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Pressurized heavy water reactors : Atucha II (JSME series in thermal and nuclear power generation ; volume 8)

Pressurized heavy water reactors : Atucha II (JSME series in thermal and nuclear power generation ; volume 8)
紙図書
edited by Jovica R. RiznicElsevier[2022]<NG41-D14>
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  • LCCTK9203.P7

Pressurized heavy water reactors : CANDU (JSME series in thermal and nuclear power generation ; volume 7)

Pressurized heavy water reactors : CANDU (JSME series in thermal and nuclear power generation ; volume 7)
紙図書
edited by Jovica R. RiznicElsevier[2022]<NG41-D13>
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  • LCCTK9203.P7

Computer codes for small-break loss-of-coolant accidents : a Nordic assessment : final report of the NKA project SÄK-3 / compiled by Ole Rathmann.

Computer codes for small-break loss-of-coolant accidents : a Nordic assessment : final report of the NKA project SÄK-3 / compiled by Ole Rathmann.
紙図書
Nordic Liaison Committee for Atomic Energy[1985]<NG41-A12>
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  • LCCTK9203.P7

Critical flow modelling in nuclear safety : a state-of-the-art report / by a Group of Experts of the NEA Committee on the Safety of Nuclear Installations, June 1982.

Critical flow modelling in nuclear safety : a state-of-the-art report / by a Group of Experts of the NEA Committee on the Safety of Nuclear Installations, June 1982.
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Nuclear Energy Agency, Organisation for Economic Co-operation and Developmentc1982.<NG31-167>
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  • LCCTK9203.P7

Thermal analysis of pressurized water reactors 3rd ed

Thermal analysis of pressurized water reactors 3rd ed
紙図書
L.S. Tong, Joel Weisman1996
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Nuclear safety : a report by the Health and Safety Executive to the Secretary of State for Energy on a review of the generic safety issues of pressurised water reactors / Health and Safety Executive.

Nuclear safety : a report by the Health and Safety Executive to the Secretary of State for Energy on a review of the generic safety issues of pressurised water reactors / Health and Safety Executive.
紙図書
H.M.S.O.[1982]<ND148-60>
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  • LCCTK9203.P7

Thermal analysis of pressurized water reactors 3rd ed

Thermal analysis of pressurized water reactors 3rd ed
紙図書
L.S. Tong, Joel WeismanAmerican Nuclear Societyc1996
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  • LCCTK9203.P7

High converting water reactors

High converting water reactors
紙図書
Yigal Ronen, editorCRC Pressc1990
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  • LCCTK9203.P7

Proceedings of the Institution of Mechanical Engineers : conference : Sizewell "B" - the First of the UK PWP Power Stations, 13-14 September 1989, Ramada Renaissance Hotel, Manchester

Proceedings of the Institution of Mechanical Engineers : conference : Sizewell "B" - the First of the UK PWP Power Stations, 13-14 September 1989, Ramada Renaissance Hotel, Manchester
紙図書
sponsored by Power Industries Division of the Institution of Mechanical EngineersInstitution of Mechanical Engineering1989
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Comparison of thermal-hydraulic safety codes for PWR systems

Comparison of thermal-hydraulic safety codes for PWR systems
紙図書
A. Forge ... [et al.]Graham & Trotman1988
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Water coolant technology of power reactors. (Monograph series on nuclear science and technology)

Water coolant technology of power reactors. (Monograph series on nuclear science and technology)
紙図書
Gordon and Breach[1969]<NG41-62>
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Critical flow modelling in nuclear safety : a state-of-the-art report

Critical flow modelling in nuclear safety : a state-of-the-art report
紙図書
by a Group of Experts of the NEA Committee on the Safety of Nuclear Installations, June 1982Nuclear Energy Agency, Organisation for Economic Co-operation and Development1982
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Pressurised water reactor in the United Kingdom, 11 May 1982, Institution Headquarters, 1 Birdcage Walk, Westminster London

Pressurised water reactor in the United Kingdom, 11 May 1982, Institution Headquarters, 1 Birdcage Walk, Westminster London
紙図書
sponsored by the Power Industries Division of the Institution of Mechanical Engineerspublished by Mechanical Engineering Publications for the Institution of Mechanical Engineers1982
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Water coolant technology of power reactors

Water coolant technology of power reactors
紙図書
Paul CohenAmerican Nuclear Societyc1980
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Thermal analysis of pressurized water reactors 2d ed

Thermal analysis of pressurized water reactors 2d ed
紙図書
L. S. Tong, Joel WeismanAmerican Nuclear Societyc1979
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Corrosion and wear handbook for water-cooled reactors.

Corrosion and wear handbook for water-cooled reactors.
紙図書
McGraw-Hill1957.<620.1122-D419c>
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  • LCCTK9203.P7

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