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