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Home / Publications / Journals / Nuclear Technology / Volume 113 / Number 1

Volume 113

Number 1

Investigation of Two-Phase Phenomena Occurring Within Moisture Separator Reheater High-Level Reactor Trips at the Maanshan Nuclear Power Plant

Yuh-Ming Ferng, Lih-Yih Liao

Nuclear Technology / Volume 113 / Number 1 / January 1996 / Pages 1-13

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT96-A35194

Westinghouse-Gothic Comparisons with Passive Containment Cooling Tests Using a One-to-Ten-Scale Test Facility

M. D. Kennedy, J. Woodcock, R. F. Wright, J. A. Gresham

Nuclear Technology / Volume 113 / Number 1 / January 1996 / Pages 14-20

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT96-A35195

Development of a MELCOR Self-Initialization Algorithm for Boiling Water Reactors

Chun-Sheng Chien, Shih-Jen Wang, Shih-Kuei Cheng

Nuclear Technology / Volume 113 / Number 1 / January 1996 / Pages 21-28

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT96-A35196

A Model for Container Performance in an Unsaturated Repository

Daniel B. Bullen

Nuclear Technology / Volume 113 / Number 1 / January 1996 / Pages 29-45

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT96-A35197

Ambient Temperature Contamination of Process Piping and the Effects of Pretreatment

S. A. Adeleye, D. A. White, J. B. Taylor

Nuclear Technology / Volume 113 / Number 1 / January 1996 / Pages 46-53

Technical Paper / Material / dx.doi.org/10.13182/NT96-A35198

Development of Thermohydraulics Computer Programs for Thermal Striping Phenomena

Toshiharu Muramatsu, Hisashi Ninokata

Nuclear Technology / Volume 113 / Number 1 / January 1996 / Pages 54-72

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT96-A35199

Modeling the Accumulators of the Advanced Neutron Source Reactor

R. L. Moore, C. D. Fletcher, C. S. Miller

Nuclear Technology / Volume 113 / Number 1 / January 1996 / Pages 73-85

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT96-A35200

Characterization of Anomalies by Applying Methods of Fractal Analysis

M. Sakuma, R. Kozma, M. Kitamura

Nuclear Technology / Volume 113 / Number 1 / January 1996 / Pages 86-99

Technical Paper / Reactor Operation / dx.doi.org/10.13182/NT96-A35201

Myth or Nightmare: Safety Consequences of the Release of Radiation-Induced Stored Energy in Rock Salt

J. Prij

Nuclear Technology / Volume 113 / Number 1 / January 1996 / Pages 100-109

Technical Note / Radioactive Waste Management / dx.doi.org/10.13182/NT96-A35202

Critical Mass Variation of 239Pu with Water Dilution

Sol Pearlstein

Nuclear Technology / Volume 113 / Number 1 / January 1996 / Pages 110-111

Technical Note / Nuclear Criticality Safety / dx.doi.org/10.13182/NT96-A35203

The Selection of Fixed-Order Quadratures in Point-Kernel Shielding Calculations

O. J. Wallace

Nuclear Technology / Volume 113 / Number 1 / January 1996 / Pages 112-122

Technical Note / Radiation Protection / dx.doi.org/10.13182/NT96-A35204

 

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