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boiling water reactors

1-24 of 245 Books

View Standard technical specifications By U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation.

Standard technical specifications

Standard technical specifications

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

View Meltdown! By Alfred B. Bortz
Cover of Meltdown! by alfred b. bortz

Meltdown!

By Alfred B. Bortz

View Safety Features of Operating Light Water Reactors of Western Design By M. Gavrilas

Safety Features of Operating Light Water Reactors of Western Design

Safety Features of Operating Light Water Reactors of Western Design

By M. Gavrilas

View The "calculated" loss-of-coolant accident By L. J. Ybarrondo
Cover of The "calculated" loss-of-coolant accident by l. j. ybarrondo

The "calculated" loss-of-coolant accident

By L. J. Ybarrondo

View An overview of BWR Mark-I containment venting risk implications By K. C. Wagner

An overview of BWR Mark-I containment venting risk implications

An overview of BWR Mark-I containment venting risk implications

By K. C. Wagner

View Post-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

Post-test analysis of P5 experiment in PANDA facility with TRAC-BF1 code

By J. Polo

View TRAC-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

TRAC-B thermal-hydraulic analysis of the Black Fox boiling water reactor

By R. P. Martin

View Offsite dose calculation manual guidance By W. Wayne Meinke

Offsite dose calculation manual guidance

Offsite dose calculation manual guidance

By W. Wayne Meinke

View Density-wave instabilities in boiling water reactors By J. March-Leuba

Density-wave instabilities in boiling water reactors

Density-wave instabilities in boiling water reactors

By J. March-Leuba

View Analysis 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)

Analysis of long-term station blackout without automatic depressurization at Peach Bottom using MELCOR (version 1.8)

By I. K. Madni

View Irradiation-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

Irradiation-assisted stress corrosion cracking of model austenitic stainless steels irradiated in the Halden reactor

By H. M. Chung

View Experimental and numerical stability investigations on natural circulation boiling water reactors By Christian Pablo Marcel
Cover of Experimental 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

By Christian Pablo Marcel

View Assessment 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

Assessment of modernization and integration of BWR components and spatial kinetics in the TRAC-M, Version 3690, code

By F. Odar

View USI A-43 regulatory analysis By A. W. Serkiz

USI A-43 regulatory analysis

USI A-43 regulatory analysis

By A. W. Serkiz

View Boiling-water reactor internals aging degradation study By K. H. Luk

Boiling-water reactor internals aging degradation study

Boiling-water reactor internals aging degradation study

By K. H. Luk

View Water Chemistry of Nuclear Reactor Systems 4 By British Nuclear Energy Society

Water Chemistry of Nuclear Reactor Systems 4

Water Chemistry of Nuclear Reactor Systems 4

By British Nuclear Energy Society

View Boiling water reactors By Andrew W. Kramer

Boiling water reactors

Boiling water reactors

By Andrew W. Kramer

View MARK II containment lead plant program load evaluation and acceptance criteria By C. Anderson

MARK II containment lead plant program load evaluation and acceptance criteria

MARK II containment lead plant program load evaluation and acceptance criteria

By C. Anderson

View Experimental 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

Experimental assessments of Gundremmingen RPV archive material for fluence rate effects studies

By J. R. Hawthorne

View Water coolant technology of power reactors By Cohen, P.
Cover of Water coolant technology of power reactors by cohen, p.

Water coolant technology of power reactors

By Cohen, P.

View Assessment 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

Assessment 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

View Mark III LOCA-related hydrodynamic load definition By M. B Fields

Mark III LOCA-related hydrodynamic load definition

Mark III LOCA-related hydrodynamic load definition

By M. B Fields

View Identification 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

Identification and assessment of containment and release management strategies for a BWR Mark I containment

By C. C. Lin

View Identification 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

Identification and assessment of containment and release management strategies for a BWR Mark III containment

By C. C. Lin