ANS / Publications / Journals / Nuclear Technology

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

Passive Pressure Tube Light Water Reactors

Pavel Hejzlar, Neil E. Todreas, Michael J. Driscoll

Nuclear Technology / Volume 113 / Number 2 / February 1996 / Pages 123-133

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT96-A35182

Large Passive Pressure Tube Light Water Reactor with Voided Calandria

Pavel Hejzlar, Neil E. Todreas, Michael J. Driscoll

Nuclear Technology / Volume 113 / Number 2 / February 1996 / Pages 134-144

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT96-A35183

Estimation of Dynamic Reactivity Using an H_∞ Optimal Filter with a Nonlinear Term

Katsuo Suzuki, Koiti Watanabe

Nuclear Technology / Volume 113 / Number 2 / February 1996 / Pages 145-154

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT96-A35184

Modeling of Diffusive Gravitational Aerosol Deposition in CONTAIN

Almir Fernandes, Sudarshan K. Loyalka

Nuclear Technology / Volume 113 / Number 2 / February 1996 / Pages 155-166

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT96-A35185

Validation Studies of a Computational Model for Molten Material Freezing

Tetsuo Sawada, Hisashi Ninokata, Akinao Shimizu

Nuclear Technology / Volume 113 / Number 2 / February 1996 / Pages 167-176

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT96-A35186

Degradation Analysis Estimates of the Time-to-Failure Distribution of Irradiated Fuel Elements

Abdellatif M. Yacout, Stefano Salvatores, Yuri Orechwa

Nuclear Technology / Volume 113 / Number 2 / February 1996 / Pages 177-189

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT96-A35187

A Set of Integrated Environmental Transport and Diffusion Models for Calculating Hazardous Releases

Darrell W. Pepper, James A. Marino

Nuclear Technology / Volume 113 / Number 2 / February 1996 / Pages 190-203

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT96-A35188

On the French Project Developed in the 1980s for the Production of ⁹⁹Mo from the Fission of ²³⁵U

J. Bourges, C. Madic, G. Koehly, T. H. Nguyen, D. Baltes, C. Landesman, A. Simon

Nuclear Technology / Volume 113 / Number 2 / February 1996 / Pages 204-220

Technical Paper / Radioisotopes and Isotope / dx.doi.org/10.13182/NT96-A35189

Gaseous Radioiodine Deposition Losses in Nuclear Reactor Sample Lines

Byung-Soo Lee, William A. Jester

Nuclear Technology / Volume 113 / Number 2 / February 1996 / Pages 221-231

Technical Paper / Reactor Operation / dx.doi.org/10.13182/NT96-A35190

A Personal Computer—Based On-Line Balance-of-Plant Performance Monitoring and Analysis System for Nuclear Power Plants

Gung-Huei Chou, Jin-Yeh Hsu, Houng-June Chao

Nuclear Technology / Volume 113 / Number 2 / February 1996 / Pages 232-241

Technical Paper / Reactor Operation / dx.doi.org/10.13182/NT96-A35191

Analysis of Core Uncovery Time in Kuosheng Station Blackout Transient with MELCOR

Shih-Jen Wang, Chun-Sheng Chien

Nuclear Technology / Volume 113 / Number 2 / February 1996 / Pages 242-248

Technical Note / Nuclear Reactor Safety / dx.doi.org/10.13182/NT96-A35192

Wind Effects on the Performance of the Reactor Vessel Auxiliary Cooling System

C. P. Tzanos, A. Hunsbedt

Nuclear Technology / Volume 113 / Number 3 / March 1996 / Pages 249-267

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT96-A35206

SASSYS/SAS4A-FPIN2 Liquid-Metal Reactor Transient Analysis Code System for Mechanical Analysis of Metallic Fuel Elements

Tanju Sofu, John M. Kramer, James E. Cahalan

Nuclear Technology / Volume 113 / Number 3 / March 1996 / Pages 268-279

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT96-A35207

Use of the Chinshan Plant Analyzer for Analysis of a Main-Steam-lsolation-Valve-Closure Anticipated Transient Without Scram

Shih-Jen Wang, Shih-Hsiin Chang, Ling-Yao Chou

Nuclear Technology / Volume 113 / Number 3 / March 1996 / Pages 280-290

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT96-A35208

Experience with COSYMA in an International Intercomparison of Probabilistic Accident Consequence Assessment Codes

I. Hasemann, J. A. Jones, J. Van Der Steen, E. Van Wonderen

Nuclear Technology / Volume 113 / Number 3 / March 1996 / Pages 291-303

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT96-A35209

Thermal Decomposition of Nitrated Tributyl Phosphate

Y. Hou, E. K. Barefield, D. W. Tedder, S. I. Abdel-Khalik

Nuclear Technology / Volume 113 / Number 3 / March 1996 / Pages 304-315

Technical Paper / Enrichment and Reprocessing System / dx.doi.org/10.13182/NT96-A35210

Sensitivity of the Radionuclide Release from a Repository to the Variability of Materials and Other Properties

Leonardo Romero, Luis Moreno, Ivars Neretnieks

Nuclear Technology / Volume 113 / Number 3 / March 1996 / Pages 316-326

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT96-A35211

Two-Phase Flow Instability for Low-Flow Boiling in Vertical Uniformly Heated Thin Rectangular Channels

Chang H. Oh, John C. Chapman

Nuclear Technology / Volume 113 / Number 3 / March 1996 / Pages 327-337

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT96-A35212

A Passive System for Long-Term Heat Removal in Advanced Light Water Reactors: Prototype Test Results and Analysis

Luca Galbiati, Luigi Mazzocchi, Paolo Vanini

Nuclear Technology / Volume 113 / Number 3 / March 1996 / Pages 338-345

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT96-A35213

Rapid Measurement of the Gaseous ⁴¹Ar Released from a Nuclear Reactor Using a Portable Spectrometer

Chien Chung, Chin-Hsuen Tsai

Nuclear Technology / Volume 113 / Number 3 / March 1996 / Pages 346-353

Technical Paper / Radiation Protection / dx.doi.org/10.13182/NT96-A35214

Optimization of Standby Safety System Maintenance Schedules in Nuclear Power Plants

Mohammad Harunuzzaman, Tunc Aldemir

Nuclear Technology / Volume 113 / Number 3 / March 1996 / Pages 354-367

Technical Paper / Reactor Operation / dx.doi.org/10.13182/NT96-A35215

Multiple-Failure Signal Validation in Nuclear Power Plants Using Artificial Neural Networks

Paolo F. Fantoni, Alessandro Mazzola

Nuclear Technology / Volume 113 / Number 3 / March 1996 / Pages 368-374

Technical Paper / Reactor Operation / dx.doi.org/10.13182/NT96-A35216

Modified Conversion Ratio Measurement in Light Water-Moderated UO₂ Lattices

Ken Nakajima, Masanori Akai

Nuclear Technology / Volume 113 / Number 3 / March 1996 / Pages 375-379

Technical Note / Fission Reactor / dx.doi.org/10.13182/NT96-A35217