Explore Books on
pressurized water reactors
1-24 of 581 Books
Standard technical specifications
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
Proceedings of the Institution of Mechanical Engineers
By IMechE (Institution of Mechanical Engineers)
Nowadays tools for graphical post-processing of TRAC-BF1 results
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
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
Safety Features of Operating Light Water Reactors of Western Design
By M. Gavrilas
The "calculated" loss-of-coolant accident
By L. J. Ybarrondo
Assessment of TRAC-PF1/MOD1 against a loss-of-grid transient in Ringhals 4 power plant
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
Assessment of TRAC-PF1/MOD1 against an inadvertent feedwater line isolation transient in the Ringhals 4 power plant
By Anders Sjöberg
Pressurized water-reactor feedwater piping response to water hammer
Pressurized water-reactor feedwater piping response to water hammer
By Don Arthur
Proceedings of the U.S. Nuclear Regulatory Commission, fifteenth Water Reactor Safety Information Meeting
Proceedings of the U.S. Nuclear Regulatory Commission, fifteenth Water Reactor Safety Information Meeting
By Water Reactor Safety Information Meeting (15th 1987 Gaithersburg, Md.)
TRAC-M programmer's guide
TRAC-M programmer's guide
By R. G. Steinke
Assessment of RELAP5/MOD3.2 against a main steam isolation valve closure at TRILLO I Nuclear Power Plant
Assessment of RELAP5/MOD3.2 against a main steam isolation valve closure at TRILLO I Nuclear Power Plant
By A. de Lucas
Assessment of RELAP5/MOD3.2-NPA3.4 against an inadvertent closure of all three MSIV's in VANDELLOS-II nuclear power plant
Assessment of RELAP5/MOD3.2-NPA3.4 against an inadvertent closure of all three MSIV's in VANDELLOS-II nuclear power plant
By C. Llopis
Assessment of RELAP5/MOD3.2-NPA3.4 against a transient of high nuclear flux variation reactor trip, natural circulation and the start of a main pump in the VANDELLOS II nuclear power plant
Assessment of RELAP5/MOD3.2-NPA3.4 against a transient of high nuclear flux variation reactor trip, natural circulation and the start of a main pump in the VANDELLOS II nuclear power plant
By C. Llopis
TRAC-M validation test matrix
TRAC-M validation test matrix
By B. E. Boyack
RELAP5/MOD3.2 post test analysis and accuracy quantification of Lobi test BL-44
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
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
RELAP5/MOD3.2 post test analysis and accuracy quantification of SPES test SP-SB-04
By F. D'Auria
RELAP5/MOD3.2 validation using BETHSY test 6.9a
RELAP5/MOD3.2 validation using BETHSY test 6.9a
By S. Bouabdallah
Voltage-based interim plugging criteria for steam generator tubes
Voltage-based interim plugging criteria for steam generator tubes
By U.S. Nuclear Regulatory Commission. IPC Task Group.
U.S. operating experience with thermally treated Alloy 600 steam generator tubes
U.S. operating experience with thermally treated Alloy 600 steam generator tubes
By K. J. Karwoski
RELAP5/MOD3.2 post test calculation of the PKL-experiment PKLIII-B4.3
RELAP5/MOD3.2 post test calculation of the PKL-experiment PKLIII-B4.3
By L. Karner