ANS / Publications / Journals / Nuclear Technology

Systems Design of Direct-Cycle Supercritical-Water-Cooled Fast Reactors

Yoshiaki Oka, Sei-Ichi Koshizuka, Tatjana Jevremovic, Yasushi Okano

Nuclear Technology / Volume 109 / Number 1 / January 1995 / Pages 1-10

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT95-A35064

Analysis of Epithermal Neutron Beam Experiments at the Hifar Reactor

Baiba V. Harrington, Geoffrey Constantine

Nuclear Technology / Volume 109 / Number 1 / January 1995 / Pages 11-20

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT95-A35065

Outline of the Uncertainty Methodology Based on Accuracy Extrapolation

Francesco D’auria, Nenad Debrecin, Giorgio Maria Galassi

Nuclear Technology / Volume 109 / Number 1 / January 1995 / Pages 21-38

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT109-21

Modeling of Cesium Release from Light Water Reactor Fuel Under Severe Accident Conditions

Anne C. Harnden-Gillis, Brent J. Lewis, William S. Andrews, Peter L. Purdy, Morris F. Osborne, Richard A. Lorenz

Nuclear Technology / Volume 109 / Number 1 / January 1995 / Pages 39-53

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT95-A35067

Evaluation of the Uncertainties in the Source Distribution for Pressure Vessel Neutron Fluence Calculations

Alireza Haghighat, Moussa Mahgerefteh, Bojan G. Petrovic

Nuclear Technology / Volume 109 / Number 1 / January 1995 / Pages 54-75

Technical Paper / Material / dx.doi.org/10.13182/NT95-A35068

A Fluid Discontinuity Tracking Methodology for Finite Difference Thermal-Hydraulic Simulation

Michael J. Zavisca, J. Michael Doster

Nuclear Technology / Volume 109 / Number 1 / January 1995 / Pages 76-86

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT95-A35069

Neutronics and Thermal-Hydraulics Analyses of the Pellet Bed Reactor for Nuclear Thermal Propulsion

Nicholas J. Morley, Mohamed S. El-Genk

Nuclear Technology / Volume 109 / Number 1 / January 1995 / Pages 87-107

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT95-A35070

Numerical Predictions of Turbulent Flow Around a Structure Via the k-∈ Model for Reactor Vessel Auxiliary Cooling System Performance Analysis

Constantine P. Tzanos

Nuclear Technology / Volume 109 / Number 1 / January 1995 / Pages 108-122

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT95-A35071

Helium-Air Exchange Flow Through Annular and Round Tubes

Motoo Fumizawa, Makoto Hishida

Nuclear Technology / Volume 109 / Number 1 / January 1995 / Pages 123-131

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT95-A35072

Determination of Time-Dependent Void Fraction Distribution in Bubbly Two-Phase Flow by A Real-Time Neutron Radiography Technique

G. D. Harvel, J. S. Chang, V. Santhana Krishnan

Nuclear Technology / Volume 109 / Number 1 / January 1995 / Pages 132-141

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT95-A35073

Simplified Evaluation Models for Total Fission Number in a Criticality Accident

Yasushi Nomura, Hiroshi Okuno

Nuclear Technology / Volume 109 / Number 1 / January 1995 / Pages 142-152

Technical Paper / Nuclear Criticality Safety / dx.doi.org/10.13182/NT95-A35074

Feedwater Control System Design with the Kuosheng Plant Analyzer

Shih-Jen Wang, Shih-Hsiin Chang, Chun-Sheng Chien, Ling-Yao Chou

Nuclear Technology / Volume 109 / Number 1 / January 1995 / Pages 153-160

Technical Paper / Reactor Control / dx.doi.org/10.13182/NT95-A35075

Simple Method for Technetium Removal from Aqueous Solutions

G. D. Del Cul, William D. Bostick

Nuclear Technology / Volume 109 / Number 1 / January 1995 / Pages 161-162

Technical Note / Material / dx.doi.org/10.13182/NT95-A35076

Modeling of Molten Metal/Water Interactions

Ali Uludogan, Michael L. Corradini

Nuclear Technology / Volume 109 / Number 2 / February 1995 / Pages 171-186

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT109-171

Influence of Isolation Condensers on Boiling Water Reactor Performance During an Anticipated Transient Without Scram

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

Nuclear Technology / Volume 109 / Number 2 / February 1995 / Pages 187-206

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT95-A35052

Iodine Release During a Steam Generator Tube Rupture

James P. Adams

Nuclear Technology / Volume 109 / Number 2 / February 1995 / Pages 207-215

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT95-A35053

Extraction Chromatographic Separation of Minor Actinides from PUREX High-Level Wastes Using CMPO

J. N. Mathur, M. S. Murali, R. H. Iyer, A. Ramanujam, P. S. Dhami, V. Gopalakrishnan, M. K. Rao, L. P. Badheka, Asoke Banerji

Nuclear Technology / Volume 109 / Number 2 / February 1995 / Pages 216-225

Technical Paper / Enrichment and Reprocessing System / dx.doi.org/10.13182/NT95-A35054

Reactor-Based Prompt Gamma Neutron Activation Setup Using a Low-Power Research Reactor

Chien Chung, Liq-Ji Yuan

Nuclear Technology / Volume 109 / Number 2 / February 1995 / Pages 226-235

Technical Paper / Radiation Application / dx.doi.org/10.13182/NT95-A35055

Experimental Study on Flow Rate Measurement of Buoyancy-Driven Exchange Flow

Motoo Fumizawa

Nuclear Technology / Volume 109 / Number 2 / February 1995 / Pages 236-245

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT95-A35056

Fundamental Study on Duplex Steam Generator Tubes for Liquid-Metal-Cooled Fast Reactors

Masanori Aritomi, Tomoaki Mizushima, Hiroshi Yabuta

Nuclear Technology / Volume 109 / Number 2 / February 1995 / Pages 246-254

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT95-A35057

Intelligent Alarm-Processing System for Nuclear Power Plants

Norio Naito, Shiroh Ohtsuka

Nuclear Technology / Volume 109 / Number 2 / February 1995 / Pages 255-264

Technical Paper / Reactor Operation / dx.doi.org/10.13182/NT95-A35058

In Situ Gamma Spectrometry of Piping in a CANDU Heat Transport System — Application During Decontamination

Aamir Husain, Calvin E. Breckenridge, David Storey

Nuclear Technology / Volume 109 / Number 2 / February 1995 / Pages 265-274

Technical Paper / Reactor Operation / dx.doi.org/10.13182/NT95-A35059

Simulation of a Marine Nuclear Reactor

Tsuyoshi Kusunoki, Masahiko Kyouya, Hideo Kobayashi, Masa-Aki Ochiai

Nuclear Technology / Volume 109 / Number 2 / February 1995 / Pages 275-285

Technical Paper / Reactor Operation / dx.doi.org/10.13182/NT95-A35060

Artificial Neural Networks Versus Conventional Methods for Boiling Water Reactor Stability Monitoring

Tim H. J. J. van der Hagen

Nuclear Technology / Volume 109 / Number 2 / February 1995 / Pages 286-305

Technical Paper / Reactor Control / dx.doi.org/10.13182/NT95-A35061

Design Study of Lead- and Lead-Bismuth-Cooled Small Long-Life Nuclear Power Reactors Using Metallic and Nitride Fuel

Hiroshi Sekimoto, Zaki Su’ud

Nuclear Technology / Volume 109 / Number 3 / March 1995 / Pages 307-313

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT109-307

Design of Neutron Beams for Neutron Capture Therapy Using a 300-kW Slab TRIGA Reactor

Hungyuan B. Liu

Nuclear Technology / Volume 109 / Number 3 / March 1995 / Pages 314-326

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT95-A35080

Simulation of the IAEA’s Fourth Standard Problem Exercise Small-Break Loss-of-Coolant Accident Using RELAP5/MOD3.1

Peter P. Cebull, Yassin A. Hassan

Nuclear Technology / Volume 109 / Number 3 / March 1995 / Pages 327-337

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT95-A35081

Passive Safety Injection Experiments with a Large-Scale Pressurized Water Reactor Simulator

Taisuke Yonomoto, Yutaka Kukita, Yoshinari Anoda, Hideaki Asaka

Nuclear Technology / Volume 109 / Number 3 / March 1995 / Pages 338-345

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT95-A35082

Implementation of a New Model for Gravitational Collision Cross Sections in Nuclear Aerosol Codes

Robert L. Buckley, Sudarshan K. Loyalka

Nuclear Technology / Volume 109 / Number 3 / March 1995 / Pages 346-356

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT95-A35083

Nuclear Analysis for the Boraflex Used in a Typical Spent-Fuel Storage Assembly

Insoo Jun, Myung Jae Song

Nuclear Technology / Volume 109 / Number 3 / March 1995 / Pages 357-365

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT95-A35084

Investigation of Silver-Impregnated Alumina for Removal of Radioactive Methyl Iodide

Kiyomi Funabashi, Tetsuo Fukasawa, Makoto Kikuchi

Nuclear Technology / Volume 109 / Number 3 / March 1995 / Pages 366-372

Technical Paper / Enrichment and Reprocessing System / dx.doi.org/10.13182/NT95-A35085

Remodeling of the Oxidant Species During Radiolysis of High-Temperature Water in a Pressurized Water Reactor

Hilbert Christensen

Nuclear Technology / Volume 109 / Number 3 / March 1995 / Pages 373-382

Technical Paper / Material / dx.doi.org/10.13182/NT95-A35086

Calculation and Benchmarking of an Azimuthal Pressure Vessel Neutron Fluence Distribution Using the Boxer Code and Scraping Experiments

Frank Holzgrewe, Ferenc Hegedues, Jean M. Paratte

Nuclear Technology / Volume 109 / Number 3 / March 1995 / Pages 383-397

Technical Paper / Material / dx.doi.org/10.13182/NT95-A35087

Investigation of Scale-Up Capability of RELAP5/MOD3 and Scaling Distortion in the IIST Facility Via Natural Circulation Experiments

Yuh-Ming Ferng, Bau-Shei Pei, Tuan-Ji Ding

Nuclear Technology / Volume 109 / Number 3 / March 1995 / Pages 398-411

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT95-A35088

Operational Control of Boiling Water Reactor Stability

Christofer M. Mowry, Israel Nir

Nuclear Technology / Volume 109 / Number 3 / March 1995 / Pages 412-428

Technical Paper / Reactor Control / dx.doi.org/10.13182/NT95-A35089

Assessment of Costs and Benefits Associated with Resolution of Generic Safety Issue 143—Availability of Heating, Ventilation, and Air Conditioning and Chilled Water Systems

Philip M. Daling, Jay E. Marler, Truong V. Vo, Hanh K. Phan, John R. Friley

Nuclear Technology / Volume 109 / Number 3 / March 1995 / Pages 429-436

Technical Note / Nuclear Reactor Safety / dx.doi.org/10.13182/NT95-A35090