Explore: Loss Of Coolant
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Books Results
Source: The Open Library
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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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2Assessment 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
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3RELAP5/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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4RELAP5/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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5RELAP5/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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6RELAP5/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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7Assessment 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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8Test 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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9RELAP5/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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10Assessment 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
Online Access
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11RELAP5/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
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12Assessment 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
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13Study 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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14RELAP5/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
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15Viscosity 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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16TRAC-PF1/MOD1 calculations of LOFT experiment LP-02-6
By P. Coddington
“TRAC-PF1/MOD1 calculations of LOFT experiment LP-02-6” Metadata:
- Title: ➤ TRAC-PF1/MOD1 calculations of LOFT experiment LP-02-6
- Author: P. Coddington
- Language: English
- Number of Pages: Median: 262
- Publisher: ➤ National Technical Information Service [distributor - Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission - Available from Supt. of Docs., U.S. G.P.O.
- Publish Date: 1992
- Publish Location: ➤ Springfield, VA - Washington, DC
“TRAC-PF1/MOD1 calculations of LOFT experiment LP-02-6” Subjects and Themes:
- Subjects: Water cooled reactors - Computer simulation - Loss of coolant
Edition Identifiers:
- The Open Library ID: OL15377070M - OL18060262M - OL14694889M
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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17Assessment of RELAP5/MOD3.2 to the loss-of-residual-heat-removal event under shutdown condition
By K. W. Seul
“Assessment of RELAP5/MOD3.2 to the loss-of-residual-heat-removal event under shutdown condition” Metadata:
- Title: ➤ Assessment of RELAP5/MOD3.2 to the loss-of-residual-heat-removal event under shutdown condition
- Author: K. W. Seul
- Language: English
- Number of Pages: Median: 51
- Publisher: ➤ Supt. of Docs., U.S. G.P.O. [distributor] - Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 2000
- Publish Location: Washington, DC
“Assessment of RELAP5/MOD3.2 to the loss-of-residual-heat-removal event under shutdown condition” Subjects and Themes:
- Subjects: ➤ Loss of coolant - Data processing - Mathematical models - Water cooled reactors - Accidents - Thermal analysis - Nuclear power plants
Edition Identifiers:
- The Open Library ID: OL18140739M - OL15573373M - OL17596330M
- Online Computer Library Center (OCLC) ID: 44805793
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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18Assessment 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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19Once-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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20Draft 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
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21Summary 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
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22Analysis 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
Downloads Are Not Available:
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23The 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
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24RELAP5/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: Computer programs - Loss of coolant - Pressurized water reactors - Testing
Edition Identifiers:
- The Open Library ID: OL18296204M - OL16132733M - OL13625228M
- Online Computer Library Center (OCLC) ID: 42793417
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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25RELAP5/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: ➤ 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 SPES test SP-SB-04” Subjects and Themes:
- Subjects: Computer programs - Loss of coolant - Pressurized water reactors - Testing
Edition Identifiers:
- The Open Library ID: OL16132735M - OL18296206M - OL13625461M
- Online Computer Library Center (OCLC) ID: 42793454
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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26Test LOBI-BL06
By T Fiore
“Test LOBI-BL06” Metadata:
- Title: Test LOBI-BL06
- Author: T Fiore
- Language: English
- Number of Pages: Median: 85
- 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
“Test LOBI-BL06” Subjects and Themes:
- Subjects: Loss of coolant - Computer simulation - Evaluation - Pressurized water reactors
Edition Identifiers:
- The Open Library ID: OL16132741M - OL13625462M - OL18296215M
- Online Computer Library Center (OCLC) ID: 42825781
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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27Assessment of LONF ATWS for Maanshan PWR using TRACE code
By Jong-Rong Wang
“Assessment of LONF ATWS for Maanshan PWR using TRACE code” Metadata:
- Title: ➤ Assessment of LONF ATWS for Maanshan PWR using TRACE code
- Author: Jong-Rong Wang
- Language: English
- Number of Pages: Median: 53
- Publisher: ➤ U.S. Nuclear Regulatory Commission
- Publish Date: 2014
- Publish Location: Washington, DC
“Assessment of LONF ATWS for Maanshan PWR using TRACE code” Subjects and Themes:
- Subjects: ➤ Pressurized water reactors - Loss of coolant - Computer simulation - Accidents - Nuclear power plants - Safety measures
- Places: China
Edition Identifiers:
- The Open Library ID: OL43057928M - OL31179322M
- Online Computer Library Center (OCLC) ID: 872581811 - 872581794
- Library of Congress Control Number (LCCN): 2014407537
Access and General Info:
- First Year Published: 2014
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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28The development and assessment of TRACE model for Maanshan Nuclear Power Plant LOCA
By Jong-Rong Wang
“The development and assessment of TRACE model for Maanshan Nuclear Power Plant LOCA” Metadata:
- Title: ➤ The development and assessment of TRACE model for Maanshan Nuclear Power Plant LOCA
- Author: Jong-Rong Wang
- Language: English
- Number of Pages: Median: 49
- Publisher: ➤ U. S. Nuclear Regulatory Commission
- Publish Date: 2012
- Publish Location: Washington, DC
“The development and assessment of TRACE model for Maanshan Nuclear Power Plant LOCA” Subjects and Themes:
- Subjects: ➤ Pressurized water reactors - Loss of coolant - Computer simulation - Accidents - Nuclear power plants - Safety measures
- Places: China
Edition Identifiers:
- The Open Library ID: OL31034259M - OL53816848M
- Online Computer Library Center (OCLC) ID: 835115463 - 835117280
- Library of Congress Control Number (LCCN): 2012515981
Access and General Info:
- First Year Published: 2012
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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29Analysis of the THETIS boildown experiments using RELAP5/MOD2
By M. G. Croxford
“Analysis of the THETIS boildown experiments using RELAP5/MOD2” Metadata:
- Title: ➤ Analysis of the THETIS boildown experiments using RELAP5/MOD2
- Author: M. G. Croxford
- Language: English
- Number of Pages: Median: 35
- Publisher: ➤ Springfield, VA - Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission - National Technical Information Service [distributor
- Publish Date: 1989
- Publish Location: Washington, DC
“Analysis of the THETIS boildown experiments using RELAP5/MOD2” Subjects and Themes:
- Subjects: Loss of coolant - Computer simulation - Pressurized water reactors
Edition Identifiers:
- The Open Library ID: OL14682370M - OL17678901M
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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30Effect of aging on the PWR chemical and volume control system
By E. J. Grove
“Effect of aging on the PWR chemical and volume control system” Metadata:
- Title: ➤ Effect of aging on the PWR chemical and volume control system
- Author: E. J. Grove
- Language: English
- Publisher: ➤ Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission - Supt. of Docs., U.S. G.P.O. [distributor]
- Publish Date: 1995
- Publish Location: Washington, DC
“Effect of aging on the PWR chemical and volume control system” Subjects and Themes:
- Subjects: ➤ Pressurized water reactors - Loss of coolant - Cooling - Reliability - Nuclear reactors - Equipment and supplies
Edition Identifiers:
- The Open Library ID: OL17792180M - OL15413436M
- Online Computer Library Center (OCLC) ID: 34344040
Access and General Info:
- First Year Published: 1995
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
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31TRAC-PF1/MOD1 calculations of LOFT experiment LP-02-6
By P Coddington
“TRAC-PF1/MOD1 calculations of LOFT experiment LP-02-6” Metadata:
- Title: ➤ TRAC-PF1/MOD1 calculations of LOFT experiment LP-02-6
- Author: P Coddington
- Language: English
- Number of Pages: Median: 262
- Publisher: ➤ National Technical Information Service [distributor - Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission - Available from Supt. of Docs., U.S. G.P.O.
- Publish Date: 1992
- Publish Location: ➤ Springfield, VA - Washington, DC
“TRAC-PF1/MOD1 calculations of LOFT experiment LP-02-6” Subjects and Themes:
- Subjects: Water cooled reactors - Computer simulation - Loss of coolant
Edition Identifiers:
- The Open Library ID: OL14809082M - OL17934384M
Access and General Info:
- First Year Published: 1992
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
Downloads Are Not Available:
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32TRAC-PF1/MOD1 post-test calculations of the OECD LOFT experiment LP-SB-3
By E. J. Allen
“TRAC-PF1/MOD1 post-test calculations of the OECD LOFT experiment LP-SB-3” Metadata:
- Title: ➤ TRAC-PF1/MOD1 post-test calculations of the OECD LOFT experiment LP-SB-3
- Author: E. J. Allen
- Language: English
- Publisher: ➤ U.S. Nuclear Regulatory Commission - Available from Supt. of Docs., U.S. G.P.O. - National Technical Information Service
- Publish Date: 1990
- Publish Location: ➤ Springfield, VA - Washington, D.C
“TRAC-PF1/MOD1 post-test calculations of the OECD LOFT experiment LP-SB-3” Subjects and Themes:
- Subjects: ➤ Loss of coolant - Experiments - Pressurized water reactors - Computer programs - Simulation methods - Hydraulic transients - LOFT (Nuclear reactor safety test facility)
Edition Identifiers:
- The Open Library ID: OL17660496M - OL17782339M
- All ISBNs: 0160223458 - 9780160223457
Access and General Info:
- First Year Published: 1990
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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33A study of thermal stratification in the cold legs during the subcooled blowdown phase of a loss of coolant accident in the OSU APEX Thermal Hydraulic Testing Facility
By Daniel M. Wachs
“A study of thermal stratification in the cold legs during the subcooled blowdown phase of a loss of coolant accident in the OSU APEX Thermal Hydraulic Testing Facility” Metadata:
- Title: ➤ A study of thermal stratification in the cold legs during the subcooled blowdown phase of a loss of coolant accident in the OSU APEX Thermal Hydraulic Testing Facility
- Author: Daniel M. Wachs
- Language: English
- Number of Pages: Median: 129
- Publish Date: 1998
“A study of thermal stratification in the cold legs during the subcooled blowdown phase of a loss of coolant accident in the OSU APEX Thermal Hydraulic Testing Facility” Subjects and Themes:
- Subjects: Pressurized water reactors - Loss of coolant - Safety measures - Computer simulation - Cores
Edition Identifiers:
- The Open Library ID: OL18117959M - OL15496020M
Access and General Info:
- First Year Published: 1998
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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34Two-phase fluid break flow measurements and scaling in the advanced plant experiment (APEX)
By David Alan Pimentel
“Two-phase fluid break flow measurements and scaling in the advanced plant experiment (APEX)” Metadata:
- Title: ➤ Two-phase fluid break flow measurements and scaling in the advanced plant experiment (APEX)
- Author: David Alan Pimentel
- Language: English
- Number of Pages: Median: 45
- Publish Date: 1996
“Two-phase fluid break flow measurements and scaling in the advanced plant experiment (APEX)” Subjects and Themes:
- Subjects: Mathematical models - Two-phase flow - Pressurized water reactors - Loss of coolant
Edition Identifiers:
- The Open Library ID: OL18086645M - OL15422702M
Access and General Info:
- First Year Published: 1996
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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35Post-test-analysis and nodalization studies of OECD LOFT experiment LP-02-6 with RELAP5/MOD2 CY36-02
By D. Lübbesmeyer
“Post-test-analysis and nodalization studies of OECD LOFT experiment LP-02-6 with RELAP5/MOD2 CY36-02” Metadata:
- Title: ➤ Post-test-analysis and nodalization studies of OECD LOFT experiment LP-02-6 with RELAP5/MOD2 CY36-02
- Author: D. Lübbesmeyer
- Language: English
- Number of Pages: Median: 178
- Publisher: ➤ National Technical Information Service [distributor - Available from Supt. of Docs., U.S. G.P.O. - Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 1992
- Publish Location: ➤ Washington, DC - Springfield, VA
“Post-test-analysis and nodalization studies of OECD LOFT experiment LP-02-6 with RELAP5/MOD2 CY36-02” Subjects and Themes:
- Subjects: Loss of coolant - Experiments - Pressurized water reactors
Edition Identifiers:
- The Open Library ID: OL15374073M - OL18059286M
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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36Post-test-analysis and nodalization studies of OECD LOFT experiment LP-LB-1 with RELAP5/MOD2 CY36-02
By D. Lübbesmeyer
“Post-test-analysis and nodalization studies of OECD LOFT experiment LP-LB-1 with RELAP5/MOD2 CY36-02” Metadata:
- Title: ➤ Post-test-analysis and nodalization studies of OECD LOFT experiment LP-LB-1 with RELAP5/MOD2 CY36-02
- Author: D. Lübbesmeyer
- Language: English
- Number of Pages: Median: 177
- Publisher: ➤ National Technical Information Service [distributor - Available from Supt. of Docs., U.S. G.P.O. - Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 1992
- Publish Location: ➤ Washington, DC - Springfield, VA
“Post-test-analysis and nodalization studies of OECD LOFT experiment LP-LB-1 with RELAP5/MOD2 CY36-02” Subjects and Themes:
- Subjects: Loss of coolant - Experiments - Pressurized water reactors
Edition Identifiers:
- The Open Library ID: OL18059289M - OL16384459M
Access and General Info:
- First Year Published: 1992
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
Downloads Are Not Available:
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37Component evaluation for intersystem loss-of-coolant accidents in advanced light water reactors
By Arthur G. Ware
“Component evaluation for intersystem loss-of-coolant accidents in advanced light water reactors” Metadata:
- Title: ➤ Component evaluation for intersystem loss-of-coolant accidents in advanced light water reactors
- Author: Arthur G. Ware
- Language: English
- Number of Pages: Median: 61
- Publisher: ➤ Supt. of Docs., U.S. G.P.O. [distributor] - Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 1994
- Publish Location: Washington, DC
“Component evaluation for intersystem loss-of-coolant accidents in advanced light water reactors” Subjects and Themes:
- Subjects: ➤ Light water reactors - Reliability - Loss of coolant - Water cooled reactors - Equipment and supplies - Accidents - Nuclear power plants - Piping
Edition Identifiers:
- The Open Library ID: OL17789590M - OL15396010M
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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38Effects of control system failures on transients, accidents, and core-melt frequencies at a combustion engineering pressurized water reactor
By W. E. Bickford
“Effects of control system failures on transients, accidents, and core-melt frequencies at a combustion engineering pressurized water reactor” Metadata:
- Title: ➤ Effects of control system failures on transients, accidents, and core-melt frequencies at a combustion engineering pressurized water reactor
- Author: W. E. Bickford
- Language: English
- Publisher: ➤ Division of Risk Anlaysis and Operations, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 1986
- Publish Location: Washington, D.C
“Effects of control system failures on transients, accidents, and core-melt frequencies at a combustion engineering pressurized water reactor” Subjects and Themes:
- Subjects: ➤ Pressurized water reactors - Control - Loss of coolant - Safety measures - Nuclear reactors - Transients (Dynamics) - System failures (Engineering)
- Places: United States
Edition Identifiers:
- The Open Library ID: OL15338340M - OL17834065M
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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39Application of RELAP5/MOD3.2 to the loss-of-residual-heat-removal event under shutdown condition
By K. W. Seul
“Application of RELAP5/MOD3.2 to the loss-of-residual-heat-removal event under shutdown condition” Metadata:
- Title: ➤ Application of RELAP5/MOD3.2 to the loss-of-residual-heat-removal event under shutdown condition
- Author: K. W. Seul
- Language: English
- Number of Pages: Median: 53
- Publisher: ➤ 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
“Application of RELAP5/MOD3.2 to the loss-of-residual-heat-removal event under shutdown condition” Subjects and Themes:
- Subjects: ➤ Loss of coolant - Data processing - Mathematical models - Water cooled reactors - Accidents - Thermal analysis - Nuclear power plants
Edition Identifiers:
- The Open Library ID: OL17703848M - OL17596495M
- Online Computer Library Center (OCLC) ID: 45081409
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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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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40Post-test-analysis and nodalization studies of OECD LOFT experiment LP-02-6 with RELAP5/MOD2 CY36-02
By D Lubbesmeyer
“Post-test-analysis and nodalization studies of OECD LOFT experiment LP-02-6 with RELAP5/MOD2 CY36-02” Metadata:
- Title: ➤ Post-test-analysis and nodalization studies of OECD LOFT experiment LP-02-6 with RELAP5/MOD2 CY36-02
- Author: D Lubbesmeyer
- Language: English
- Number of Pages: Median: 178
- Publisher: ➤ National Technical Information Service [distributor - Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission - Available from Supt. of Docs., U.S. G.P.O.
- Publish Date: 1992
- Publish Location: ➤ Springfield, VA - Washington, DC
“Post-test-analysis and nodalization studies of OECD LOFT experiment LP-02-6 with RELAP5/MOD2 CY36-02” Subjects and Themes:
- Subjects: Loss of coolant - Experiments - Pressurized water reactors
Edition Identifiers:
- The Open Library ID: OL14723442M - OL17933824M
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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41Analysis of PANDA experiments P3 and P6 using RELAP5/MOD3.2
By L. Batet
“Analysis of PANDA experiments P3 and P6 using RELAP5/MOD3.2” Metadata:
- Title: ➤ Analysis of PANDA experiments P3 and P6 using RELAP5/MOD3.2
- Author: L. Batet
- Language: English
- Number of Pages: Median: 16
- Publisher: ➤ Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 2001
- Publish Location: Washington, DC
“Analysis of PANDA experiments P3 and P6 using RELAP5/MOD3.2” Subjects and Themes:
- Subjects: Water cooled reactors - Computer simulation - Loss of coolant
Edition Identifiers:
- The Open Library ID: OL17716948M - OL17614764M
- Online Computer Library Center (OCLC) ID: 52537964
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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42The probability of intersystem LOCA
By M. P. Rubin
“The probability of intersystem LOCA” Metadata:
- Title: ➤ The probability of intersystem LOCA
- Author: M. P. Rubin
- Language: English
- Number of Pages: Median: 25
- Publisher: ➤ National Technical Information Service - Division of Systems Safety, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission - Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission
- Publish Date: 1980
- Publish Location: ➤ Springfield, Va - Washington, D.C
“The probability of intersystem LOCA” Subjects and Themes:
- Subjects: Pressurized water reactors - Loss of coolant - Deterioration - Cores
Edition Identifiers:
- The Open Library ID: OL17984487M - OL14947816M
Access and General Info:
- First Year Published: 1980
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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43Drywell debris transport study
By D. V. Rao
“Drywell debris transport study” Metadata:
- Title: Drywell debris transport study
- Author: D. V. Rao
- Language: English
- Publisher: ➤ United States Government Printing Office - U.S. Nuclear Regulatory Commission
- Publish Date: 1999 - 2000
- Publish Location: Washington, DC
“Drywell debris transport study” Subjects and Themes:
- Subjects: ➤ Loss of coolant - Safety measures - Accidents - Boiling water reactors - Containment - Water cooled reactors - Nuclear reactors
Edition Identifiers:
- The Open Library ID: OL17742015M - OL50662193M
- Online Computer Library Center (OCLC) ID: 43473762
- All ISBNs: 9780160501937 - 0160501938
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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44TRAC-PF1 MOD1 post test calculations of the OECD LOFT experiment LP-SB-1 (International agreement report)
By E. J Allen
“TRAC-PF1 MOD1 post test calculations of the OECD LOFT experiment LP-SB-1 (International agreement report)” Metadata:
- Title: ➤ TRAC-PF1 MOD1 post test calculations of the OECD LOFT experiment LP-SB-1 (International agreement report)
- Author: E. J Allen
- Language: English
- Publisher: ➤ National Technical Information Service
- Publish Date: 1990
“TRAC-PF1 MOD1 post test calculations of the OECD LOFT experiment LP-SB-1 (International agreement report)” Subjects and Themes:
- Subjects: ➤ LOFT (Nuclear reactor safety test facility) - Experiments - Pressurized water reactors - Loss of coolant - Computer programs - Transients (Dynamics) - Simulation methods
Edition Identifiers:
- The Open Library ID: OL10108418M
- Online Computer Library Center (OCLC) ID: 22646967
- All ISBNs: 9780160221613 - 0160221617
Access and General Info:
- First Year Published: 1990
- 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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45TRAC-PF1/MOD1 post-test calculations of the OECD LOFT experiment LP-SB-3
By E. J Allen
“TRAC-PF1/MOD1 post-test calculations of the OECD LOFT experiment LP-SB-3” Metadata:
- Title: ➤ TRAC-PF1/MOD1 post-test calculations of the OECD LOFT experiment LP-SB-3
- Author: E. J Allen
- Language: English
- Publisher: ➤ National Technical Information Service - U.S. Nuclear Regulatory Commission - Available from Supt. of Docs., U.S. G.P.O.
- Publish Date: 1990
- Publish Location: ➤ Washington, D.C - Springfield, VA
“TRAC-PF1/MOD1 post-test calculations of the OECD LOFT experiment LP-SB-3” Subjects and Themes:
- Subjects: ➤ Computer programs - Experiments - Hydraulic transients - LOFT (Nuclear reactor safety test facility) - Loss of coolant - Pressurized water reactors - Simulation methods
Edition Identifiers:
- The Open Library ID: OL14660356M
- Online Computer Library Center (OCLC) ID: 23460947
- All ISBNs: 0160223458 - 9780160223457
Access and General Info:
- First Year Published: 1990
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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46SUNYAB/ERPI Combined Injection ECCS Program
By State University College at Buffalo.
“SUNYAB/ERPI Combined Injection ECCS Program” Metadata:
- Title: ➤ SUNYAB/ERPI Combined Injection ECCS Program
- Author: ➤ State University College at Buffalo.
- Language: English
- Number of Pages: Median: 62
- Publisher: EPRI
- Publish Date: 1977
- Publish Location: Palo Alto, Calif
“SUNYAB/ERPI Combined Injection ECCS Program” Subjects and Themes:
Edition Identifiers:
- The Open Library ID: OL4232553M
- Library of Congress Control Number (LCCN): 80513004
Access and General Info:
- First Year Published: 1977
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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47RELAP5 assessment using LSTF test data SB-CL-18
By S. Lee
“RELAP5 assessment using LSTF test data SB-CL-18” Metadata:
- Title: ➤ RELAP5 assessment using LSTF test data SB-CL-18
- Author: S. Lee
- Language: English
- Number of Pages: Median: 206
- Publisher: ➤ National Technical Information Service [distributor - Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission - Available from Supt. of Docs., U.S. G.P.O.
- Publish Date: 1993
- Publish Location: ➤ Springfield, VA - Washington, DC
“RELAP5 assessment using LSTF test data SB-CL-18” Subjects and Themes:
- Subjects: Computer simulation - Loss of coolant - Pressurized water reactors
Edition Identifiers:
- The Open Library ID: OL14690768M
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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48RELAP/MOD2 calculations of OECD-LOFT test LP-SB-01
By P. C Hall
“RELAP/MOD2 calculations of OECD-LOFT test LP-SB-01” Metadata:
- Title: ➤ RELAP/MOD2 calculations of OECD-LOFT test LP-SB-01
- Author: P. C Hall
- Language: English
- Publisher: ➤ Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 1990
- Publish Location: Washington, D.C
“RELAP/MOD2 calculations of OECD-LOFT test LP-SB-01” Subjects and Themes:
- Subjects: ➤ Computer programs - Experiments - Heat - LOFT (Nuclear reactor safety test facility) - Loss of coolant - Pressurized water reactors - Transmission
Edition Identifiers:
- The Open Library ID: OL16132679M
Access and General Info:
- First Year Published: 1990
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
Downloads Are Not Available:
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49Fuel behavior under abnormal conditions
By R. O. Meyer
“Fuel behavior under abnormal conditions” Metadata:
- Title: ➤ Fuel behavior under abnormal conditions
- Author: R. O. Meyer
- Language: English
- Number of Pages: Median: 36
- Publisher: ➤ U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research
- Publish Date: 2013
- Publish Location: Washington, D.C
“Fuel behavior under abnormal conditions” Subjects and Themes:
- Subjects: ➤ Nuclear fuels - Accidents - Analysis - Water cooled reactors - Loss of coolant - Nuclear power plants - Nuclear reactors - Reactivity
Edition Identifiers:
- The Open Library ID: OL53817263M
- Online Computer Library Center (OCLC) ID: 840109451
Access and General Info:
- First Year Published: 2013
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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50Post-test examination results from integral, high-burnup, fueled LOCA tests at Studsvik Nuclear Laboratory
By Michelle E. Flanagan
“Post-test examination results from integral, high-burnup, fueled LOCA tests at Studsvik Nuclear Laboratory” Metadata:
- Title: ➤ Post-test examination results from integral, high-burnup, fueled LOCA tests at Studsvik Nuclear Laboratory
- Author: Michelle E. Flanagan
- Language: English
- Number of Pages: Median: 99
- Publisher: ➤ United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research
- Publish Date: 2013
- Publish Location: Washington, D.C
“Post-test examination results from integral, high-burnup, fueled LOCA tests at Studsvik Nuclear Laboratory” Subjects and Themes:
- Subjects: ➤ Pressurized water reactors - Loss of coolant - Testing - Nuclear power plants - Accidents - Research - Nuclear accidents
- Places: Sweden
Edition Identifiers:
- The Open Library ID: OL55220871M
- Online Computer Library Center (OCLC) ID: 858919506
Access and General Info:
- First Year Published: 2013
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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Wiki
Source: Wikipedia
Wikipedia Results
Search Results from Wikipedia
Loss-of-coolant accident
A loss-of-coolant accident (LOCA) is a mode of failure for a nuclear reactor; if not managed effectively, the results of a LOCA could result in reactor
Nuclear meltdown
A meltdown may be caused by a loss of coolant, loss of coolant pressure, or low coolant flow rate, or be the result of a criticality excursion in which
Soviet submarine K-8
Barents Sea, K-8 suffered a ruptured steam generator tube, causing a loss-of-coolant accident. While the crew jury-rigged a system to supply emergency cooling
Void coefficient
reactor. Voids may also form if coolant is lost from the reactor in some sort of accident (called a loss of coolant accident, which has other dangers)
Coolant
A coolant is a substance, typically liquid, that is used to reduce or regulate the temperature of a system. An ideal coolant has high thermal capacity
Passive nuclear safety
overheating resulting from a loss of coolant or loss of coolant flow). Such design features tend to rely on the engineering of components such that their
Three Mile Island accident
initial failure of plant operators to recognize the situation as a loss-of-coolant accident (LOCA). TMI training and operating procedures left operators
Nuclear submarine
uncontrolled start-up of the ship's reactor led to a fire and the release of radioactivity K-116, 1970: suffered a loss-of-coolant accident in the port
Nuclear navy
needed] K-8 (1960; November-class submarine; loss of coolant) K-19 (1961; Hotel-class submarine; two loss of coolant accidents, 27 killed due to one accident)
Soviet submarine K-19
several of which threatened to sink the submarine. On its initial voyage on 4 July 1961, K-19 suffered a complete loss of coolant to one of its two reactors