ANS / Publications / Journals / Nuclear Technology

Simplified Boiling Water Reactor Thermal-Hydraulic Performance: A RELAP5/MOD2 Model Simulation

P. Barbucci, L. Bella

Nuclear Technology / Volume 112 / Number 1 / October 1995 / Pages 1-8

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT95-A15847

Radial Resonance Captures in ²³⁸U Metal Rods and Spatial Resonance Production of ²³⁹Pu in Uranium-Oxide Fuels

Donald Bogart

Nuclear Technology / Volume 112 / Number 1 / October 1995 / Pages 9-20

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT95-A15848

Aging Effects on Time-Dependent Nuclear Plant Component Unavailability: An Investigation of Variations from Static Calculations

Rob D. Radulovich, William E. Vesely, Tunc Aldemir

Nuclear Technology / Volume 112 / Number 1 / October 1995 / Pages 21-41

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT95-A15849

Evaluation of Reflooding Effects on an Overheated Boiling Water Reactor Core in a Small Steam-Line Break Accident Using MAAP, MELCOR, and SCDAP/RELAP5 Computer Codes

I. Lindholm, E. Pekkarinen, H. Sjövall

Nuclear Technology / Volume 112 / Number 1 / October 1995 / Pages 42-57

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT95-A15850

Qualification of a Passive Catalytic Module for Hydrogen Mitigation

Karsten Fischer

Nuclear Technology / Volume 112 / Number 1 / October 1995 / Pages 58-62

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT95-A15851

A Route-Specific System for Risk Assessment of Radioactive Materials Transportation Accidents

John E. Moore, Gary M. Sandquist, David M. Slaughter

Nuclear Technology / Volume 112 / Number 1 / October 1995 / Pages 63-78

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT95-A15852

Thermal and Thermomechanical Analyses for Disposal in Drifts of a Repository in Rock Salt

Alexandra Pudewills, Nina Müller-Hoeppe, Reiner Papp

Nuclear Technology / Volume 112 / Number 1 / October 1995 / Pages 79-88

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT95-A15853

Fast Multiple-Path Model to Calculate Radionuclide Release from the Near Field of a Repository

L. Romero, L. Moreno, I. Neretnieks

Nuclear Technology / Volume 112 / Number 1 / October 1995 / Pages 89-98

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT95-A15854

The Fast Multiple-Path NUCTRAN Model—Calculating the Radionuclide Release from a Repository

L. Romero, L. Moreno, I. Neretnieks

Nuclear Technology / Volume 112 / Number 1 / October 1995 / Pages 99-107

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT95-A15855

Framatome Antistratification Device for Steam Generator Feedwater Nozzle: Effectiveness, Qualification Test, and On-Site Measurements

Christophe Poussin, Alain Holcblat

Nuclear Technology / Volume 112 / Number 1 / October 1995 / Pages 108-121

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT95-A15856

Experimental Study on Performance of a Hybrid Baffle Plate for the Water-Wall-Type Passive Containment Cooling System

Tadashi Fujii, Yoshiyuki Kataoka, Michio Murase, Kenji Tominaga

Nuclear Technology / Volume 112 / Number 1 / October 1995 / Pages 122-131

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT95-A15857

Calculated Shielding Characteristics of Eight Materials for Neutrons and Secondary Photons Produced by Monoenergetic Source Neutrons with Energies Less Than 400 MeV

Noriyoshi Nakanishi, Takashi Shikata, Shin Fujita, Toshiso Kosako

Nuclear Technology / Volume 112 / Number 1 / October 1995 / Pages 132-141

Technical Paper / Radiation Protection / dx.doi.org/10.13182/NT95-A15858

Improved Neutronics Model of the High Flux Isotope Reactor

S. Goluoglu, H. L. Dodds

Nuclear Technology / Volume 112 / Number 1 / October 1995 / Pages 142-153

Technical Note / Fission Reactor / dx.doi.org/10.13182/NT95-A15859

Mitigation of an Anticipated Transient Without Scram Event in A Simplified Boiling Water Reactor by the Insertion of Fine-Motion Control Rods

Hasna J. Khan, Hsiang S. Cheng, Upendra S. Rohatgi

Nuclear Technology / Volume 112 / Number 2 / November 1995 / Pages 155-168

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT95-A35170

Independent Assessment of Melcor as A Severe Accident Thermal-Hydraulic/Source Term Analysis Tool

I. K. Madni

Nuclear Technology / Volume 112 / Number 2 / November 1995 / Pages 169-180

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT95-A35171

A Comparative Simulation of Feed and Bleed Operation During the Total Loss of Feedwater Event by RELAP5/MOD3 and CEFLASH-4AS/REM Computer Codes

Young Min Kwon, Tae Sun Ro, Jin Ho Song

Nuclear Technology / Volume 112 / Number 2 / November 1995 / Pages 181-193

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT95-A35172

Irradiation Performance of Fast Flux Test Facility Drivers Using D9 Alloy

A. L. Pitner, B. C. Gneiting, F. E. Bard

Nuclear Technology / Volume 112 / Number 2 / November 1995 / Pages 194-203

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT95-A35173

Choice of A Process Design for Simultaneous Detritiation and Upgrading of Heavy water for the Advanced Neutron Source

A. I. Miller, D. A. Spagnolo, J. R. DeVore

Nuclear Technology / Volume 112 / Number 2 / November 1995 / Pages 204-213

Technical Paper / Radioisotopes and Isotope / dx.doi.org/10.13182/NT95-A35174

Taiwan Power Company’s Power Distribution Analysis and Fuel Thermal Margin Verification Methods for Pressurized Water Reactors

Ping-Hue Huang

Nuclear Technology / Volume 112 / Number 2 / November 1995 / Pages 214-226

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT95-A35175

Heat Transfer from A Plate Cooled by A Water Film with Countercurrent Air Flow

W. Ambrosini, A. Manfredini, F. Mariotti, F. Oriolo, P. Vigni

Nuclear Technology / Volume 112 / Number 2 / November 1995 / Pages 227-237

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT95-A35176

Thermal-Hydraulic Modeling and Severe Accident Radionuclide Transport

F. Oriolo, W. Ambrosini, G. Fruttuoso, F. Parozzi, R. Fontana

Nuclear Technology / Volume 112 / Number 2 / November 1995 / Pages 238-249

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT95-A35177

Probabilistic Analysis of Limiting Conditions for Operation Action Requirements Including Risk of Shutdown

T. Mankamo, I. S. Kim, P. K. Samanta

Nuclear Technology / Volume 112 / Number 2 / November 1995 / Pages 250-265

Technical Paper / Reactor Operation / dx.doi.org/10.13182/NT95-A35178

Development of the On-Line Operator Aid System OASYS Using A Rule-Based Expert System and Fuzzy Logic for Nuclear Power Plants

Soon Heung Chang, Ki Sig Kang, Seong Soo Choi, Han Gon Kim, Hee Kyo Jeong, Chul Un Yi

Nuclear Technology / Volume 112 / Number 2 / November 1995 / Pages 266-294

Technical Paper / Reactor Control / dx.doi.org/10.13182/NT95-A35179

Transient Gap Conductance in Nuclear Fuel Rods

G. Dharmadurai

Nuclear Technology / Volume 112 / Number 2 / November 1995 / Pages 295-298

Technical Note / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT95-A35180

Validation of the Assert Subchannel Code: Prediction of Critical Heat Flux in Standard and Nonstandard Candu Bundle Geometries

M. B. Carver, J. C. Kiteley, R. Q.-N. Zhou, S. V. Junop, D. S. Rowe

Nuclear Technology / Volume 112 / Number 3 / December 1995 / Pages 299-314

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT95-A35156

Prediction of Dryout Performance for Boiling Water Reactor Fuel Assemblies Based on Subchannel Analysis with the Rings Code

P. Knabe, F. Wehle

Nuclear Technology / Volume 112 / Number 3 / December 1995 / Pages 315-323

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT95-A35157

A Perspective on Large eddy Simulation of Problems in the Nuclear Industry

Yassin A. Hassan, John M. Pruitt, David A. Steininger

Nuclear Technology / Volume 112 / Number 3 / December 1995 / Pages 324-330

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT95-A35158

The THYC Three-Dimensional Thermal-Hydraulic Code for Rod Bundles: Recent Developments and Validation Tests

Sylvie Aubry, Christian Caremoli, Jean Olive, Paul Rascle

Nuclear Technology / Volume 112 / Number 3 / December 1995 / Pages 331-345

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT95-A35159

The Application of Computational Fluid Dynamics to Critical Heat Flux

James H. Stuhmiller, Paul J. Masiello, Govinda S. Srikantiah, Lance J. Agee

Nuclear Technology / Volume 112 / Number 3 / December 1995 / Pages 346-354

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT95-A35160

A Utility Perspective on Subchannel Analysis

Gregg B. Swindlehurst

Nuclear Technology / Volume 112 / Number 3 / December 1995 / Pages 355-358

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT95-A35161

Equilibrium Quality and Mass Flux Distributions in an Adiabatic Three-Subchannel Test Section

George Yadigaroglu, Athan Maganas

Nuclear Technology / Volume 112 / Number 3 / December 1995 / Pages 359-372

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT95-A35162

Reactor Subchannel Analysis—Electric Power Research Institute Perspective

G. Srikantiah

Nuclear Technology / Volume 112 / Number 3 / December 1995 / Pages 373-381

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT95-A35163

The Japanese Utilities’ Expectations for Subchannel Analysis

Akio Toba, Akira Omoto

Nuclear Technology / Volume 112 / Number 3 / December 1995 / Pages 382-387

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT95-A35164

Void Fraction Distribution in A Boiling Water Reactor Fuel Assembly and the Evaluation of Subchannel Analysis Codes

Akira Inoue, Masanobu Futakuchi, Makoto Yagi, Toru Mitsutake, Shin-Ichi Morooka

Nuclear Technology / Volume 112 / Number 3 / December 1995 / Pages 388-400

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT95-A35165

Subchannel Thermal-Hydraulic Analysis at AP600 Low-Flow Steam-Line-Break Conditions

T. Morita, C. A. Olson, Y. X. Sung, J. F. Connelley, Jr., E. H. Novendstern, S. Kapil, P. W. Rosenthal

Nuclear Technology / Volume 112 / Number 3 / December 1995 / Pages 401-411

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT95-A35166

Pressurized Water Reactor Fuel Assembly Subchannel Void Fraction Measurement

Yoshiei Akiyama, Keiichi Hori, Keiji Miyazaki, Kaichiro Mishima, Shigekazu Sugiyama

Nuclear Technology / Volume 112 / Number 3 / December 1995 / Pages 412-421

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT95-A35167