OL18167729M - OL16025902M - OL18657720M - OL17603539M - OL22429258M
- Online Computer Library Center (OCLC) ID: 47652997
Access and General Info:
- First Year Published: 2001
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
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7Nowadays tools for graphical post-processing of TRAC-BF1 results
By P. Corcuera
“Nowadays tools for graphical post-processing of TRAC-BF1 results” Metadata:
- Title: ➤ Nowadays tools for graphical post-processing of TRAC-BF1 results
- Author: P. Corcuera
- Language: English
- Number of Pages: Median: 24
- Publisher: ➤ United States Government Printing Office - U.S. Nuclear Regulatory Commission - Supt. of Docs., U.S. G.P.O., distributor - Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission - [Supt. of Docs., U.S. G.P.O., distributor
- Publish Date: 2000
- Publish Location: Washington, DC
“Nowadays tools for graphical post-processing of TRAC-BF1 results” Subjects and Themes:
Edition Identifiers:
- The Open Library ID: OL59592826M - OL50666264M - OL23140364M - OL15999757M - OL23139452M
- Online Computer Library Center (OCLC) ID: 46490781
- Library of Congress Control Number (LCCN): 00329653
- All ISBNs: 9780160614323 - 0160614325
Access and General Info:
- First Year Published: 2000
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
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8Pressurized water-reactor feedwater piping response to water hammer
By Don Arthur
“Pressurized water-reactor feedwater piping response to water hammer” Metadata:
- Title: ➤ Pressurized water-reactor feedwater piping response to water hammer
- Author: Don Arthur
- Language: English
- Number of Pages: Median: 33
- Publisher: ➤ for sale by the National Technical Information Service - University of California, Lawrence Livermore Laboratory, Technical Information Dept.
- Publish Date: 1978
- Publish Location: ➤ Livermore, Calif - Springfield, Va
“Pressurized water-reactor feedwater piping response to water hammer” Subjects and Themes:
- Subjects: Accidents - Pressurized water reactors - Water hammer
Edition Identifiers:
- The Open Library ID: OL14885035M - OL18013946M - OL15225875M - OL17965701M
Access and General Info:
- First Year Published: 1978
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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9Proceedings of the U.S. Nuclear Regulatory Commission, fifteenth Water Reactor Safety Information Meeting
By Water Reactor Safety Information Meeting (15th 1987 Gaithersburg, Md.)
“Proceedings of the U.S. Nuclear Regulatory Commission, fifteenth Water Reactor Safety Information Meeting” Metadata:
- Title: ➤ Proceedings of the U.S. Nuclear Regulatory Commission, fifteenth Water Reactor Safety Information Meeting
- Author: ➤ Water Reactor Safety Information Meeting (15th 1987 Gaithersburg, Md.)
- Language: English
- Publisher: ➤ National Technical Information Service - Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission - Available from Supt. of Docs., U.S. G.P.O.
- Publish Date: 1987
- Publish Location: ➤ Washington, DC - Springfield, VA
“Proceedings of the U.S. Nuclear Regulatory Commission, fifteenth Water Reactor Safety Information Meeting” Subjects and Themes:
- Subjects: Safety measures - Congresses - Nuclear reactors - Pressurized water reactors
Edition Identifiers:
- The Open Library ID: OL15346354M - OL14658442M - OL17090375M - OL18048915M
Access and General Info:
- First Year Published: 1987
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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10Voltage-based interim plugging criteria for steam generator tubes
By U.S. Nuclear Regulatory Commission. IPC Task Group.
“Voltage-based interim plugging criteria for steam generator tubes” Metadata:
- Title: ➤ Voltage-based interim plugging criteria for steam generator tubes
- Author: ➤ U.S. Nuclear Regulatory Commission. IPC Task Group.
- Language: English
- Publisher: ➤ U.S. Nuclear Regulatory Commission
- Publish Date: 1993
- Publish Location: Washington, DC
“Voltage-based interim plugging criteria for steam generator tubes” Subjects and Themes:
- Subjects: Materials - Stress corrosion - Steam-boilers - Pressurized water reactors
Edition Identifiers:
- The Open Library ID: OL15383844M - OL17110203M - OL14698719M - OL18063675M
Access and General Info:
- First Year Published: 1993
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
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11Assessment of RELAP5/MOD3.2-NPA3.4 against an inadvertent closure of all three MSIV's in VANDELLOS-II nuclear power plant
By C. Llopis
“Assessment of RELAP5/MOD3.2-NPA3.4 against an inadvertent closure of all three MSIV's in VANDELLOS-II nuclear power plant” Metadata:
- Title: ➤ Assessment of RELAP5/MOD3.2-NPA3.4 against an inadvertent closure of all three MSIV's in VANDELLOS-II nuclear power plant
- Author: C. Llopis
- Language: English
- Number of Pages: Median: 61
- Publisher: ➤ Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 2001
- Publish Location: Washington, DC
“Assessment of RELAP5/MOD3.2-NPA3.4 against an inadvertent closure of all three MSIV's in VANDELLOS-II nuclear power plant” Subjects and Themes:
- Subjects: Computer simulation - Pressurized water reactors - Accident - Accidents
- Places: Spain
Edition Identifiers:
- The Open Library ID: OL18157435M - OL17614765M - OL16005621M - OL22416914M
- Online Computer Library Center (OCLC) ID: 52431937
Access and General Info:
- First Year Published: 2001
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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12Assessment of RELAP5/MOD3.2-NPA3.4 against a transient of high nuclear flux variation reactor trip, natural circulation and the start of a main pump in the VANDELLOS II nuclear power plant
By C. Llopis
“Assessment of RELAP5/MOD3.2-NPA3.4 against a transient of high nuclear flux variation reactor trip, natural circulation and the start of a main pump in the VANDELLOS II nuclear power plant” Metadata:
- Title: ➤ Assessment of RELAP5/MOD3.2-NPA3.4 against a transient of high nuclear flux variation reactor trip, natural circulation and the start of a main pump in the VANDELLOS II nuclear power plant
- Author: C. Llopis
- Language: English
- Number of Pages: Median: 49
- Publisher: ➤ Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission - Supt. of Docs., U.S. G.P.O. [distributor
- Publish Date: 1998
- Publish Location: Washington, DC
“Assessment of RELAP5/MOD3.2-NPA3.4 against a transient of high nuclear flux variation reactor trip, natural circulation and the start of a main pump in the VANDELLOS II nuclear power plant” Subjects and Themes:
- Subjects: Accidents - Computer simulation - Pressurized water reactors
- Places: Spain
Edition Identifiers:
- The Open Library ID: OL22382759M - OL15542381M - OL17602216M - OL18132859M
Access and General Info:
- First Year Published: 1998
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
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13TRAC-M validation test matrix
By B. E. Boyack
“TRAC-M validation test matrix” Metadata:
- Title: TRAC-M validation test matrix
- Author: B. E. Boyack
- Language: English
- Publisher: ➤ United States Government Printing Office - U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research - Division of System Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 2001
- Publish Location: ➤ Washington, D.C - Washington, DC
“TRAC-M validation test matrix” Subjects and Themes:
- Subjects: Forecasting - Accidents - Computer programs - Water cooled reactors - Pressurized water reactors
Edition Identifiers:
- The Open Library ID: OL18166952M - OL16024723M - OL17614753M - OL50666828M
- Online Computer Library Center (OCLC) ID: 50678819
- All ISBNs: 0160664438 - 9780160664434
Access and General Info:
- First Year Published: 2001
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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14U.S. operating experience with thermally treated Alloy 600 steam generator tubes
By K. J. Karwoski
“U.S. operating experience with thermally treated Alloy 600 steam generator tubes” Metadata:
- Title: ➤ U.S. operating experience with thermally treated Alloy 600 steam generator tubes
- Author: K. J. Karwoski
- Language: English
- Number of Pages: Median: 251
- Publisher: ➤ Supt. of Docs., U.S. G.P.O. [distributor] - Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission
- Publish Date: 2003
- Publish Location: Washington, DC
“U.S. operating experience with thermally treated Alloy 600 steam generator tubes” Subjects and Themes:
- Subjects: Materials - Stress corrosion - Steam-boilers - Pressurized water reactors
- Places: United States
Edition Identifiers:
- The Open Library ID: OL18187960M - OL18683113M - OL16055704M - OL17620901M
- Online Computer Library Center (OCLC) ID: 53126487
Access and General Info:
- First Year Published: 2003
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
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15RELAP5/MOD.2 post test analysis and accuracy quantification of Lobi test BL-34
By F. D'Auria
“RELAP5/MOD.2 post test analysis and accuracy quantification of Lobi test BL-34” Metadata:
- Title: ➤ RELAP5/MOD.2 post test analysis and accuracy quantification of Lobi test BL-34
- Author: F. D'Auria
- Language: English
- Number of Pages: Median: 148
- Publisher: ➤ Supt. of Docs., U.S. G.P.O. [distributor - Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 1999
- Publish Location: Washington, DC
“RELAP5/MOD.2 post test analysis and accuracy quantification of Lobi test BL-34” Subjects and Themes:
- Subjects: Loss of coolant - Testing - Pressurized water reactors - Computer programs
Edition Identifiers:
- The Open Library ID: OL22382933M - OL15545093M - OL18133590M - OL17602219M
Access and General Info:
- First Year Published: 1999
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
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16RELAP5/MOD3.2 post test analysis and accuracy quantification of Lobi test BL-44
By F. D'Auria
“RELAP5/MOD3.2 post test analysis and accuracy quantification of Lobi test BL-44” Metadata:
- Title: ➤ RELAP5/MOD3.2 post test analysis and accuracy quantification of Lobi test BL-44
- Author: F. D'Auria
- Language: English
- Number of Pages: Median: 152
- Publisher: ➤ Supt. of Docs., U.S. G.P.O. [distributor - Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 1999
- Publish Location: Washington, DC
“RELAP5/MOD3.2 post test analysis and accuracy quantification of Lobi test BL-44” Subjects and Themes:
- Subjects: Loss of coolant - Testing - Pressurized water reactors - Computer programs
Edition Identifiers:
- The Open Library ID: OL18132860M - OL15542384M - OL17602220M - OL22382760M
Access and General Info:
- First Year Published: 1999
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
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17RELAP5/MOD3.2 post test analysis and accuracy quantification of SPES test SP-SB-03
By F. D'Auria
“RELAP5/MOD3.2 post test analysis and accuracy quantification of SPES test SP-SB-03” Metadata:
- Title: ➤ RELAP5/MOD3.2 post test analysis and accuracy quantification of SPES test SP-SB-03
- Author: F. D'Auria
- Language: English
- Number of Pages: Median: 143
- Publisher: ➤ Supt. of Docs., U.S. G.P.O. [distributor - Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 1999
- Publish Location: Washington, DC
“RELAP5/MOD3.2 post test analysis and accuracy quantification of SPES test SP-SB-03” Subjects and Themes:
- Subjects: Loss of coolant - Testing - Pressurized water reactors - Computer programs
Edition Identifiers:
- The Open Library ID: OL22382934M - OL15545095M - OL17602221M - OL18133592M
Access and General Info:
- First Year Published: 1999
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
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18RELAP5/MOD3.2 post test analysis and accuracy quantification of SPES test SP-SB-04
By F. D'Auria
“RELAP5/MOD3.2 post test analysis and accuracy quantification of SPES test SP-SB-04” Metadata:
- Title: ➤ RELAP5/MOD3.2 post test analysis and accuracy quantification of SPES test SP-SB-04
- Author: F. D'Auria
- Language: English
- Number of Pages: Median: 168
- Publisher: ➤ Supt. of Docs., U.S. G.P.O. [distributor - Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 1999
- Publish Location: Washington, DC
“RELAP5/MOD3.2 post test analysis and accuracy quantification of SPES test SP-SB-04” Subjects and Themes:
- Subjects: Loss of coolant - Testing - Pressurized water reactors - Computer programs
Edition Identifiers:
- The Open Library ID: OL15549644M - OL22384207M - OL18135298M - OL17602222M
Access and General Info:
- First Year Published: 1999
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
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19Assessment of RELAP5/MOD3.2 against a main steam isolation valve closure at TRILLO I Nuclear Power Plant
By A. de Lucas
“Assessment of RELAP5/MOD3.2 against a main steam isolation valve closure at TRILLO I Nuclear Power Plant” Metadata:
- Title: ➤ Assessment of RELAP5/MOD3.2 against a main steam isolation valve closure at TRILLO I Nuclear Power Plant
- Author: A. de Lucas
- Language: English
- Number of Pages: Median: 39
- Publisher: ➤ Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 2000
- Publish Location: Washington, DC
“Assessment of RELAP5/MOD3.2 against a main steam isolation valve closure at TRILLO I Nuclear Power Plant” Subjects and Themes:
- Subjects: Computer simulation - Loss of coolant - Nuclear power plants - Pressurized water reactors - Thermodynamics
- Places: Spain
Edition Identifiers:
- The Open Library ID: OL18168903M - OL17718536M - OL22429767M - OL13629620M
- Online Computer Library Center (OCLC) ID: 49588295
Access and General Info:
- First Year Published: 2000
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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20Test LOBI-BL06
By T. Fiore
“Test LOBI-BL06” Metadata:
- Title: Test LOBI-BL06
- Author: T. Fiore
- Language: English
- Number of Pages: Median: 85
- Publisher: ➤ Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission - Supt. of Docs., U.S. G.P.O. [distributor
- Publish Date: 1999
- Publish Location: Washington, DC
“Test LOBI-BL06” Subjects and Themes:
- Subjects: Loss of coolant - Computer simulation - Evaluation - Pressurized water reactors
Edition Identifiers:
- The Open Library ID: OL17602226M - OL15549646M - OL18135301M - OL22384208M
Access and General Info:
- First Year Published: 1999
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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21RELAP5/MOD3.2 validation using BETHSY test 6.9a
By S. Bouabdallah
“RELAP5/MOD3.2 validation using BETHSY test 6.9a” Metadata:
- Title: ➤ RELAP5/MOD3.2 validation using BETHSY test 6.9a
- Author: S. Bouabdallah
- Language: English
- Number of Pages: Median: 22
- Publisher: ➤ Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 2000
- Publish Location: Washington, DC
“RELAP5/MOD3.2 validation using BETHSY test 6.9a” Subjects and Themes:
- Subjects: Loss of coolant - Testing - Pressurized water reactors - Computer programs
Edition Identifiers:
- The Open Library ID: OL17716947M - OL22416912M - OL17614762M - OL18157430M
- Online Computer Library Center (OCLC) ID: 52431869
Access and General Info:
- First Year Published: 2000
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
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22Proceedings of the U.S. Nuclear Regulatory Commission
By Water Reactor Safety Information Meeting (14th 1986 Gaithersburg, Md.)
“Proceedings of the U.S. Nuclear Regulatory Commission” Metadata:
- Title: ➤ Proceedings of the U.S. Nuclear Regulatory Commission
- Author: ➤ Water Reactor Safety Information Meeting (14th 1986 Gaithersburg, Md.)
- Language: English
- Publisher: ➤ Available from Supt. of Docs., U.S. G.P.O. - National Technical Information Service - Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 1987
- Publish Location: ➤ Washington, DC - Springfield, VA
“Proceedings of the U.S. Nuclear Regulatory Commission” Subjects and Themes:
- Subjects: Safety measures - Congresses - Nuclear reactors - Pressurized water reactors
Edition Identifiers:
- The Open Library ID: OL18050828M - OL17570037M - OL15352129M - OL17092718M
Access and General Info:
- First Year Published: 1987
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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23TRAC-M programmer's guide
By R. G. Steinke
“TRAC-M programmer's guide” Metadata:
- Title: TRAC-M programmer's guide
- Author: R. G. Steinke
- Language: English
- Publisher: ➤ Supt. of Docs., U.S. G.P.O. [distributor] - Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission - U.S. Nuclear Regulatory Commission
- Publish Date: 1999
- Publish Location: Washington, DC
“TRAC-M programmer's guide” Subjects and Themes:
- Subjects: ➤ Computer programs - Forecasting - Accidents - Pressurized water reactors - Water cooled reactors - Safety measures
Edition Identifiers:
- The Open Library ID: OL15561159M - OL16320516M - OL17603925M - OL18138803M
- Online Computer Library Center (OCLC) ID: 43618801 - 43363480
Access and General Info:
- First Year Published: 1999
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
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24RELAP5/MOD3.2 post test calculation of the PKL-experiment PKLIII-B4.3
By L. Karner
“RELAP5/MOD3.2 post test calculation of the PKL-experiment PKLIII-B4.3” Metadata:
- Title: ➤ RELAP5/MOD3.2 post test calculation of the PKL-experiment PKLIII-B4.3
- Author: L. Karner
- Language: English
- Number of Pages: Median: 68
- Publisher: ➤ Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission - Supt. of Docs., U.S. G.P.O. [distributor
- Publish Date: 1999
- Publish Location: Washington, DC
“RELAP5/MOD3.2 post test calculation of the PKL-experiment PKLIII-B4.3” Subjects and Themes:
- Subjects: ➤ Computer simulation - Control - Steam generating heavy water reactors - Pressurized water reactors
Edition Identifiers:
- The Open Library ID: OL15560428M - OL17602233M - OL22395416M - OL18138687M
Access and General Info:
- First Year Published: 1999
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
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25Assessment of TRAC-PF1/MOD1 against a loss-of-grid transient in Ringhals 4 power plant
By Anders Sjöberg
“Assessment of TRAC-PF1/MOD1 against a loss-of-grid transient in Ringhals 4 power plant” Metadata:
- Title: ➤ Assessment of TRAC-PF1/MOD1 against a loss-of-grid transient in Ringhals 4 power plant
- Author: Anders Sjöberg
- Language: English
- Number of Pages: Median: 35
- Publisher: ➤ U.S. Nuclear Regulatory Commission - Supt. of Docs., U.S. G.P.O. [distributor] - National Technical Information Service [distributor
- Publish Date: 1989
- Publish Location: ➤ Washington, DC - Springfield, VA
“Assessment of TRAC-PF1/MOD1 against a loss-of-grid transient in Ringhals 4 power plant” Subjects and Themes:
- Subjects: Computer programs - Mathematical models - Nuclear reactors - Pressurized water reactors - Thermodynamics
- Places: United States
Edition Identifiers:
- The Open Library ID: OL18060295M - OL14809091M - OL17934385M - OL15377096M
Access and General Info:
- First Year Published: 1989
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
Downloads Are Not Available:
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26Assessment of TRAC-PF1/MOD1 against an inadvertent feedwater line isolation transient in the Ringhals 4 power plant
By Anders Sjöberg
“Assessment of TRAC-PF1/MOD1 against an inadvertent feedwater line isolation transient in the Ringhals 4 power plant” Metadata:
- Title: ➤ Assessment of TRAC-PF1/MOD1 against an inadvertent feedwater line isolation transient in the Ringhals 4 power plant
- Author: Anders Sjöberg
- Language: English
- Number of Pages: Median: 55
- Publisher: ➤ U.S. Nuclear Regulatory Commission - Supt. of Docs., U.S. G.P.O. [distributor] - National Technical Information Service [distributor
- Publish Date: 1992
- Publish Location: ➤ Washington, DC - Springfield, VA
“Assessment of TRAC-PF1/MOD1 against an inadvertent feedwater line isolation transient in the Ringhals 4 power plant” Subjects and Themes:
- Subjects: Accidents - Data processing - Loss of coolant - Nuclear power plants - Pressurized water reactors
- Places: Sweden
Edition Identifiers:
- The Open Library ID: OL17995384M - OL14956320M - OL18066470M - OL15389713M
Access and General Info:
- First Year Published: 1992
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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27Thermal analysis of pressurized water reactors
By L. S. Tong

“Thermal analysis of pressurized water reactors” Metadata:
- Title: ➤ Thermal analysis of pressurized water reactors
- Author: L. S. Tong
- Language: English
- Number of Pages: Median: 417
- Publisher: American Nuclear Society
- Publish Date: 1970 - 1979 - 1996
- Publish Location: ➤ La Grange Park, Ill - LaGrange Park, Ill - Hinsdale, Ill
“Thermal analysis of pressurized water reactors” Subjects and Themes:
- Subjects: Transmission - Thermodynamics - Heat - Pressurized water reactors - Réacteurs à eau sous pression
Edition Identifiers:
- The Open Library ID: OL808609M - OL4575549M - OL4428552M
- Online Computer Library Center (OCLC) ID: 605613242 - 126721 - 5896991
- Library of Congress Control Number (LCCN): 79054237 - 77119001 - 95045359
- All ISBNs: 9780894480195 - 0894480383 - 9780894480386 - 0894480197
Access and General Info:
- First Year Published: 1970
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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28RELAP5/MOD3.2 post test analysis and accuracy quantification of Lobi test BL-44
By F D'Auria
“RELAP5/MOD3.2 post test analysis and accuracy quantification of Lobi test BL-44” Metadata:
- Title: ➤ RELAP5/MOD3.2 post test analysis and accuracy quantification of Lobi test BL-44
- Author: F D'Auria
- Language: English
- Number of Pages: Median: 152
- Publisher: ➤ Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission - Supt. of Docs., U.S. G.P.O. [distributor
- Publish Date: 1999
- Publish Location: Washington, DC
“RELAP5/MOD3.2 post test analysis and accuracy quantification of Lobi test BL-44” Subjects and Themes:
- Subjects: Computer programs - Loss of coolant - Pressurized water reactors - Testing
Edition Identifiers:
- The Open Library ID: OL18296201M - OL16132731M - OL13625180M
- Online Computer Library Center (OCLC) ID: 42793352
Access and General Info:
- First Year Published: 1999
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
Downloads Are Not Available:
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29Assessment of BETHSY test 9.1.b using RELAP5/MOD3
By S. Lee
“Assessment of BETHSY test 9.1.b using RELAP5/MOD3” Metadata:
- Title: ➤ Assessment of BETHSY test 9.1.b using RELAP5/MOD3
- Author: S. Lee
- Language: English
- Number of Pages: Median: 234
- Publisher: ➤ available from Supt. of Docs., U.S. G.P.O. - Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission - National Technical Information Service [distributor
- Publish Date: 1993
- Publish Location: ➤ Springfield, VA - Washington, DC
“Assessment of BETHSY test 9.1.b using RELAP5/MOD3” Subjects and Themes:
- Subjects: Accidents - Data processing - Loss of coolant - Pressurized water reactors
Edition Identifiers:
- The Open Library ID: OL17750442M - OL14715702M - OL17678004M
Access and General Info:
- First Year Published: 1993
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
Downloads Are Not Available:
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30GSI-191
By D. V. Rao
“GSI-191” Metadata:
- Title: GSI-191
- Author: D. V. Rao
- Language: English
- Number of Pages: Median: 285
- Publisher: ➤ Supt. of Docs., U.S. G.P.O. [distributor] - Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission - United States Government Printing Office
- Publish Date: 2002
- Publish Location: Washington, DC
“GSI-191” Subjects and Themes:
- Subjects: Emergency core cooling systems - Pressurized water reactors
- Places: United States
Edition Identifiers:
- The Open Library ID: OL50664680M - OL16043119M - OL18178704M
- All ISBNs: 9780160675256 - 0160675251
Access and General Info:
- First Year Published: 2002
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
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31Materials Ageing and Degradation in Light Water Reactors
By K. L. Murty

“Materials Ageing and Degradation in Light Water Reactors” Metadata:
- Title: ➤ Materials Ageing and Degradation in Light Water Reactors
- Author: K. L. Murty
- Language: English
- Number of Pages: Median: 441
- Publisher: ➤ Woodhead Publishing - Elsevier Science & Technology
- Publish Date: 2013 - 2018
“Materials Ageing and Degradation in Light Water Reactors” Subjects and Themes:
- Subjects: Pressurized water reactors
Edition Identifiers:
- The Open Library ID: OL53923898M - OL27846613M - OL35485016M
- All ISBNs: ➤ 1306176387 - 9781306176385 - 9780081016060 - 9780857097453 - 0081016069 - 0857097458
Access and General Info:
- First Year Published: 2013
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
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32SPARC-90, a code for calculating fission product capture in suppression pools
By P. C. Owczarski
“SPARC-90, a code for calculating fission product capture in suppression pools” Metadata:
- Title: ➤ SPARC-90, a code for calculating fission product capture in suppression pools
- Author: P. C. Owczarski
- Language: English
- Publisher: ➤ Division of Regulatory Applications, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission - Supt. of Docs., U.S. G.P.O. [distributor]
- Publish Date: 1991
- Publish Location: Washington, DC
“SPARC-90, a code for calculating fission product capture in suppression pools” Subjects and Themes:
- Subjects: ➤ Accidents - Aerosols, Radioactive - Computer programs - Fission products - Measurement - Pressurized water reactors - Radioactive Aerosols
Edition Identifiers:
- The Open Library ID: OL15374882M - OL14693499M - OL18059579M
Access and General Info:
- First Year Published: 1991
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
Downloads Are Not Available:
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33Post-test analysis of LOBI test BT-12 using RELAP5/MOD2
By A. J. Smethurst
“Post-test analysis of LOBI test BT-12 using RELAP5/MOD2” Metadata:
- Title: ➤ Post-test analysis of LOBI test BT-12 using RELAP5/MOD2
- Author: A. J. Smethurst
- Language: English
- Number of Pages: Median: 62
- Publisher: ➤ National Technical Information Service [distributor - U.S. Nuclear Regulatory Commission - Supt. of Docs., U.S. G.P.O. [distributor]
- Publish Date: 1992
- Publish Location: ➤ Springfield, VA - Washington, DC
“Post-test analysis of LOBI test BT-12 using RELAP5/MOD2” Subjects and Themes:
- Subjects: Pressurized water reactors - Safety measures - Testing - Nuclear reactors
- Places: Great Britain
Edition Identifiers:
- The Open Library ID: OL18067275M - OL15391366M - OL14704422M
Access and General Info:
- First Year Published: 1992
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
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34Study of unusual occurrence of a partial core uncovery in an SBLOCA scenario
By C. Pretel
“Study of unusual occurrence of a partial core uncovery in an SBLOCA scenario” Metadata:
- Title: ➤ Study of unusual occurrence of a partial core uncovery in an SBLOCA scenario
- Author: C. Pretel
- Language: English
- Number of Pages: Median: 30
- Publisher: ➤ Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission - Supt. of Docs., U.S. G.P.O. [distributor - United States Government Printing Office
- Publish Date: 2000
- Publish Location: Washington, DC
“Study of unusual occurrence of a partial core uncovery in an SBLOCA scenario” Subjects and Themes:
- Subjects: Loss of coolant - Computer simulation - Pressurized water reactors
Edition Identifiers:
- The Open Library ID: OL50666067M - OL17703164M - OL17594222M
- Online Computer Library Center (OCLC) ID: 43915720
- All ISBNs: 9780160591150 - 0160591155
Access and General Info:
- First Year Published: 2000
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
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35RELAP5/MOD3.2 assessment using GERDA small break test, 1605AA
By W. Tietsch
“RELAP5/MOD3.2 assessment using GERDA small break test, 1605AA” Metadata:
- Title: ➤ RELAP5/MOD3.2 assessment using GERDA small break test, 1605AA
- Author: W. Tietsch
- Language: English
- Number of Pages: Median: 62
- Publisher: ➤ Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission - Supt. of Docs., U.S. G.P.O. [distributor
- Publish Date: 1999
- Publish Location: Washington, DC
“RELAP5/MOD3.2 assessment using GERDA small break test, 1605AA” Subjects and Themes:
- Subjects: Loss of coolant - Computer simulation - Pressurized water reactors
Edition Identifiers:
- The Open Library ID: OL15550829M - OL18135710M - OL17584249M
- Online Computer Library Center (OCLC) ID: 42825873
Access and General Info:
- First Year Published: 1999
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
Downloads Are Not Available:
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36Thermal-hydraulic research plan for Babcock and Wilcox plants
By R. Y. Lee
“Thermal-hydraulic research plan for Babcock and Wilcox plants” Metadata:
- Title: ➤ Thermal-hydraulic research plan for Babcock and Wilcox plants
- Author: R. Y. Lee
- Language: English
- Number of Pages: Median: 33
- Publisher: ➤ Division of Reactor and Plant Systems, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 1988
- Publish Location: Washington, DC
“Thermal-hydraulic research plan for Babcock and Wilcox plants” Subjects and Themes:
- Subjects: ➤ Babcock & Wilcox Company - Nuclear power plants - Pressurized water reactors - Research - Steam-boilers - Thermodynamics
- Places: United States
Edition Identifiers:
- The Open Library ID: OL18048605M - OL17089956M - OL15344996M
Access and General Info:
- First Year Published: 1988
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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37Viscosity of zirconium-uranium oxide (Zr-UO) mixtures at 1800 to 2100C̊
By L. R. Bunnell
“Viscosity of zirconium-uranium oxide (Zr-UO) mixtures at 1800 to 2100C̊” Metadata:
- Title: ➤ Viscosity of zirconium-uranium oxide (Zr-UO) mixtures at 1800 to 2100C̊
- Author: L. R. Bunnell
- Language: English
- Number of Pages: Median: 35
- Publisher: ➤ Division of Reactor System Safety, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 1986
- Publish Location: Washington, DC
“Viscosity of zirconium-uranium oxide (Zr-UO) mixtures at 1800 to 2100C̊” Subjects and Themes:
- Subjects: Uranium - Viscosity - Zirconium oxide - Pressurized water reactors - Loss of coolant
Edition Identifiers:
- The Open Library ID: OL17563909M - OL18046671M - OL15338369M
Access and General Info:
- First Year Published: 1986
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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38Evaluation of simulated-LOCA tests that produced large fuel cladding ballooning
By D. A. Powers
“Evaluation of simulated-LOCA tests that produced large fuel cladding ballooning” Metadata:
- Title: ➤ Evaluation of simulated-LOCA tests that produced large fuel cladding ballooning
- Author: D. A. Powers
- Language: English
- Number of Pages: Median: 33
- Publisher: ➤ Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Division of Systems Safety, Core Performance Branch - for sale by the National Technical Information Service
- Publish Date: 1979
- Publish Location: Washington - Springfield, Va
“Evaluation of simulated-LOCA tests that produced large fuel cladding ballooning” Subjects and Themes:
- Subjects: Pressurized water reactors - Nuclear fuel claddings - Cooling - Accidents
Edition Identifiers:
- The Open Library ID: OL17984414M - OL14947640M - OL22392320M
Access and General Info:
- First Year Published: 1979
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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39Assessment of the TRAC-M codes using Flecht-Seaset reflood and steam cooling data
By F Odar
“Assessment of the TRAC-M codes using Flecht-Seaset reflood and steam cooling data” Metadata:
- Title: ➤ Assessment of the TRAC-M codes using Flecht-Seaset reflood and steam cooling data
- Author: F Odar
- Language: English
- Number of Pages: Median: 82
- Publisher: ➤ Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 2001
- Publish Location: Washington, DC
“Assessment of the TRAC-M codes using Flecht-Seaset reflood and steam cooling data” Subjects and Themes:
- Subjects: ➤ Computer programs - Pressurized water reactors - Loss of coolant - Thermodynamics - Steam-boilers - Cooling
Edition Identifiers:
- The Open Library ID: OL18128979M - OL13629495M - OL15342852M
- Online Computer Library Center (OCLC) ID: 50670957
Access and General Info:
- First Year Published: 2001
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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40Voltage-based interim plugging criteria for steam generator tubes
By U.S. Nuclear Regulatory Commission. IPC Task Group
“Voltage-based interim plugging criteria for steam generator tubes” Metadata:
- Title: ➤ Voltage-based interim plugging criteria for steam generator tubes
- Author: ➤ U.S. Nuclear Regulatory Commission. IPC Task Group
- Language: English
- Publisher: ➤ U.S. Nuclear Regulatory Commission
- Publish Date: 1993
- Publish Location: Washington, DC
“Voltage-based interim plugging criteria for steam generator tubes” Subjects and Themes:
- Subjects: Materials - Stress corrosion - Steam-boilers - Pressurized water reactors
Edition Identifiers:
- The Open Library ID: OL14955870M - OL17994485M - OL14448841M
- Online Computer Library Center (OCLC) ID: 30262989
Access and General Info:
- First Year Published: 1993
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
Downloads Are Not Available:
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41USI A-43 regulatory analysis
By A. W. Serkiz
“USI A-43 regulatory analysis” Metadata:
- Title: USI A-43 regulatory analysis
- Author: A. W. Serkiz
- Language: English
- Publisher: ➤ Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission
- Publish Date: 1985
- Publish Location: Washington, D.C
“USI A-43 regulatory analysis” Subjects and Themes:
- Subjects: ➤ Boiling water reactors - Emergency core cooling systems - Pressurized water reactors - Rules and practice - Safety measures - U.S. Nuclear Regulatory Commission
Edition Identifiers:
- The Open Library ID: OL15334954M - OL18045571M - OL17086604M
Access and General Info:
- First Year Published: 1985
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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42Once-through integral system (OTIS)
By J. R. Gloudemans
“Once-through integral system (OTIS)” Metadata:
- Title: ➤ Once-through integral system (OTIS)
- Author: J. R. Gloudemans
- Language: English
- Publisher: ➤ Division of Reactor System Safety, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 1986
- Publish Location: Washington, DC
“Once-through integral system (OTIS)” Subjects and Themes:
- Subjects: Loss of coolant - Nuclear reactor accidents - Pressurized water reactors
- Places: United States
Edition Identifiers:
- The Open Library ID: OL17570026M - OL18050821M - OL15352059M
Access and General Info:
- First Year Published: 1986
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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43Draft regulatory guide DG-1107
By U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research.
“Draft regulatory guide DG-1107” Metadata:
- Title: Draft regulatory guide DG-1107
- Author: ➤ U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research.
- Language: English
- Number of Pages: Median: 30
- Publisher: ➤ U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research
- Publish Date: 2003
- Publish Location: [Washington, D.C.]
“Draft regulatory guide DG-1107” Subjects and Themes:
- Subjects: ➤ Pressurized water reactors - Safety regulations - Loss of coolant - Cooling - Nuclear reactors - Emergency core cooling systems - Standards
- Places: United States
Edition Identifiers:
- The Open Library ID: OL17722958M - OL17621420M - OL18208396M
- Online Computer Library Center (OCLC) ID: 56025473
Access and General Info:
- First Year Published: 2003
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
Downloads Are Not Available:
The book is not public therefore the download links will not allow the download of the entire book, however, borrowing the book online is available.
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44Summary of MELCOR 1.8.2 calculations for three LOCA sequences (AG, S2D, and S3D) at the Surry plant
By L. N. Kmetyk
“Summary of MELCOR 1.8.2 calculations for three LOCA sequences (AG, S2D, and S3D) at the Surry plant” Metadata:
- Title: ➤ Summary of MELCOR 1.8.2 calculations for three LOCA sequences (AG, S2D, and S3D) at the Surry plant
- Author: L. N. Kmetyk
- Language: English
- Number of Pages: Median: 186
- Publisher: ➤ Supt. of Docs., U.S. G.P.O [distributor] - Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 1994
- Publish Location: Washington, DC
“Summary of MELCOR 1.8.2 calculations for three LOCA sequences (AG, S2D, and S3D) at the Surry plant” Subjects and Themes:
- Subjects: Data processing - Loss of coolant - Accidents - Pressurized water reactors - Nuclear power plants
- Places: Virginia - Surry County
Edition Identifiers:
- The Open Library ID: OL15389085M - OL16387404M - OL18066240M
Access and General Info:
- First Year Published: 1994
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
Downloads Are Not Available:
The book is not public therefore the download links will not allow the download of the entire book, however, borrowing the book online is available.
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45Assessment of RELAP5/MOD3.2-NPA3.4 against a transient of high nuclear flux variation reactor trip, natural circulation and the start of a main pump in the VANDELLOS II nuclear power plant
By C Llopis
“Assessment of RELAP5/MOD3.2-NPA3.4 against a transient of high nuclear flux variation reactor trip, natural circulation and the start of a main pump in the VANDELLOS II nuclear power plant” Metadata:
- Title: ➤ Assessment of RELAP5/MOD3.2-NPA3.4 against a transient of high nuclear flux variation reactor trip, natural circulation and the start of a main pump in the VANDELLOS II nuclear power plant
- Author: C Llopis
- Language: English
- Number of Pages: Median: 49
- Publisher: ➤ Supt. of Docs., U.S. G.P.O. [distributor - Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 1998
- Publish Location: Washington, DC
“Assessment of RELAP5/MOD3.2-NPA3.4 against a transient of high nuclear flux variation reactor trip, natural circulation and the start of a main pump in the VANDELLOS II nuclear power plant” Subjects and Themes:
- Subjects: Accidents - Computer simulation - Pressurized water reactors
- Places: Spain
Edition Identifiers:
- The Open Library ID: OL18296196M - OL16132725M - OL13625179M
- Online Computer Library Center (OCLC) ID: 42793035
Access and General Info:
- First Year Published: 1998
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
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46U.S. operating experience with thermally treated Alloy 600 steam generator tubes
By K. J Karwoski
“U.S. operating experience with thermally treated Alloy 600 steam generator tubes” Metadata:
- Title: ➤ U.S. operating experience with thermally treated Alloy 600 steam generator tubes
- Author: K. J Karwoski
- Language: English
- Number of Pages: Median: 251
- Publisher: ➤ Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission - Supt. of Docs., U.S. G.P.O. [distributor]
- Publish Date: 2003
- Publish Location: Washington, DC
“U.S. operating experience with thermally treated Alloy 600 steam generator tubes” Subjects and Themes:
- Subjects: Materials - Stress corrosion - Steam-boilers - Pressurized water reactors
- Places: United States
Edition Identifiers:
- The Open Library ID: OL15392812M - OL13632302M - OL18141388M
- Online Computer Library Center (OCLC) ID: 53126487
Access and General Info:
- First Year Published: 2003
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
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47Analysis of LOFT test L5-1 using RELAP5/MOD2
By S. Cooper
“Analysis of LOFT test L5-1 using RELAP5/MOD2” Metadata:
- Title: ➤ Analysis of LOFT test L5-1 using RELAP5/MOD2
- Author: S. Cooper
- Language: English
- Number of Pages: Median: 34
- Publisher: ➤ Available from Supt. of Docs., U.S. G.P.O. - Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission - National Technical Information Service [distributor
- Publish Date: 1993
- Publish Location: ➤ Washington, DC - Springfield, VA
“Analysis of LOFT test L5-1 using RELAP5/MOD2” Subjects and Themes:
- Subjects: Loss of coolant - Experiments - Pressurized water reactors - LOFT (Nuclear reactor safety test facility)
- Places: Great Britain
Edition Identifiers:
- The Open Library ID: OL14691358M - OL18058137M - OL15372203M
Access and General Info:
- First Year Published: 1993
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
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48Electrochemistry in Light Water Reactors
By D. Féron

“Electrochemistry in Light Water Reactors” Metadata:
- Title: ➤ Electrochemistry in Light Water Reactors
- Author: D. Féron
- Language: English
- Number of Pages: Median: 216
- Publisher: ➤ CRC - Elsevier Science & Technology
- Publish Date: 2007
“Electrochemistry in Light Water Reactors” Subjects and Themes:
- Subjects: ➤ Electrochemistry - Pressurized water reactors - Light water reactors - Industrial Electrochemistry - Corrosion - Electrolytic corrosion - Réacteurs à eau légère - Électrochimie industrielle - Corrosion électrochimique - Electrochemical corrosion - TECHNOLOGY & ENGINEERING - Power Resources - Nuclear
Edition Identifiers:
- The Open Library ID: OL35756048M - OL8484677M - OL37096225M
- Online Computer Library Center (OCLC) ID: 173491188
- All ISBNs: ➤ 9781420054088 - 9781845692407 - 1420054082 - 9781845693022 - 1845692403 - 1845693027
Access and General Info:
- First Year Published: 2007
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
Downloads Are Not Available:
The book is not public therefore the download links will not allow the download of the entire book, however, borrowing the book online is available.
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49Assessment of RELAP5/MOD 2 against 25 dryout experiments conducted at the Royal Institute of Technology
By Anders Sjöberg
“Assessment of RELAP5/MOD 2 against 25 dryout experiments conducted at the Royal Institute of Technology” Metadata:
- Title: ➤ Assessment of RELAP5/MOD 2 against 25 dryout experiments conducted at the Royal Institute of Technology
- Author: Anders Sjöberg
- Language: English
- Number of Pages: Median: 41
- Publisher: ➤ Available from Supt. of Docs., U.S. G.P.O. - National Technical Information Service - Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 1986
- Publish Location: ➤ Washington, DC - Springfield, VA
“Assessment of RELAP5/MOD 2 against 25 dryout experiments conducted at the Royal Institute of Technology” Subjects and Themes:
- Subjects: Critical heat flux - Pressurized water reactors - Thermodynamics
Edition Identifiers:
- The Open Library ID: OL17781491M - OL15268904M - OL14948314M
Access and General Info:
- First Year Published: 1986
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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50The OECD/LOFT Project, achievements and significant results, 9th-11th May 1990, Madrid, Spain =
By Organisation for Economic Co-operation and Development
“The OECD/LOFT Project, achievements and significant results, 9th-11th May 1990, Madrid, Spain =” Metadata:
- Title: ➤ The OECD/LOFT Project, achievements and significant results, 9th-11th May 1990, Madrid, Spain =
- Author: ➤ Organisation for Economic Co-operation and Development
- Language: English
- Number of Pages: Median: 424
- Publisher: ➤ Organisation for Economic Co-Operation and Development - Organization for Economic - OECD Publications and Information Centre [distributor] - Organisation for Economic Co-operation and Development
- Publish Date: 1991
- Publish Location: ➤ Paris, France - Washington, D.C - Paris
“The OECD/LOFT Project, achievements and significant results, 9th-11th May 1990, Madrid, Spain =” Subjects and Themes:
- Subjects: ➤ Safety measures - Nuclear reactors - Congresses - LOFT (Nuclear reactor safety test facility) - Research - Pressurized water reactors - Loss of coolant - Testing
Edition Identifiers:
- The Open Library ID: OL9126298M - OL21201002M - OL1627042M
- Online Computer Library Center (OCLC) ID: 23449736
- Library of Congress Control Number (LCCN): 91174223
- All ISBNs: 9264033394 - 9789264033399
Author's Alternative Names:
"OECD. Organisation for Economic Co-operation and Development.", "Organisation for Economic Cooperation and Development.", "Organisation for Economic Co-operation and Development (OECD)", "Organization for Economic Co-operation and Development (OECD).", "Oecd Organisation for Economic Co-operation and Development", "OECD", "Organisation for Economic Co-Operation and Development Staff", "Oecd Organisation For Economic Cooperation And Development", "Organisation for Economic Cooperation and development.", "Organisation for economic co-operation and development", "Organisation for Economic Co-opertion and Development", "Organisation for Economic Co-operation andDevelopment.", "OECD Organisation for Economic Co-operation and Development", "ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT", "Organisation for Economic Co-operation and Development.", "Organisation for Economic Co-Operation and Development (OECD)", "OECO (Organization for Economic Cooperat", "Oecd", "Organisation for Economic Co-operation and Development (Paris)", "Organization for Economic Cooperation and Development (OECD) Staff", "Organisation for Economic Co-operation and Development Staff", "Organization for Economic Cooperation and Development (OECD)", "ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT.", "Organisation for Economic Co-opertion and Development.", "Organization for Economic Cooperation and Development OECD", "Organization for Economic Co-operation and Development (OECD)", "OECD (Organisation for Economic Co-operation and Development)", "Organisation for Economic Co-Operation and Development", "OECD: Organisation for Economic Co-operation and Development", "Oecd Organisation For Economic Co-Operation And Development", "Organisation For Economic Co-operation and Development.", "Organisation for Economic Co-operation and development.", "ORGANISATION FOR ECONOMIC COOPERATION AND DEVELOPMENT.", "Organisation for Economic co-operation and development", "OCDE Staff", "Organisation for Economic co-operation and Development.", "Organisation for Economic Cooperation and Development", "Organisation for Economic Co-Operation and Development (OECD) Staff", "OCDE. Publie par : editions OCDE", "Organization for Economic Cooperation An", "Organisation for Economic Co-operation and Development (OECD) Staff", "Organisation For Economic Co-Operation And Development.", "OECD Organisation for Economic Co-operation and Develop", "OECD Staff", "Organization For Economic Cooperat OECD", "Organization for Economic Cooperation &", "Organisation for economic cooperation and development.", "Organisation for economic co-operation and development.", "Organisation for Economic Co operation and Development", "Organisation for Economic Co-operation and Development",Access and General Info:
- First Year Published: 1991
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
Downloads Are Not Available:
The book is not public therefore the download links will not allow the download of the entire book, however, borrowing the book online is available.
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Wiki
Source: Wikipedia
Wikipedia Results
Search Results from Wikipedia
Pressurized water reactor
operated pressurized water reactors from 1954 to 1974. Three Mile Island Nuclear Generating Station initially operated two pressurized water reactor plants
Pressurized heavy-water reactor
A pressurized heavy-water reactor (PHWR) is a nuclear reactor that uses heavy water (deuterium oxide D2O) as its coolant and neutron moderator. PHWRs
Light-water reactor
Thermal-neutron reactors are the most common type of nuclear reactor, and light-water reactors are the most common type of thermal-neutron reactor. There are
Nuclear reactor
be boiled to produce pressurized steam for the turbines, like the pressurized water reactor. However, in some reactors the water for the steam turbines
Boiling water reactor
electricity-generating nuclear reactor after the pressurized water reactor (PWR). BWR are thermal neutron reactors, where water is thus used both as a coolant
Scram
commercial reactor operations, this type of shutdown is often referred to as a "scram" at boiling water reactors and a "reactor trip" at pressurized water reactors
Small modular reactor
including generation IV, thermal-neutron reactors, fast-neutron reactors, molten salt, and gas-cooled reactor models. Commercial SMRs have been designed
Heavy-water reactor
may also use this as the coolant, in the case of pressurized heavy water reactors. Due to heavy water's low neutron absorption cross section, HWRs can operate
EPR (nuclear reactor)
"Advanced Nuclear Power Reactors". world-nuclear.org. WNA. Retrieved 6 June 2024. "The European Pressurized Water Reactor: A Safe and Competitive Solution
Framatome
5%). The company first formed in 1958 to license Westinghouse's pressurized water reactor (PWR) designs for use in France. Similar agreements had been put