Explore: Boiling Water Reactors
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AI-Generated Overview About “boiling-water-reactors”:
Books Results
Source: The Open Library
The Open Library Search Results
Search results from The Open Library
1Meltdown!
By Alfred B. Bortz
“Meltdown!” Metadata:
- Title: Meltdown!
- Author: Alfred B. Bortz
- Language: English
- Number of Pages: Median: 64
- Publisher: ➤ Twenty-First Century Books - Lerner Publishing Group
- Publish Date: 2012 - 2015 - 2017
- Publish Location: Minneapolis
“Meltdown!” Subjects and Themes:
- Subjects: ➤ Safety measures - Nuclear reactor accidents - Boiling water reactors - Tsunami damage - Accidents - Nuclear energy - Nuclear power plants - Juvenile literature - Industrial accidents - Industries, japan - Nuclear reactors
- Places: Japan - Fukushima-ken
Edition Identifiers:
- The Open Library ID: ➤ OL25010997M - OL29725776M - OL29779197M - OL29649347M - OL29778273M - OL29762001M - OL29778476M
- Library of Congress Control Number (LCCN): 2011029692
- All ISBNs: ➤ 9781512452983 - 9780761389194 - 1512452998 - 1512453005 - 9781512457742 - 9780761386605 - 9781512453003 - 1467759333 - 0761386602 - 1512457744 - 9781467759335 - 151245298X - 9781512452990 - 0761389199
Access and General Info:
- First Year Published: 2012
- Is Full Text Available: Yes
- Is The Book Public: No
- Access Status: Borrowable
Online Access
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2The "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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3Water coolant technology of power reactors
By Cohen, P.
“Water coolant technology of power reactors” Metadata:
- Title: ➤ Water coolant technology of power reactors
- Author: Cohen, P.
- Language: English
- Number of Pages: Median: 439
- Publisher: ➤ American Nuclear Society - Gordon and Breach
- Publish Date: 1969 - 1980
- Publish Location: ➤ New York - [La Grange Park, Ill.]
“Water coolant technology of power reactors” Subjects and Themes:
- Subjects: Boiling water reactors - Pressurized water reactors
Edition Identifiers:
- The Open Library ID: OL5754094M - OL4430063M
- Online Computer Library Center (OCLC) ID: 110487 - 6081529
- Library of Congress Control Number (LCCN): 71085210 - 79057306
- All ISBNs: 9780894480201 - 0894480200 - 9780677022406 - 0677022409
Access and General Info:
- First Year Published: 1969
- Is Full Text Available: Yes
- Is The Book Public: No
- Access Status: Borrowable
Online Access
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4Standard 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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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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6An overview of BWR Mark-I containment venting risk implications
By K. C. Wagner
“An overview of BWR Mark-I containment venting risk implications” Metadata:
- Title: ➤ An overview of BWR Mark-I containment venting risk implications
- Author: K. C. Wagner
- Language: English
- Publisher: ➤ Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 1988
- Publish Location: Washington, DC
“An overview of BWR Mark-I containment venting risk implications” Subjects and Themes:
- Subjects: ➤ Nuclear reactors - Safety measures - Risk assessment - Containment - Nuclear power plants - Boiling water reactors
- Places: United States
Edition Identifiers:
- The Open Library ID: OL15387376M - OL15296949M - OL18065276M - OL18034408M
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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7Post-test analysis of P5 experiment in PANDA facility with TRAC-BF1 code
By J. Polo
“Post-test analysis of P5 experiment in PANDA facility with TRAC-BF1 code” Metadata:
- Title: ➤ Post-test analysis of P5 experiment in PANDA facility with TRAC-BF1 code
- Author: J. Polo
- Language: English
- Number of Pages: Median: 18
- 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
“Post-test analysis of P5 experiment in PANDA facility with TRAC-BF1 code” Subjects and Themes:
- Subjects: Testing - Boiling water reactors - Safety appliances
Edition Identifiers:
- The Open Library ID: OL17594227M - OL15565331M - OL22398962M - OL18139536M
- Online Computer Library Center (OCLC) ID: 43955475
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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8TRAC-B thermal-hydraulic analysis of the Black Fox boiling water reactor
By R. P. Martin
“TRAC-B thermal-hydraulic analysis of the Black Fox boiling water reactor” Metadata:
- Title: ➤ TRAC-B thermal-hydraulic analysis of the Black Fox boiling water reactor
- Author: R. P. Martin
- Language: English
- Number of Pages: Median: 48
- Publisher: ➤ Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission - Supt. of Docs., U.S. G.P.O. [distributor
- Publish Date: 1993
- Publish Location: Washington, DC
“TRAC-B thermal-hydraulic analysis of the Black Fox boiling water reactor” Subjects and Themes:
- Subjects: Accidents - Computer simulation - Boiling water reactors - Nuclear power plants
- Places: Oklahoma
Edition Identifiers:
- The Open Library ID: OL14691628M - OL18058272M - OL15372480M
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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9Analysis of long-term station blackout without automatic depressurization at Peach Bottom using MELCOR (version 1.8)
By I. K. Madni
“Analysis of long-term station blackout without automatic depressurization at Peach Bottom using MELCOR (version 1.8)” Metadata:
- Title: ➤ Analysis of long-term station blackout without automatic depressurization at Peach Bottom using MELCOR (version 1.8)
- Author: I. K. Madni
- Language: English
- Number of Pages: Median: 65
- Publisher: ➤ Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission - Supt. of Docs., U.S. G.P.O. [distributor]
- Publish Date: 1994
- Publish Location: Washington, DC
“Analysis of long-term station blackout without automatic depressurization at Peach Bottom using MELCOR (version 1.8)” Subjects and Themes:
- Subjects: Accidents - Boiling water reactors - Data processing - Nuclear power plants - Peach Bottom Atomic Power Station (Pa.)
- Places: Pennsylvania
Edition Identifiers:
- The Open Library ID: OL15391479M - OL14704722M - OL18067370M
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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10Boiling-water reactor internals aging degradation study
By K. H. Luk
“Boiling-water reactor internals aging degradation study” Metadata:
- Title: ➤ Boiling-water reactor internals aging degradation study
- Author: K. H. Luk
- Language: English
- Number of Pages: Median: 43
- 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: 1993
- Publish Location: Washington, DC
“Boiling-water reactor internals aging degradation study” Subjects and Themes:
- Subjects: Materials - Deterioration - Nuclear pressure vessels - Boiling water reactors
Edition Identifiers:
- The Open Library ID: OL17678535M - OL14692584M - OL18059317M
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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11Experimental and numerical stability investigations on natural circulation boiling water reactors
By Christian Pablo Marcel
“Experimental and numerical stability investigations on natural circulation boiling water reactors” Metadata:
- Title: ➤ Experimental and numerical stability investigations on natural circulation boiling water reactors
- Author: Christian Pablo Marcel
- Language: English
- Number of Pages: Median: 141
- Publisher: ➤ Delft University Press, IOS Press
- Publish Date: 2007
- Publish Location: Amsterdam
“Experimental and numerical stability investigations on natural circulation boiling water reactors” Subjects and Themes:
- Subjects: Stability - Boiling water reactors
Edition Identifiers:
- The Open Library ID: OL20749474M - OL18726007M - OL18565851M
- Library of Congress Control Number (LCCN): 2008271965
- All ISBNs: 1586038036 - 9781586038038
Access and General Info:
- First Year Published: 2007
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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12Irradiation-assisted stress corrosion cracking of model austenitic stainless steels irradiated in the Halden reactor
By H. M. Chung
“Irradiation-assisted stress corrosion cracking of model austenitic stainless steels irradiated in the Halden reactor” Metadata:
- Title: ➤ Irradiation-assisted stress corrosion cracking of model austenitic stainless steels irradiated in the Halden reactor
- Author: H. M. Chung
- Language: English
- Number of Pages: Median: 30
- Publisher: ➤ Supt. of Docs., U.S. G.P.O. [distributor] - Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 1999
- Publish Location: Washington, DC
“Irradiation-assisted stress corrosion cracking of model austenitic stainless steels irradiated in the Halden reactor” Subjects and Themes:
- Subjects: Nuclear reactors - Materials - Effect of radiation on - Stress corrosion - Boiling water reactors
Edition Identifiers:
- The Open Library ID: OL17603766M - OL18134324M - OL15546523M
- Online Computer Library Center (OCLC) ID: 42638091
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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13Density-wave instabilities in boiling water reactors
By J. March-Leuba
“Density-wave instabilities in boiling water reactors” Metadata:
- Title: ➤ Density-wave instabilities in boiling water reactors
- Author: J. March-Leuba
- Language: English
- Number of Pages: Median: 45
- Publisher: ➤ Supt. of Docs., U.S. G.P.O. [distributor] - Division of Systems Technology, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission
- Publish Date: 1992
- Publish Location: Washington, DC
“Density-wave instabilities in boiling water reactors” Subjects and Themes:
- Subjects: Density wave theory - Boiling water reactors
Edition Identifiers:
- The Open Library ID: OL15373915M - OL14688217M - OL18059215M
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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14USI 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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15Assessment of modernization and integration of BWR components and spatial kinetics in the TRAC-M, Version 3690, code
By F. Odar
“Assessment of modernization and integration of BWR components and spatial kinetics in the TRAC-M, Version 3690, code” Metadata:
- Title: ➤ Assessment of modernization and integration of BWR components and spatial kinetics in the TRAC-M, Version 3690, code
- Author: F. Odar
- Language: English
- Publisher: ➤ Supt. of Docs., U.S. G.P.O. [distributor] - United States Government Printing Office - Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 2001 - 2002
- Publish Location: Washington, DC
“Assessment of modernization and integration of BWR components and spatial kinetics in the TRAC-M, Version 3690, code” Subjects and Themes:
- Subjects: Evaluation - Computer programs - Accidents - Nuclear power plants - Boiling water reactors
Edition Identifiers:
- The Open Library ID: OL50663095M - OL17620677M - OL17718920M
- Online Computer Library Center (OCLC) ID: 49730476
- All ISBNs: 0160665949 - 9780160665943
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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16Offsite dose calculation manual guidance
By W. Wayne Meinke
“Offsite dose calculation manual guidance” Metadata:
- Title: ➤ Offsite dose calculation manual guidance
- Author: W. Wayne Meinke
- Language: English
- Number of Pages: Median: 116
- Publisher: ➤ Division of Radiation Protection and Emergency Preparedness, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission - Supt. of Docs., U.S. G.P.O. [distributor]
- Publish Date: 1991
- Publish Location: Washington, DC
“Offsite dose calculation manual guidance” Subjects and Themes:
- Subjects: Radiation dosimetry - Radioactive pollution - Boiling water reactors - Measurement
Edition Identifiers:
- The Open Library ID: OL17680542M - OL17623125M - OL13616896M
- Online Computer Library Center (OCLC) ID: 24020739
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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17Boiling water reactors
By Andrew W. Kramer
“Boiling water reactors” Metadata:
- Title: Boiling water reactors
- Author: Andrew W. Kramer
- Language: English
- Number of Pages: Median: 563
- Publisher: Addison-Wesley Pub. Co.
- Publish Date: 1958
- Publish Location: Reading, Mass
“Boiling water reactors” Subjects and Themes:
- Subjects: Boiling water reactors
Edition Identifiers:
- The Open Library ID: OL38587633M - OL6250755M
- Online Computer Library Center (OCLC) ID: 872352
- Library of Congress Control Number (LCCN): 58012603
Access and General Info:
- First Year Published: 1958
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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18Water Chemistry of Nuclear Reactor Systems 4
By British Nuclear Energy Society
“Water Chemistry of Nuclear Reactor Systems 4” Metadata:
- Title: ➤ Water Chemistry of Nuclear Reactor Systems 4
- Author: British Nuclear Energy Society
- Language: English
- Number of Pages: Median: 584
- Publisher: The Society - Unipub
- Publish Date: 1986 - 1989
- Publish Location: London
“Water Chemistry of Nuclear Reactor Systems 4” Subjects and Themes:
- Subjects: ➤ Water chemistry - Water cooled reactors - Water-supply - Congresses - Nuclear power plants - Nuclear reactors - Pressurized water reactors - Boiling water reactors
Edition Identifiers:
- The Open Library ID: OL10591240M - OL21161153M
- Online Computer Library Center (OCLC) ID: 14243804
- Library of Congress Control Number (LCCN): gb86025323
- All ISBNs: 9780727702029 - 0727702025 - 9780727703705 - 0727703706
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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19MARK II containment lead plant program load evaluation and acceptance criteria
By C. Anderson
“MARK II containment lead plant program load evaluation and acceptance criteria” Metadata:
- Title: ➤ MARK II containment lead plant program load evaluation and acceptance criteria
- Author: C. Anderson
- Language: English
- Number of Pages: Median: 15
- Publisher: ➤ Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission - National Technical Information Service - National Information Service - Division of Safety Technology, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission
- Publish Date: 1980 - 1981
- Publish Location: ➤ Springfield, Va - Washington, D.C
“MARK II containment lead plant program load evaluation and acceptance criteria” Subjects and Themes:
- Subjects: Boiling water reactors - Containment - Nuclear reactors - Safety measures
- Places: United States
Edition Identifiers:
- The Open Library ID: OL16139872M - OL14947603M
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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20Assessment and management of ageing of major nuclear power plant components important to safety
By International Atomic Energy Agency
“Assessment and management of ageing of major nuclear power plant components important to safety” Metadata:
- Title: ➤ Assessment and management of ageing of major nuclear power plant components important to safety
- Author: ➤ International Atomic Energy Agency
- Language: English
- Number of Pages: Median: 107
- Publisher: ➤ Intl Atomic Energy Agency - International Atomic Energy Agency
- Publish Date: 2005
- Publish Location: Vienna
“Assessment and management of ageing of major nuclear power plant components important to safety” Subjects and Themes:
- Subjects: ➤ Boiling water reactors - Risk assessment - Nuclear pressure vessels - Equipment and supplies - Reliability - Maintenance and repair - Deterioration - Materials - Nuclear power plants
Edition Identifiers:
- The Open Library ID: OL18253629M - OL12857901M
- Online Computer Library Center (OCLC) ID: 63661431
- All ISBNs: 9201092059 - 9789201092052
Access and General Info:
- First Year Published: 2005
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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21Identification and assessment of containment and release management strategies for a BWR Mark I containment
By C. C. Lin
“Identification and assessment of containment and release management strategies for a BWR Mark I containment” Metadata:
- Title: ➤ Identification and assessment of containment and release management strategies for a BWR Mark I containment
- Author: C. C. Lin
- Language: English
- Publisher: ➤ Division of Systems Research, 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
“Identification and assessment of containment and release management strategies for a BWR Mark I containment” Subjects and Themes:
- Subjects: Boiling water reactors - Safety measures - Accidents - Nuclear reactors - Containment
Edition Identifiers:
- The Open Library ID: OL16384741M - OL17678656M
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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22Identification and assessment of containment and release management strategies for a BWR Mark III containment
By C. C. Lin
“Identification and assessment of containment and release management strategies for a BWR Mark III containment” Metadata:
- Title: ➤ Identification and assessment of containment and release management strategies for a BWR Mark III containment
- Author: C. C. Lin
- Language: English
- Publisher: ➤ Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission - Supt. of Docs., U.S. G.P.O. [distributor]
- Publish Date: 1992
- Publish Location: Washington, DC
“Identification and assessment of containment and release management strategies for a BWR Mark III containment” Subjects and Themes:
- Subjects: Boiling water reactors - Safety measures - Accidents - Nuclear reactors - Containment
Edition Identifiers:
- The Open Library ID: OL17679801M - OL14697912M
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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23Integrated plant safety assessment, systematic evaluation program, La Crosse Boiling Water Reactor, Dairyland Power Cooperative, docket no. 50-409
By U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation.
“Integrated plant safety assessment, systematic evaluation program, La Crosse Boiling Water Reactor, Dairyland Power Cooperative, docket no. 50-409” Metadata:
- Title: ➤ Integrated plant safety assessment, systematic evaluation program, La Crosse Boiling Water Reactor, Dairyland Power Cooperative, docket no. 50-409
- Author: ➤ U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation.
- Language: English
- Publisher: ➤ U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation
- Publish Date: 1983 - 1986
- Publish Location: Washington, D.C
“Integrated plant safety assessment, systematic evaluation program, La Crosse Boiling Water Reactor, Dairyland Power Cooperative, docket no. 50-409” Subjects and Themes:
- Subjects: Safety measures - Nuclear power plants - Nuclear facilities - Boiling water reactors - Design and construction
- Places: Wisconsin
Edition Identifiers:
- The Open Library ID: OL14947966M - OL14947970M
Author's Alternative Names:
"U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation"Access and General Info:
- First Year Published: 1983
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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24Standard 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 - Supt. of Docs., U.S. G.P.O. [distributor - U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation
- Publish Date: 1995
- Publish Location: ➤ Washington, DC - [Washington, DC]
“Standard technical specifications” Subjects and Themes:
- Subjects: Boiling water reactors - Design and construction - General Electric Company - Nuclear power plants - Specifications
- Places: United States
Edition Identifiers:
- The Open Library ID: OL16121884M - OL16115941M
Author's Alternative Names:
"U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation"Access and General Info:
- First Year Published: 1995
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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25Assessment of the turbine trip transient in Cofrentes NPP with TRAC-BF1
By F. Castrillo
“Assessment of the turbine trip transient in Cofrentes NPP with TRAC-BF1” Metadata:
- Title: ➤ Assessment of the turbine trip transient in Cofrentes NPP with TRAC-BF1
- Author: F. Castrillo
- Language: English
- 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
“Assessment of the turbine trip transient in Cofrentes NPP with TRAC-BF1” Subjects and Themes:
- Subjects: Computer simulation - Accidents - Boiling water reactors - Nuclear reactor accidents - Nuclear reactors
- Places: Spain
Edition Identifiers:
- The Open Library ID: OL14692787M - OL17678570M
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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26LAPUR5.2 verification and user's manual
By A. Escrivá
“LAPUR5.2 verification and user's manual” Metadata:
- Title: ➤ LAPUR5.2 verification and user's manual
- Author: A. Escrivá
- Language: English
- Number of Pages: Median: 99
- Publisher: ➤ Division of Systems Safety and Analysis, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission
- Publish Date: 2001
- Publish Location: Washington, DC
“LAPUR5.2 verification and user's manual” Subjects and Themes:
- Subjects: Boiling water reactors - Computer programs - Handbooks, manuals - Handbooks, manuals, etc - Mathematical models
Edition Identifiers:
- The Open Library ID: OL17718304M - OL18166949M
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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27Applications of reliability degradation analysis
By W. E. Vesley
“Applications of reliability degradation analysis” Metadata:
- Title: ➤ Applications of reliability degradation analysis
- Author: W. E. Vesley
- 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: 1996
- Publish Location: Washington, DC
“Applications of reliability degradation analysis” Subjects and Themes:
- Subjects: Reliability - Pressurized water reactors - Nuclear reactors - Boiling water reactors - Containment
Edition Identifiers:
- The Open Library ID: OL15422279M - OL17796162M
- Online Computer Library Center (OCLC) ID: 34937583
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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28A simplified model of decontamination by BWR steam suppression pools
By D. A. Powers
“A simplified model of decontamination by BWR steam suppression pools” Metadata:
- Title: ➤ A simplified model of decontamination by BWR steam suppression pools
- Author: D. A. Powers
- Language: English
- Number of Pages: Median: 438
- Publisher: ➤ United States Government Printing Office - Division of Systems Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 1997
- Publish Location: Washington, D.C
“A simplified model of decontamination by BWR steam suppression pools” Subjects and Themes:
Edition Identifiers:
- The Open Library ID: OL50666737M - OL16045093M
- All ISBNs: 0160628415 - 9780160628412
Access and General Info:
- First Year Published: 1997
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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29Value-impact analysis of regulatory options for resolution of generic issue C-8
By J. D. Jamison
“Value-impact analysis of regulatory options for resolution of generic issue C-8” Metadata:
- Title: ➤ Value-impact analysis of regulatory options for resolution of generic issue C-8
- Author: J. D. Jamison
- Language: English
- Publisher: ➤ Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 1990
- Publish Location: Washington, DC
“Value-impact analysis of regulatory options for resolution of generic issue C-8” Subjects and Themes:
- Subjects: ➤ Piping - Nuclear power plants - Safety measures - Inspection - Values - Boiling water reactors - Maintainability - Evaluation
Edition Identifiers:
- The Open Library ID: OL15368961M - OL18056625M
Access and General Info:
- First Year Published: 1990
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
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30The management of ATWS by boron injection
By M. P. Dias
“The management of ATWS by boron injection” Metadata:
- Title: ➤ The management of ATWS by boron injection
- Author: M. P. Dias
- Language: English
- Number of Pages: Median: 27
- Publisher: ➤ Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission - Supt. of Docs., U.S. G.P.O. [distributor
- Publish Date: 1993
- Publish Location: Washington, DC
“The management of ATWS by boron injection” Subjects and Themes:
- Subjects: Safety measures - Nuclear power plants - Boiling water reactors
- Places: United States
Edition Identifiers:
- The Open Library ID: OL14688751M - OL17677521M
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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31Risk impact of BWR technical specifications requirements during shutdown
By B. D. Staple
“Risk impact of BWR technical specifications requirements during shutdown” Metadata:
- Title: ➤ Risk impact of BWR technical specifications requirements during shutdown
- Author: B. D. Staple
- Language: English
- Number of Pages: Median: 74
- Publisher: ➤ Supt. of Docs., U.S. G.P.O. [distributor] - Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 1994
- Publish Location: Washington, DC
“Risk impact of BWR technical specifications requirements during shutdown” Subjects and Themes:
- Subjects: Specifications - Nuclear power plants - Risk assessment - Boiling water reactors
Edition Identifiers:
- The Open Library ID: OL17789724M - OL15397440M
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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32The DF-4 fuel damage experiment in ACRR with a BWR control blade and channel box
By Randall Owen Gauntt
“The DF-4 fuel damage experiment in ACRR with a BWR control blade and channel box” Metadata:
- Title: ➤ The DF-4 fuel damage experiment in ACRR with a BWR control blade and channel box
- Author: Randall Owen Gauntt
- Language: English
- Publisher: ➤ Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 1989
- Publish Location: Washington, DC
“The DF-4 fuel damage experiment in ACRR with a BWR control blade and channel box” Subjects and Themes:
- Subjects: Experiments - Nuclear fuel elements - Boiling water reactors
Edition Identifiers:
- The Open Library ID: OL18027221M - OL15270823M
Access and General Info:
- First Year Published: 1989
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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33Estimating boiling water reactor decommissioning costs
By M. C. Bierschbach
“Estimating boiling water reactor decommissioning costs” Metadata:
- Title: ➤ Estimating boiling water reactor decommissioning costs
- Author: M. C. Bierschbach
- Language: English
- Publisher: ➤ Division of Regulatory Applications, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commssion - Supt. of Docs., U.S. G.P.O. [distributor] - U.S. Nuclear Regulatory Commission
- Publish Date: 1994 - 1996
- Publish Location: Washington, DC
“Estimating boiling water reactor decommissioning costs” Subjects and Themes:
- Subjects: ➤ Costs - Decommissioning - Handbooks, manuals - Computer programs - Nuclear reactors - Boiling water reactors - Boilng water reactors - Data processing
- Places: United States
Edition Identifiers:
- The Open Library ID: OL15445494M - OL16983512M
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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34Systems summary of a Westinghouse pressurized water reactor nuclear power plant
By George Masche
“Systems summary of a Westinghouse pressurized water reactor nuclear power plant” Metadata:
- Title: ➤ Systems summary of a Westinghouse pressurized water reactor nuclear power plant
- Author: George Masche
- Language: English
- Number of Pages: Median: 238
- Publisher: ➤ Westinghouse Nuclear Energy Systems
- Publish Date: 1971
- Publish Location: [Pittsburgh
“Systems summary of a Westinghouse pressurized water reactor nuclear power plant” Subjects and Themes:
- Subjects: Thermodynamics - Nuclear power plants - Boiling water reactors
Edition Identifiers:
- The Open Library ID: OL14373625M
Access and General Info:
- First Year Published: 1971
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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35Estimated safety significance of generic safety issue 61
By J. R. Lehner
“Estimated safety significance of generic safety issue 61” Metadata:
- Title: ➤ Estimated safety significance of generic safety issue 61
- Author: J. R. Lehner
- Language: English
- Number of Pages: Median: 57
- Publisher: ➤ Division of Safety Review and Oversight, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission
- Publish Date: 1986
- Publish Location: Washington, D.C
“Estimated safety significance of generic safety issue 61” Subjects and Themes:
- Subjects: Boiling water reactors - Safety measures - Accidents - Nuclear reactors - Containment
- Places: United States
Edition Identifiers:
- The Open Library ID: OL15335101M - OL17833653M
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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36USI 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: OL17984532M - OL14948015M
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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37Report of the U.S. Nuclear Regulatory Commission Piping Review Committee
By U.S. Nuclear Regulatory Commission. Piping Review Committee. Pipe Crack Task Group
“Report of the U.S. Nuclear Regulatory Commission Piping Review Committee” Metadata:
- Title: ➤ Report of the U.S. Nuclear Regulatory Commission Piping Review Committee
- Author: ➤ U.S. Nuclear Regulatory Commission. Piping Review Committee. Pipe Crack Task Group
- Language: English
- Publisher: The Committee
- Publish Date: 1984
- Publish Location: Washington, D.C
“Report of the U.S. Nuclear Regulatory Commission Piping Review Committee” Subjects and Themes:
- Subjects: Boiling water reactors - Nuclear power plants - Pipe, Steel - Safety measures - Steel Pipe
- Places: United States
Edition Identifiers:
- The Open Library ID: OL14948133M - OL17984596M
Access and General Info:
- First Year Published: 1984
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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38Assessment of single recirculation pump trip transient in Santa Maria de Garona Nuclear Power Plant with TRAC-BF1/MOD1, version 0.4
By C. García de la Rúa
“Assessment of single recirculation pump trip transient in Santa Maria de Garona Nuclear Power Plant with TRAC-BF1/MOD1, version 0.4” Metadata:
- Title: ➤ Assessment of single recirculation pump trip transient in Santa Maria de Garona Nuclear Power Plant with TRAC-BF1/MOD1, version 0.4
- Author: C. García de la Rúa
- Language: English
- Number of Pages: Median: 38
- Publisher: ➤ Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 2001
- Publish Location: Washington, DC
“Assessment of single recirculation pump trip transient in Santa Maria de Garona Nuclear Power Plant with TRAC-BF1/MOD1, version 0.4” Subjects and Themes:
- Subjects: Accidents - Computer simulation - Boiling water reactors
- Places: Spain
Edition Identifiers:
- The Open Library ID: OL16098447M - OL17617843M
- Online Computer Library Center (OCLC) ID: 53243996
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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39Mark III LOCA-related hydrodynamic load definition
By M. B Fields
“Mark III LOCA-related hydrodynamic load definition” Metadata:
- Title: ➤ Mark III LOCA-related hydrodynamic load definition
- Author: M. B Fields
- Language: English
- Publisher: ➤ Division of Systems Integration, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission
- Publish Date: 1984
- Publish Location: Washington D.C
“Mark III LOCA-related hydrodynamic load definition” Subjects and Themes:
- Subjects: Safety measures - Nuclear reactors - Hydrodynamics - Boiling water reactors - Containment
- Places: United States
Edition Identifiers:
- The Open Library ID: OL16100257M - OL18288185M
Access and General Info:
- First Year Published: 1984
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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40Drywell 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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41Experimental assessments of Gundremmingen RPV archive material for fluence rate effects studies
By J. R. Hawthorne
“Experimental assessments of Gundremmingen RPV archive material for fluence rate effects studies” Metadata:
- Title: ➤ Experimental assessments of Gundremmingen RPV archive material for fluence rate effects studies
- Author: J. R. Hawthorne
- Language: English
- Publisher: ➤ Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 1988
- Publish Location: Washington, DC
“Experimental assessments of Gundremmingen RPV archive material for fluence rate effects studies” Subjects and Themes:
- Subjects: Boiling water reactors - Decommissioning - Nuclear reactors
Edition Identifiers:
- The Open Library ID: OL15367578M - OL17748651M
- Online Computer Library Center (OCLC) ID: 28118455
Author's Alternative Names:
"J. R Hawthorne"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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42The thermal-hydraulics of a boiling water nuclear reactor
By Richard T. Lahey
“The thermal-hydraulics of a boiling water nuclear reactor” Metadata:
- Title: ➤ The thermal-hydraulics of a boiling water nuclear reactor
- Author: Richard T. Lahey
- Language: English
- Number of Pages: Median: 532
- Publisher: ➤ The Society - American Nuclear Society
- Publish Date: 1977 - 1993
- Publish Location: ➤ La Grange Park, Ill., USA - [Hinsdale, Ill.]
“The thermal-hydraulics of a boiling water nuclear reactor” Subjects and Themes:
- Subjects: ➤ Boiling water reactors - Fluid dynamics - Heat - Nuclear reactors - Transmission - Hydrodynamics - Thermodynamics - Nuclear engineering
Edition Identifiers:
- The Open Library ID: OL4901192M - OL1404624M
- Online Computer Library Center (OCLC) ID: 3556562
- Library of Congress Control Number (LCCN): 93012785 - 76045712
- All ISBNs: 0894480375 - 0894480103 - 9780894480379 - 9780894480102
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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43Final environmental statement related to primary cooling system chemical decontamination at Dresden Nuclear Power Station, Unit no. 1, Docket no. 50-10, Commonwealth Edison Company
By U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation.
“Final environmental statement related to primary cooling system chemical decontamination at Dresden Nuclear Power Station, Unit no. 1, Docket no. 50-10, Commonwealth Edison Company” Metadata:
- Title: ➤ Final environmental statement related to primary cooling system chemical decontamination at Dresden Nuclear Power Station, Unit no. 1, Docket no. 50-10, Commonwealth Edison Company
- Author: ➤ U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation.
- Language: English
- Number of Pages: Median: 238
- Publisher: ➤ National Technical Information Service - Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission - The Office
- Publish Date: 1980
- Publish Location: ➤ Washington, D.C - Springfield, Va
“Final environmental statement related to primary cooling system chemical decontamination at Dresden Nuclear Power Station, Unit no. 1, Docket no. 50-10, Commonwealth Edison Company” Subjects and Themes:
- Subjects: ➤ Boiling water reactors - Cooling systems - Environmental aspects of Nuclear power plants - Nuclear power plants - Radioactive decontamination
- Places: Illinois
Edition Identifiers:
- The Open Library ID: OL22391607M
Author's Alternative Names:
"U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation"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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44Integrated plant safety assessment, systematic evaluation program, La Crosse Boiling Water Reactor, Dairyland Power Cooperative, docket no. 50-409
By U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation.
“Integrated plant safety assessment, systematic evaluation program, La Crosse Boiling Water Reactor, Dairyland Power Cooperative, docket no. 50-409” Metadata:
- Title: ➤ Integrated plant safety assessment, systematic evaluation program, La Crosse Boiling Water Reactor, Dairyland Power Cooperative, docket no. 50-409
- Author: ➤ U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation.
- Language: English
- Publisher: ➤ U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation
- Publish Date: 1986
- Publish Location: Washington, D.C
“Integrated plant safety assessment, systematic evaluation program, La Crosse Boiling Water Reactor, Dairyland Power Cooperative, docket no. 50-409” Subjects and Themes:
- Subjects: Boiling water reactors - Nuclear power plants - Safety measures
- Places: Wisconsin
Edition Identifiers:
- The Open Library ID: OL17670273M
Author's Alternative Names:
"U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation"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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45A critical literature study on scaling laws for heat transfer
By Rolf Andersen
“A critical literature study on scaling laws for heat transfer” Metadata:
- Title: ➤ A critical literature study on scaling laws for heat transfer
- Author: Rolf Andersen
- Language: English
- Number of Pages: Median: 123
- Publisher: (Gjellerups Boghandel
- Publish Date: 1970
- Publish Location: Copenhagen
“A critical literature study on scaling laws for heat transfer” Subjects and Themes:
- Subjects: ➤ Boiling water reactors - Heat - Scaling laws (Statistical physics) - Transmission - Two-phase flow
Edition Identifiers:
- The Open Library ID: OL3918239M
- Library of Congress Control Number (LCCN): 81484393
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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46The burn-up routine in the transport code FLEF
By A. Rumpold
“The burn-up routine in the transport code FLEF” Metadata:
- Title: ➤ The burn-up routine in the transport code FLEF
- Author: A. Rumpold
- Language: English
- Number of Pages: Median: 49
- Publisher: Institutt for Atomenergi]
- Publish Date: 1967
- Publish Location: [Halden
“The burn-up routine in the transport code FLEF” Subjects and Themes:
- Subjects: Boiling water reactors - Nuclear fuels
Edition Identifiers:
- The Open Library ID: OL5667156M
- Library of Congress Control Number (LCCN): 68119893
Access and General Info:
- First Year Published: 1967
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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47Observations of fuel pin internal pressure
By M. Hurme
“Observations of fuel pin internal pressure” Metadata:
- Title: ➤ Observations of fuel pin internal pressure
- Author: M. Hurme
- Language: English
- Number of Pages: Median: 37
- Publish Date: 1969
- Publish Location: Halden
“Observations of fuel pin internal pressure” Subjects and Themes:
- Subjects: Pressure - Nuclear fuel elements - Boiling water reactors - Measurement
Edition Identifiers:
- The Open Library ID: OL5734010M
- Library of Congress Control Number (LCCN): 70557509
Access and General Info:
- First Year Published: 1969
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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48Ustoĭchivostʹ kipi͡a︡shchikh apparatov
By Ivan Ivanovich Morozov
“Ustoĭchivostʹ kipi͡a︡shchikh apparatov” Metadata:
- Title: ➤ Ustoĭchivostʹ kipi͡a︡shchikh apparatov
- Author: Ivan Ivanovich Morozov
- Language: rus
- Number of Pages: Median: 280
- Publisher: Atomizdat
- Publish Date: 1969
- Publish Location: Moskva
“Ustoĭchivostʹ kipi͡a︡shchikh apparatov” Subjects and Themes:
- Subjects: Boiling water reactors - Heat exchangers
Edition Identifiers:
- The Open Library ID: OL5730068M
- Online Computer Library Center (OCLC) ID: 6879801
- Library of Congress Control Number (LCCN): 70509516
Access and General Info:
- First Year Published: 1969
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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49Summary of the experience from the 1964-66 experimental operation of the HBWR
By Symposium on Heavy-Water Power Reactors Vienna 1967.
“Summary of the experience from the 1964-66 experimental operation of the HBWR” Metadata:
- Title: ➤ Summary of the experience from the 1964-66 experimental operation of the HBWR
- Author: ➤ Symposium on Heavy-Water Power Reactors Vienna 1967.
- Language: English
- Publisher: Institutt for atomenergi
- Publish Date: 1967
- Publish Location: [Halden
“Summary of the experience from the 1964-66 experimental operation of the HBWR” Subjects and Themes:
- Subjects: Boiling water reactors - Congresses
Edition Identifiers:
- The Open Library ID: OL5737585M
- Library of Congress Control Number (LCCN): 70599386
Access and General Info:
- First Year Published: 1967
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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50Experimental burn-out and hydraulic instability investigations
By E. Rolstad
“Experimental burn-out and hydraulic instability investigations” Metadata:
- Title: ➤ Experimental burn-out and hydraulic instability investigations
- Author: E. Rolstad
- Language: English
- Number of Pages: Median: 91
- Publish Date: 1967
- Publish Location: [Halden]
“Experimental burn-out and hydraulic instability investigations” Subjects and Themes:
- Subjects: Boiling water reactors
Edition Identifiers:
- The Open Library ID: OL5659911M
- Library of Congress Control Number (LCCN): 68106508
Access and General Info:
- First Year Published: 1967
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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