Explore: Water Cooled Reactors
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AI-Generated Overview About “water-cooled-reactors”:
Books Results
Source: The Open Library
The Open Library Search Results
Search results from The Open Library
1The gentle killers
By Ralph Graeub
“The gentle killers” Metadata:
- Title: The gentle killers
- Author: Ralph Graeub
- Language: English
- Number of Pages: Median: 194
- Publisher: Abelard-Schuman
- Publish Date: 1974
- Publish Location: London
“The gentle killers” Subjects and Themes:
- Subjects: ➤ Accidents - Health aspects - Health aspects of Nuclear power plants - Nuclear power plants - Radiation - Radioactive pollution - Toxicology - Water cooled reactors - Environmental aspects
Edition Identifiers:
- The Open Library ID: OL5114215M
- Library of Congress Control Number (LCCN): 74186942
- All ISBNs: 0200719572 - 9780200719575
Access and General Info:
- First Year Published: 1974
- Is Full Text Available: Yes
- Is The Book Public: No
- Access Status: Borrowable
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2TRAC-M validation test matrix
By B. E. Boyack
“TRAC-M validation test matrix” Metadata:
- Title: TRAC-M validation test matrix
- Author: B. E. Boyack
- Language: English
- Publisher: ➤ United States Government Printing Office - U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research - Division of System Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 2001
- Publish Location: ➤ Washington, D.C - Washington, DC
“TRAC-M validation test matrix” Subjects and Themes:
- Subjects: Forecasting - Accidents - Computer programs - Water cooled reactors - Pressurized water reactors
Edition Identifiers:
- The Open Library ID: OL18166952M - OL16024723M - OL17614753M - OL50666828M
- Online Computer Library Center (OCLC) ID: 50678819
- All ISBNs: 0160664438 - 9780160664434
Access and General Info:
- First Year Published: 2001
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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3Proceedings of the U.S. Nuclear Regulatory Commission
By Water Reactor Safety Information Meeting (25th 1997 Bethesda, Md.)
“Proceedings of the U.S. Nuclear Regulatory Commission” Metadata:
- Title: ➤ Proceedings of the U.S. Nuclear Regulatory Commission
- Author: ➤ Water Reactor Safety Information Meeting (25th 1997 Bethesda, Md.)
- Language: English
- Publisher: ➤ Supt. of Docs., U.S. G.P.O. [distributor - Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 1998
- Publish Location: Washington, DC
“Proceedings of the U.S. Nuclear Regulatory Commission” Subjects and Themes:
- Subjects: ➤ Congresses - Safety measures - Nuclear reactor accidents - Risk assessment - Water cooled reactors - Nuclear power plants
Edition Identifiers:
- The Open Library ID: OL17131325M - OL15541606M - OL18132511M - OL17580397M
- Online Computer Library Center (OCLC) ID: 41434128
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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4TRAC-M programmer's guide
By R. G. Steinke
“TRAC-M programmer's guide” Metadata:
- Title: TRAC-M programmer's guide
- Author: R. G. Steinke
- Language: English
- Publisher: ➤ Supt. of Docs., U.S. G.P.O. [distributor] - Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission - U.S. Nuclear Regulatory Commission
- Publish Date: 1999
- Publish Location: Washington, DC
“TRAC-M programmer's guide” Subjects and Themes:
- Subjects: ➤ Computer programs - Forecasting - Accidents - Pressurized water reactors - Water cooled reactors - Safety measures
Edition Identifiers:
- The Open Library ID: OL15561159M - OL16320516M - OL17603925M - OL18138803M
- Online Computer Library Center (OCLC) ID: 43618801 - 43363480
Access and General Info:
- First Year Published: 1999
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
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5Proceedings of the Eighth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors
By International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors (8th 1997 Amelia Island, Fla.)
“Proceedings of the Eighth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors” Metadata:
- Title: ➤ Proceedings of the Eighth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors
- Author: ➤ International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors (8th 1997 Amelia Island, Fla.)
- Language: English
- Number of Pages: Median: 1071
- Publisher: ➤ Amer Nuclear Society - American Nuclear Society
- Publish Date: 1997
- Publish Location: La Grange Park, Ill
“Proceedings of the Eighth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors” Subjects and Themes:
- Subjects: ➤ Congresses - Corrosion - Effect of radiation on - Materials - Nuclear power plants - Water cooled reactors
Edition Identifiers:
- The Open Library ID: OL8248740M - OL3774780M
- Online Computer Library Center (OCLC) ID: 45256101
- Library of Congress Control Number (LCCN): 2003535054
- All ISBNs: 9780894486265 - 0894486268
Access and General Info:
- First Year Published: 1997
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
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6The Department of Energy's water-cooled breeder program
should it continue? : report to the Congress
By United States. General Accounting Office
“The Department of Energy's water-cooled breeder program” Metadata:
- Title: ➤ The Department of Energy's water-cooled breeder program
- Author: ➤ United States. General Accounting Office
- Language: English
- Number of Pages: Median: 48
- Publisher: U.S. General Accounting Office
- Publish Date: 1981
- Publish Location: Washington, D.C
“The Department of Energy's water-cooled breeder program” Subjects and Themes:
- Subjects: United States - Water cooled reactors - Nuclear reactors - United States. Dept. of Energy
- Places: United States
Edition Identifiers:
- The Open Library ID: OL15981262M - OL17824055M - OL17652433M
- Online Computer Library Center (OCLC) ID: 9401259
Author's Alternative Names:
"U S. General Accounting Office", "U.S. General Accounting Office", "United States General Accounting Office ", "United States General Accounting Office.", "General Accounting Office (U.S.)", "United States. General of Accounting Office.", "United States. General Accounting Office.", "General Accounting Office.", "U.S. General Accounting Office.", "General Accountability Office (U.S.)" and "United States. General Accounting OFfice.",Access and General Info:
- First Year Published: 1981
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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7TRAC-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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8Assessment 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
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9Transactions of the Twenty-fifth Water Reactor Safety Information Meeting
By Water Reactor Safety Information Meeting (25th 1997 Bethesda, Md.)
“Transactions of the Twenty-fifth Water Reactor Safety Information Meeting” Metadata:
- Title: ➤ Transactions of the Twenty-fifth Water Reactor Safety Information Meeting
- Author: ➤ Water Reactor Safety Information Meeting (25th 1997 Bethesda, Md.)
- Language: English
- Number of Pages: Median: 132
- Publisher: ➤ Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission - Supt. of Docs., U.S. G.P.O. [distributor]
- Publish Date: 1997
- Publish Location: Washington, DC
“Transactions of the Twenty-fifth Water Reactor Safety Information Meeting” Subjects and Themes:
- Subjects: ➤ Congresses - Safety measures - Nuclear reactor accidents - Risk assessment - Water cooled reactors - Nuclear power plants
Edition Identifiers:
- The Open Library ID: OL17603785M - OL17700611M - OL14494538M
- Online Computer Library Center (OCLC) ID: 41887747
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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10Water Chemistry of Nuclear Reactor Systems 3 (Water Chemistry of Nuclear Reactor Systems)
By International Conference Onw Ater Chemistry of Nuclear Reactor Systems
“Water Chemistry of Nuclear Reactor Systems 3 (Water Chemistry of Nuclear Reactor Systems)” Metadata:
- Title: ➤ Water Chemistry of Nuclear Reactor Systems 3 (Water Chemistry of Nuclear Reactor Systems)
- Author: ➤ International Conference Onw Ater Chemistry of Nuclear Reactor Systems
- Language: English
- Number of Pages: Median: 2
- Publisher: ➤ The Society - British Nuclear Energy Society
- Publish Date: 1983 - 1985
- Publish Location: London
“Water Chemistry of Nuclear Reactor Systems 3 (Water Chemistry of Nuclear Reactor Systems)” Subjects and Themes:
- Subjects: ➤ Water chemistry - Water cooled reactors - Water-supply - Congresses - Nuclear power plants - Nuclear reactors, cooling
Edition Identifiers:
- The Open Library ID: OL20514558M - OL10591229M
- All ISBNs: 9780727702029 - 0727702025
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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11Water 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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12Water Chemistry of Nuclear Reactor Systems 6
By British Nuclear Energy Society
“Water Chemistry of Nuclear Reactor Systems 6” Metadata:
- Title: ➤ Water Chemistry of Nuclear Reactor Systems 6
- Author: British Nuclear Energy Society
- Language: English
- Number of Pages: Median: 340
- Publisher: ➤ Unipub - British Nuclear Energy Society
- Publish Date: 1992
- Publish Location: London
“Water Chemistry of Nuclear Reactor Systems 6” Subjects and Themes:
- Subjects: ➤ Water chemistry - Water cooled reactors - Water-supply - Congresses - Nuclear power plants - Nuclear reactors - Pressurized water reactors
Edition Identifiers:
- The Open Library ID: OL10591372M - OL21529422M
- All ISBNs: 9780727716972 - 0727716972
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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13Review of Fuel Failures in Water Cooled Reactors (Technical Reports Series (International Atomic Energy Agency))
By Iaea
“Review of Fuel Failures in Water Cooled Reactors (Technical Reports Series (International Atomic Energy Agency))” Metadata:
- Title: ➤ Review of Fuel Failures in Water Cooled Reactors (Technical Reports Series (International Atomic Energy Agency))
- Author: Iaea
- Language: English
- Number of Pages: Median: 167
- Publisher: ➤ Bernan Associates - International Atomic Energy Agency
- Publish Date: 1998
- Publish Location: Vienna
“Review of Fuel Failures in Water Cooled Reactors (Technical Reports Series (International Atomic Energy Agency))” Subjects and Themes:
- Subjects: ➤ Nuclear fuels - Failures - Water cooled reactors - Nuclear fuel elements - System failures (Engineering) - Reactor fuel reprocessing
Edition Identifiers:
- The Open Library ID: OL18125677M - OL12857597M
- Online Computer Library Center (OCLC) ID: 41319736
- Library of Congress Control Number (LCCN): 98194933 - 98000193
- All ISBNs: 9789201022981 - 9201022980
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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14Selected Safety Aspects of Wwer-440 Mode L 213 Nuclear Power Plants
By Iaea
“Selected Safety Aspects of Wwer-440 Mode L 213 Nuclear Power Plants” Metadata:
- Title: ➤ Selected Safety Aspects of Wwer-440 Mode L 213 Nuclear Power Plants
- Author: Iaea
- Language: English
- Number of Pages: Median: 444
- Publisher: ➤ International Atomic Energy Agency
- Publish Date: 1996
- Publish Location: Vienna
“Selected Safety Aspects of Wwer-440 Mode L 213 Nuclear Power Plants” Subjects and Themes:
- Subjects: Water cooled reactors - Safety measures - Nuclear power plants - Risk assessment
Edition Identifiers:
- The Open Library ID: OL12857508M - OL717805M
- Online Computer Library Center (OCLC) ID: 35160421
- Library of Congress Control Number (LCCN): 97103841
- All ISBNs: 9789201011961 - 9201011962
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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15Die sanften Mörder
By Ralph Graeub
“Die sanften Mörder” Metadata:
- Title: Die sanften Mörder
- Author: Ralph Graeub
- Language: ger
- Number of Pages: Median: 179
- Publisher: ➤ Albert Müller - Fischer Taschenbuch Verlag
- Publish Date: 1972 - 1974
- Publish Location: ➤ Wien - Frankfurt am Main - Stuttgart - Rüschlikon-Zürich
“Die sanften Mörder” Subjects and Themes:
- Subjects: ➤ Accidents - Health aspects - Health aspects of Nuclear power plants - Nuclear power plants - Radiation - Radioactive pollution - Toxicology - Water cooled reactors
Edition Identifiers:
- The Open Library ID: OL50340568M - OL3898205M
- Online Computer Library Center (OCLC) ID: 2094932
- Library of Congress Control Number (LCCN): 81460187
- All ISBNs: 3275004662 - 3436018538 - 9783275004669 - 9783436018535
Access and General Info:
- First Year Published: 1972
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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16Improvements in water reactor fuel technology and utilization
By International Symposium on Improvements in Water Reactor Fuel Technology and Utilization (1986 Stockholm, Sweden)
“Improvements in water reactor fuel technology and utilization” Metadata:
- Title: ➤ Improvements in water reactor fuel technology and utilization
- Author: ➤ International Symposium on Improvements in Water Reactor Fuel Technology and Utilization (1986 Stockholm, Sweden)
- Language: English
- Number of Pages: Median: 621
- Publisher: ➤ International Atomic Energy Agency - Bernan-Unipub [distributor]
- Publish Date: 1987
- Publish Location: Lanham, MD - Vienna
“Improvements in water reactor fuel technology and utilization” Subjects and Themes:
- Subjects: Congresses - Nuclear fuels - Water cooled reactors - Water-power - Nuclear fuel elements
Edition Identifiers:
- The Open Library ID: OL2084411M - OL12857358M
- Online Computer Library Center (OCLC) ID: 18834525
- Library of Congress Control Number (LCCN): 88123744
- All ISBNs: 9789200500879 - 9200500870
Access and General Info:
- First Year Published: 1987
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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17Proceedings of the Third International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors
By International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors (3rd 1987 Traverse City, Mich.)
“Proceedings of the Third International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors” Metadata:
- Title: ➤ Proceedings of the Third International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors
- Author: ➤ International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors (3rd 1987 Traverse City, Mich.)
- Language: English
- Number of Pages: Median: 818
- Publisher: ➤ Metallurgical Society - The Minerals, Metals & Materials Society
- Publish Date: 1987
- Publish Location: Warrendale, Pa
“Proceedings of the Third International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors” Subjects and Themes:
- Subjects: ➤ Congresses - Corrosion - Effect of radiation on - Materials - Nuclear power plants - Water cooled reactors
Edition Identifiers:
- The Open Library ID: OL8377840M - OL2407543M
- Library of Congress Control Number (LCCN): 87042885
- All ISBNs: 087339030X - 9780873390309
Access and General Info:
- First Year Published: 1987
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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18Proceedings of the International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors
By International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors (1st 1983 Myrtle Beach, S.C.)
“Proceedings of the International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors” Metadata:
- Title: ➤ Proceedings of the International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors
- Author: ➤ International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors (1st 1983 Myrtle Beach, S.C.)
- Language: English
- Number of Pages: Median: 990
- Publisher: NACE
- Publish Date: 1984
- Publish Location: Houston, Tex
“Proceedings of the International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors” Subjects and Themes:
- Subjects: ➤ Congresses - Corrosion - Effect of radiation on - Materials - Nuclear power plants - Water cooled reactors - Pressurized water reactors
Edition Identifiers:
- The Open Library ID: OL8335376M - OL3191371M
- Library of Congress Control Number (LCCN): 83063121
- All ISBNs: 9780915567003 - 0915567008
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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19Design Measure to Facilitate Implementation of Safeguards at Future Water Cooled (Technical Reports Series (International Atomic Energy Agency))
By International Atomic Energy Agency.
“Design Measure to Facilitate Implementation of Safeguards at Future Water Cooled (Technical Reports Series (International Atomic Energy Agency))” Metadata:
- Title: ➤ Design Measure to Facilitate Implementation of Safeguards at Future Water Cooled (Technical Reports Series (International Atomic Energy Agency))
- Author: ➤ International Atomic Energy Agency.
- Language: English
- Number of Pages: Median: 94
- Publisher: ➤ International Atomic Energy Agency
- Publish Date: 1998 - 1999
- Publish Location: Vienna
“Design Measure to Facilitate Implementation of Safeguards at Future Water Cooled (Technical Reports Series (International Atomic Energy Agency))” Subjects and Themes:
- Subjects: ➤ Nuclear engineering, safety measures - Water cooled reactors - Design and construction - Security measures - Nuclear power plants
Edition Identifiers:
- The Open Library ID: OL18129820M - OL12857781M
- Online Computer Library Center (OCLC) ID: 40846166
- All ISBNs: 9201047983 - 9789201047984
Author's Alternative Names:
"Intl Atomic Energy Agency", "International Atomic Energy Agenc", "International Atomic Energy Agency (IAEA", "International Atomic Energy Agency; IAEA.", "Atomic Energy Agency,International.", "Atomic Energy Agency, International.", "International Atomic Energy Agency (IAEA).", "INTERNATIONAL ATOMIC ENERGY AGENCY" and "International Atomic Energy Agency"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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20Guidebook on Destructive Examination of Water Reactor Fuel (Technical Reports Series (International Atomic Energy Agency))
By International Atomic Energy Agency.
“Guidebook on Destructive Examination of Water Reactor Fuel (Technical Reports Series (International Atomic Energy Agency))” Metadata:
- Title: ➤ Guidebook on Destructive Examination of Water Reactor Fuel (Technical Reports Series (International Atomic Energy Agency))
- Author: ➤ International Atomic Energy Agency.
- Languages: ger - English
- Number of Pages: Median: 61
- Publisher: ➤ International Atomic Energy Agency
- Publish Date: 1997
- Publish Location: Vienna
“Guidebook on Destructive Examination of Water Reactor Fuel (Technical Reports Series (International Atomic Energy Agency))” Subjects and Themes:
- Subjects: Nuclear fuels - Water cooled reactors - Corrosion and anti-corrosives - Deterioration - Analysis
Edition Identifiers:
- The Open Library ID: OL439784M - OL12857478M
- Online Computer Library Center (OCLC) ID: 37775643
- Library of Congress Control Number (LCCN): 98150517
- All ISBNs: 920100897X - 9789201008978
Author's Alternative Names:
"Intl Atomic Energy Agency", "International Atomic Energy Agenc", "International Atomic Energy Agency (IAEA", "International Atomic Energy Agency; IAEA.", "Atomic Energy Agency,International.", "Atomic Energy Agency, International.", "International Atomic Energy Agency (IAEA).", "INTERNATIONAL ATOMIC ENERGY AGENCY" and "International Atomic Energy Agency"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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21Proceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors
By International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors (9th 1999 Newport Beach, Calif.)
“Proceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors” Metadata:
- Title: ➤ Proceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors
- Author: ➤ International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors (9th 1999 Newport Beach, Calif.)
- Language: English
- Number of Pages: Median: 1179
- Publisher: ➤ Minerals, Metals & Materials Society - Minerals, Metals, & Materials Society
- Publish Date: 1999 - 2000
- Publish Location: Warrendale, Pa
“Proceedings of the Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors” Subjects and Themes:
- Subjects: ➤ Congresses - Corrosion - Effect of radiation on - Materials - Nuclear power plants - Water cooled reactors - Nuclear reactors
Edition Identifiers:
- The Open Library ID: OL8378065M - OL58514M
- Online Computer Library Center (OCLC) ID: 45236910
- Library of Congress Control Number (LCCN): 99080044
- All ISBNs: 0873394755 - 9780873394758
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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22Design and performance of WWER fuel
By D. O. Pickman
“Design and performance of WWER fuel” Metadata:
- Title: ➤ Design and performance of WWER fuel
- Author: D. O. Pickman
- Language: English
- Number of Pages: Median: 80
- Publisher: ➤ International Atomic Energy Agency
- Publish Date: 1996
- Publish Location: Vienna
“Design and performance of WWER fuel” Subjects and Themes:
- Subjects: ➤ Safety measures - Nuclear fuel elements - Risk assessment - Water cooled reactors - Nuclear power plants - Design and construction
- Places: Russia (Federation)
Edition Identifiers:
- The Open Library ID: OL492373M - OL16850296M
- Online Computer Library Center (OCLC) ID: 36171935
- Library of Congress Control Number (LCCN): 95000157 - 98224203
- All ISBNs: 9789201040961 - 9201040962
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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23Seventh International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors
proceedings and symposium discussions : August 7-10, 1995, Breckenridge, Colorado
By International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors (7th 1995 Breckenridge, Colo.)
“Seventh International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors” Metadata:
- Title: ➤ Seventh International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors
- Author: ➤ International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors (7th 1995 Breckenridge, Colo.)
- Language: English
- Number of Pages: Median: 1256
- Publisher: ➤ Natl Assn of Corrosion - NACE International
- Publish Date: 1995
- Publish Location: Houston, TX
“Seventh International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors” Subjects and Themes:
- Subjects: ➤ Congresses - Corrosion - Nuclear power plants - Materials - Water cooled reactors - Effect of radiation on - Pressurized water reactors
Edition Identifiers:
- The Open Library ID: OL3778592M - OL8658499M
- Online Computer Library Center (OCLC) ID: 49520801
- Library of Congress Control Number (LCCN): 2003545470
- All ISBNs: 9781877914959 - 1877914959
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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24Data processing technologies and diagnostics for water chemistry and corrosion control in nuclear power plants (DAWAC)
By International Atomic Energy Agency
“Data processing technologies and diagnostics for water chemistry and corrosion control in nuclear power plants (DAWAC)” Metadata:
- Title: ➤ Data processing technologies and diagnostics for water chemistry and corrosion control in nuclear power plants (DAWAC)
- Author: ➤ International Atomic Energy Agency
- Language: English
- Number of Pages: Median: 99
- Publisher: ➤ International Atomic Energy Agency - Intl Atomic Energy Agency
- Publish Date: 2006
- Publish Location: Vienna
“Data processing technologies and diagnostics for water chemistry and corrosion control in nuclear power plants (DAWAC)” Subjects and Themes:
- Subjects: Water chemistry - Water cooled reactors - Corrosion - Nuclear power plants - Data processing
Edition Identifiers:
- The Open Library ID: OL18276276M - OL12857865M
- Online Computer Library Center (OCLC) ID: 76813683
- All ISBNs: 9789201079060 - 9201079060
Access and General Info:
- First Year Published: 2006
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
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25Water chemistry of nuclear reactor systems 2
By British Nuclear Energy Society
“Water chemistry of nuclear reactor systems 2” Metadata:
- Title: ➤ Water chemistry of nuclear reactor systems 2
- Author: British Nuclear Energy Society
- Language: English
- Number of Pages: Median: 428
- Publisher: ➤ British Nuclear Energy Society - Thomas Telford Ltd
- Publish Date: 1981
- Publish Location: London
“Water chemistry of nuclear reactor systems 2” Subjects and Themes:
- Subjects: ➤ Water chemistry - Water cooled reactors - Water-supply - Congresses - Nuclear power plants - Nuclear reactors - Water
Edition Identifiers:
- The Open Library ID: OL22442583M - OL7866578M
- All ISBNs: 0727701266 - 9780727701268
Access and General Info:
- First Year Published: 1981
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
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26Water chemistry of nuclear reactor systems
By British Nuclear Energy Society
“Water chemistry of nuclear reactor systems” Metadata:
- Title: ➤ Water chemistry of nuclear reactor systems
- Author: British Nuclear Energy Society
- Language: English
- Number of Pages: Median: 534
- Publisher: ➤ The Society - Thomas Telford Ltd
- Publish Date: 1978 - 1994
- Publish Location: London
“Water chemistry of nuclear reactor systems” Subjects and Themes:
- Subjects: ➤ Water chemistry - Water cooled reactors - Water-supply - Congresses - Nuclear power plants - Nuclear reactors - Pressurized water reactors
Edition Identifiers:
- The Open Library ID: OL10591215M - OL17894998M
- Library of Congress Control Number (LCCN): 79322194
- All ISBNs: 0727700537 - 9780727700537
Access and General Info:
- First Year Published: 1978
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
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27Water reactor fuel extended burnup study
By International Atomic Energy Agency
“Water reactor fuel extended burnup study” Metadata:
- Title: ➤ Water reactor fuel extended burnup study
- Author: ➤ International Atomic Energy Agency
- Language: English
- Number of Pages: Median: 60
- Publisher: ➤ International Atomic Energy Agency
- Publish Date: 1992 - 1993
- Publish Location: Vienna
“Water reactor fuel extended burnup study” Subjects and Themes:
- Subjects: Nuclear fuels - Water cooled reactors - Nuclear reactors - Fuel burnup (Nuclear engineering)
Edition Identifiers:
- The Open Library ID: OL1530127M - OL12857727M
- Online Computer Library Center (OCLC) ID: 27313931
- Library of Congress Control Number (LCCN): 93222171
- All ISBNs: 9789201039927 - 9201039921
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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28Development of the LOFT prototype drag screen
By James R. Fincke
“Development of the LOFT prototype drag screen” Metadata:
- Title: ➤ Development of the LOFT prototype drag screen
- Author: James R. Fincke
- Language: English
- Number of Pages: Median: 47
- Publisher: ➤ Available from National Technical Information Service - U.S. Nuclear Regulatory Commission
- Publish Date: 1978
- Publish Location: ➤ Springfield, Va - [Washington, D.C.?]
“Development of the LOFT prototype drag screen” Subjects and Themes:
- Subjects: ➤ Water cooled reactors - Testing - LOFT (Nuclear reactor safety test facility)
Edition Identifiers:
- The Open Library ID: OL15249692M - OL17824375M
Access and General Info:
- First Year Published: 1978
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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29Transactions of the Twenty-seventh Water Reactor Safety Information Meeting
By Water Reactor Safety Information Meeting (27th 1999 Bethesda, Md.)
“Transactions of the Twenty-seventh Water Reactor Safety Information Meeting” Metadata:
- Title: ➤ Transactions of the Twenty-seventh Water Reactor Safety Information Meeting
- Author: ➤ Water Reactor Safety Information Meeting (27th 1999 Bethesda, Md.)
- Language: English
- Number of Pages: Median: 75
- 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
“Transactions of the Twenty-seventh Water Reactor Safety Information Meeting” Subjects and Themes:
- Subjects: ➤ Congresses - Safety measures - Nuclear reactor accidents - Risk assessment - Water cooled reactors - Nuclear power plants
Edition Identifiers:
- The Open Library ID: OL17702687M - OL14504823M
- Online Computer Library Center (OCLC) ID: 43618718
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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30Preparation of radiological effluent technical specification for nuclear power plants
a guidance manual for users of standard technical specifications
By United States. Office of Nuclear Reactor Regulation. Division of Site Safety and Environmental Analysis
“Preparation of radiological effluent technical specification for nuclear power plants” Metadata:
- Title: ➤ Preparation of radiological effluent technical specification for nuclear power plants
- Author: ➤ United States. Office of Nuclear Reactor Regulation. Division of Site Safety and Environmental Analysis
- Language: English
- Number of Pages: Median: 147
- Publisher: ➤ Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Division of Site Safety and Environmental Analysis - for sale by the National Technical Information Service
- Publish Date: 1978
- Publish Location: Springfield, Va - [Washington]
“Preparation of radiological effluent technical specification for nuclear power plants” Subjects and Themes:
- Subjects: ➤ Radioactive pollution of the atmosphere - Mathematical models - Safety measures - Nuclear engineering - Water cooled reactors
Edition Identifiers:
- The Open Library ID: OL24051384M - OL14947347M
Access and General Info:
- First Year Published: 1978
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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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
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32Component 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
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33Application 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
Online Access
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34Analysis 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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35Transactions of the Twenty-sixth Water Reactor Safety Information Meeting
By Water Reactor Safety Information Meeting (26th 1998 Bethesda, Md.)
“Transactions of the Twenty-sixth Water Reactor Safety Information Meeting” Metadata:
- Title: ➤ Transactions of the Twenty-sixth Water Reactor Safety Information Meeting
- Author: ➤ Water Reactor Safety Information Meeting (26th 1998 Bethesda, Md.)
- Language: English
- Number of Pages: Median: 134
- Publisher: ➤ Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission - Supt. of Docs., U.S. G.P.O. [distributor]
- Publish Date: 1997
- Publish Location: Washington, DC
“Transactions of the Twenty-sixth Water Reactor Safety Information Meeting” Subjects and Themes:
- Subjects: ➤ Congresses - Safety measures - Nuclear reactor accidents - Risk assessment - Water cooled reactors - Nuclear power plants
- Places: United States
Edition Identifiers:
- The Open Library ID: OL17700764M - OL14496332M
- Online Computer Library Center (OCLC) ID: 42346422
Access and General Info:
- First Year Published: 1997
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
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36Drywell 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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37Thermal-Hydraulics of Water Cooled Nuclear Reactors
By Francesco D'Auria
“Thermal-Hydraulics of Water Cooled Nuclear Reactors” Metadata:
- Title: ➤ Thermal-Hydraulics of Water Cooled Nuclear Reactors
- Author: Francesco D'Auria
- Language: English
- Number of Pages: Median: 1198
- Publisher: Elsevier Science & Technology
- Publish Date: 2017
“Thermal-Hydraulics of Water Cooled Nuclear Reactors” Subjects and Themes:
- Subjects: ➤ Nuclear reactors - Thermal hydraulics - Water cooled reactors - Réacteurs refroidis par eau - TECHNOLOGY & ENGINEERING - Power Resources - Nuclear - SCIENCE - Physics
Edition Identifiers:
- The Open Library ID: OL34525736M - OL28624301M
- Online Computer Library Center (OCLC) ID: 987908860
- All ISBNs: 9780081006795 - 0081006624 - 9780081006627 - 0081006799
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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38The failed promise of nuclear power
By Irvin C. Bupp
“The failed promise of nuclear power” Metadata:
- Title: ➤ The failed promise of nuclear power
- Author: Irvin C. Bupp
- Language: English
- Number of Pages: Median: 241
- Publisher: Basic Books
- Publish Date: 1978 - 1981
- Publish Location: New York
“The failed promise of nuclear power” Subjects and Themes:
- Subjects: Nuclear industry - Public relations - Water cooled reactors - Light water reactors
Edition Identifiers:
- The Open Library ID: OL17898831M - OL18680548M
- Library of Congress Control Number (LCCN): 77020419
- All ISBNs: 9780465022731 - 0465022731
Access and General Info:
- First Year Published: 1978
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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39Failed Promise of Nuclear Power
By Irvin E. Bupp
“Failed Promise of Nuclear Power” Metadata:
- Title: ➤ Failed Promise of Nuclear Power
- Author: Irvin E. Bupp
- Language: English
- Number of Pages: Median: 241
- Publisher: Basic Books
- Publish Date: 1981
“Failed Promise of Nuclear Power” Subjects and Themes:
- Subjects: Nuclear industry - Water cooled reactors - Public relations
Edition Identifiers:
- The Open Library ID: OL10277605M
- Online Computer Library Center (OCLC) ID: 7236804
- All ISBNs: 0465022731 - 9780465022731
Access and General Info:
- First Year Published: 1981
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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40Analysis of loss of electrical power with the CATHENA model of the blanket & first wall cooling loop for the SEAFP reactordesign
By W. E. Ross
“Analysis of loss of electrical power with the CATHENA model of the blanket & first wall cooling loop for the SEAFP reactordesign” Metadata:
- Title: ➤ Analysis of loss of electrical power with the CATHENA model of the blanket & first wall cooling loop for the SEAFP reactordesign
- Author: W. E. Ross
- Language: English
- Number of Pages: Median: 16
- Publisher: CFFTP
- Publish Date: 1994
- Publish Location: Mississauga, Ont
“Analysis of loss of electrical power with the CATHENA model of the blanket & first wall cooling loop for the SEAFP reactordesign” Subjects and Themes:
- Subjects: Water cooled reactors
Edition Identifiers:
- The Open Library ID: OL16760457M
Access and General Info:
- First Year Published: 1994
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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41CATHENA model of shield circuit ITER
By W. E. Ross
“CATHENA model of shield circuit ITER” Metadata:
- Title: ➤ CATHENA model of shield circuit ITER
- Author: W. E. Ross
- Language: English
- Publisher: CFFTP
- Publish Date: 1992
- Publish Location: Mississauga, Ont
“CATHENA model of shield circuit ITER” Subjects and Themes:
- Subjects: Water cooled reactors
Edition Identifiers:
- The Open Library ID: OL19050888M
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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42Modified Cathena Model of a Shield Circuit for ITER
By W. E. Ross
“Modified Cathena Model of a Shield Circuit for ITER” Metadata:
- Title: ➤ Modified Cathena Model of a Shield Circuit for ITER
- Author: W. E. Ross
- Language: English
- Publisher: CFFTP
- Publish Date: 1993
- Publish Location: Mississauga, Ont
“Modified Cathena Model of a Shield Circuit for ITER” Subjects and Themes:
- Subjects: Water cooled reactors
Edition Identifiers:
- The Open Library ID: OL14927026M
Access and General Info:
- First Year Published: 1993
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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43Thermosyphoning analysis with the CATHENA model of the blanket & first wall cooling loop for the SEAFP reactor design
By W. E. Ross
“Thermosyphoning analysis with the CATHENA model of the blanket & first wall cooling loop for the SEAFP reactor design” Metadata:
- Title: ➤ Thermosyphoning analysis with the CATHENA model of the blanket & first wall cooling loop for the SEAFP reactor design
- Author: W. E. Ross
- Language: English
- Number of Pages: Median: 17
- Publisher: CFFTP
- Publish Date: 1994
- Publish Location: Mississauga, Ont
“Thermosyphoning analysis with the CATHENA model of the blanket & first wall cooling loop for the SEAFP reactor design” Subjects and Themes:
- Subjects: Water cooled reactors
Edition Identifiers:
- The Open Library ID: OL16795554M
Access and General Info:
- First Year Published: 1994
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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44Teplofizicheskie aspekty bezopasnosti VVĖR
By Teplofizika-98 (1998 Obninsk, Russia)
“Teplofizicheskie aspekty bezopasnosti VVĖR” Metadata:
- Title: ➤ Teplofizicheskie aspekty bezopasnosti VVĖR
- Author: ➤ Teplofizika-98 (1998 Obninsk, Russia)
- Language: rus
- Publisher: ➤ Gos. nauch. t͡s︡entr Rossiĭskoĭ Federat͡s︡ii, Fiziko-ėnergeticheskiĭ in-t
- Publish Date: 1998
- Publish Location: [Obninsk]
“Teplofizicheskie aspekty bezopasnosti VVĖR” Subjects and Themes:
- Subjects: ➤ Congresses - Nuclear power plants - Risk assessment - Safety measures - Water cooled reactors - Pressurized water reactors
Edition Identifiers:
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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45Coolant Technology of Water Cooled Reactors
By IAEA
“Coolant Technology of Water Cooled Reactors” Metadata:
- Title: ➤ Coolant Technology of Water Cooled Reactors
- Author: IAEA
- Language: English
- Number of Pages: Median: 71
- Publisher: Intl Atomic Energy Agency
- Publish Date: 1993
“Coolant Technology of Water Cooled Reactors” Subjects and Themes:
- Subjects: Pressurized water reactors - Water cooled reactors
Edition Identifiers:
- The Open Library ID: OL12857412M
- Online Computer Library Center (OCLC) ID: 27964291
- All ISBNs: 9201001932 - 9789201001931
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:
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.
Online Borrowing:
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46Operation and Licensing of Mixed Cores in Water Cooled Reactors
By IAEA
“Operation and Licensing of Mixed Cores in Water Cooled Reactors” Metadata:
- Title: ➤ Operation and Licensing of Mixed Cores in Water Cooled Reactors
- Author: IAEA
- Language: English
- Publisher: ➤ International Atomic Energy Agency
- Publish Date: 2013
“Operation and Licensing of Mixed Cores in Water Cooled Reactors” Subjects and Themes:
- Subjects: ➤ Nuclear reactors - Cores - Licenses - Water cooled reactors - Nuclear fuel elements - Design and construction - Réacteurs refroidis par eau
Edition Identifiers:
- The Open Library ID: OL37253747M
- Online Computer Library Center (OCLC) ID: 877889986
- All ISBNs: 9201132131 - 9789201132130
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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47Efficient Water Management in Water Cooled Reactors
By IAEA
“Efficient Water Management in Water Cooled Reactors” Metadata:
- Title: ➤ Efficient Water Management in Water Cooled Reactors
- Author: IAEA
- Language: English
- Publisher: ➤ International Atomic Energy Agency
- Publish Date: 2012
“Efficient Water Management in Water Cooled Reactors” Subjects and Themes:
- Subjects: ➤ Water cooled reactors - Management - Nuclear power plants - Water-supply - Réacteurs refroidis par eau - Gestion - Centrales nucléaires - Approvisionnement en eau
Edition Identifiers:
- The Open Library ID: OL37158945M
- Online Computer Library Center (OCLC) ID: 843032996
- All ISBNs: 9201326106 - 9789201326102
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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48Good Practices for Water Quality Management in Research Reactors and Spent Fuel Storage Facilities
By IAEA
“Good Practices for Water Quality Management in Research Reactors and Spent Fuel Storage Facilities” Metadata:
- Title: ➤ Good Practices for Water Quality Management in Research Reactors and Spent Fuel Storage Facilities
- Author: IAEA
- Language: English
- Publisher: ➤ International Atomic Energy Agency
- Publish Date: 2011
“Good Practices for Water Quality Management in Research Reactors and Spent Fuel Storage Facilities” Subjects and Themes:
- Subjects: ➤ Water cooled reactors - Corrosion - Radioactive waste disposal - Water quality management - Réacteurs refroidis par eau - Eau - Qualité - Gestion
Edition Identifiers:
- The Open Library ID: OL37141793M
- Online Computer Library Center (OCLC) ID: 782017502
- All ISBNs: 9789201128102 - 920112810X
Access and General Info:
- First Year Published: 2011
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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49Review of Fuel Failures in Water Cooled Reactors
By IAEA
“Review of Fuel Failures in Water Cooled Reactors” Metadata:
- Title: ➤ Review of Fuel Failures in Water Cooled Reactors
- Author: IAEA
- Language: English
- Publisher: ➤ International Atomic Energy Agency
- Publish Date: 2010
“Review of Fuel Failures in Water Cooled Reactors” Subjects and Themes:
- Subjects: ➤ Water cooled reactors - Statistics - Fuel systems - Reliability - Nuclear fuel elements - System failures (Engineering) - Réacteurs refroidis par eau - Statistiques - Alimentation en carburant - Fiabilité - Combustibles nucléaires - Éléments - Pannes
Edition Identifiers:
- The Open Library ID: OL37143931M
- Online Computer Library Center (OCLC) ID: 781957515
- All ISBNs: 9201026102 - 9789201026101
Access and General Info:
- First Year Published: 2010
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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50Fuel 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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Wiki
Source: Wikipedia
Wikipedia Results
Search Results from Wikipedia
Generation IV reactor
were: the gas-cooled fast reactor (GFR), the lead-cooled fast reactor (LFR), the molten salt reactor (MSR), the sodium-cooled fast reactor (SFR), the
Light-water reactor
Thermal-neutron reactors are the most common type of nuclear reactor, and light-water reactors are the most common type of thermal-neutron reactor. There are
Sodium-cooled fast reactor
sodium-cooled fast reactor (SFR) is a fast neutron reactor cooled by liquid sodium. The initials SFR in particular refer to two Generation IV reactor proposals
Nuclear reactor
Water cooled reactor. These constitute the great majority of operational nuclear reactors: as of 2014, 93% of the world's nuclear reactors are water cooled
Supercritical water reactor
liquid metal cooled reactors). A fast SCWR could be a breeder reactor, like the proposed Clean and Environmentally Safe Advanced Reactor and could burn
Lead-cooled fast reactor
energy reactors rather than fast reactors). Some proposed new nuclear reactor designs are lead-cooled. Fuel designs being explored for this reactor scheme
Gas-cooled reactor
types of reactor cooled by gas, the terms GCR and to a lesser extent gas cooled reactor are particularly used to refer to this type of reactor. The GCR
Breeder reactor
least 25% more than water-cooled reactors. It was thought that breeder reactors could be as safe and reliable as light-water reactors, but safety issues
Liquid metal cooled reactor
liquid metal cooled nuclear reactor (LMR) is a type of nuclear reactor where the primary coolant is a liquid metal. Liquid metal cooled reactors were first
Gas-cooled fast reactor
gas-cooled reactor (HTGR), as well as the Gas-cooled Fast Reactor (GCFR) system. Gas-cooled projects (thermal spectrum) include decommissioned reactors such