Explore Books on
pressurized water reactors

Standard technical specifications

By U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation.

Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors

By John H Jackson,Denise Paraventi,Michael Wright

Assessment of RELAP5/MOD3.2 using LOFT large break LOCA test, LP-02-6

By T. S. Choi,U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research

Assessment of RELAP5/MOD3.2 with the semiscale natural circulation experiment, S-NC-8B

By Y. S. Bang

Assessment of RELAP5/MOD3.2 for steam condensation experiments in the presence of noncondensibles in a vertical tube of PCCS

By U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research,Han'guk Kwahak Kisurwŏn,Han'guk Wŏnjaryŏk Anjŏn Kisurwŏn

Assessment of RELAP5/MOD3.1 using LSTF ten-percent main steam-line-break test run SB-SL-01

By U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research,Han'guk Wŏnjaryŏk Anjŏn Kisurwŏn,Nihon Genshiryoku Kenkyūjo

Proceedings of the Institution of Mechanical Engineers

By IMechE (Institution of Mechanical Engineers)

Result of BETHSY test 9.1.b using RELAP5/MOD2

By S. Petelin,U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research

Nowadays tools for graphical post-processing of TRAC-BF1 results

By P. Corcuera

Assessment of the TRAC-M codes using Flecht-Seaset reflood and steam cooling data

By F. Odar

Safety Features of Operating Light Water Reactors of Western Design

By M. Gavrilas

The "calculated" loss-of-coolant accident

By L. J. Ybarrondo

Voltage-based alternative repair criteria

By

Pressurized water-reactor feedwater piping response to water hammer

By Don Arthur

Assessment of TRAC-PF1/MOD1 against a loss-of-grid transient in Ringhals 4 power plant

By Anders Sjöberg

Assessment of TRAC-PF1/MOD1 against an inadvertent feedwater line isolation transient in the Ringhals 4 power plant

By Anders Sjöberg

U.S. operating experience with thermally treated Alloy 600 steam generator tubes

By K. J. Karwoski

Voltage-based interim plugging criteria for steam generator tubes

By U.S. Nuclear Regulatory Commission. IPC Task Group.

Assessment of RELAP5/MOD3.2 against a main steam isolation valve closure at TRILLO I Nuclear Power Plant

By A. de Lucas

TRAC-M validation test matrix

By B. E. Boyack

RELAP5/MOD.2 post test analysis and accuracy quantification of Lobi test BL-34

By F. D'Auria

RELAP5/MOD3.2 post test analysis and accuracy quantification of Lobi test BL-44

By F. D'Auria

RELAP5/MOD3.2 post test analysis and accuracy quantification of SPES test SP-SB-03

By F. D'Auria

RELAP5/MOD3.2 post test analysis and accuracy quantification of SPES test SP-SB-04

By F. D'Auria