ANS / Publications / Journals / Nuclear Technology

Integrated Information System for Analysis of Nuclear Power Plants

Alex Galperin, Kurt Hofer

Nuclear Technology / Volume 108 / Number 1 / October 1994 / Pages 1-12

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT94-A35038

Critical and Power Experiments on the Low-Enriched Uranium Core of the Upgraded Pakistan Research Reactor-1

Saleem A. Ansari, Masood Iqbal, Liaqat Ali, N. M. Butt

Nuclear Technology / Volume 108 / Number 1 / October 1994 / Pages 13-23

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT94-A35039

Core Design of a Direct-Cycle, Supercritical-Water-Cooled Fast Breeder Reactor

Tatjana Jevremovic, Yoshiaki Oka, Sei-Ichi Koshizuka

Nuclear Technology / Volume 108 / Number 1 / October 1994 / Pages 24-32

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT94-A35040

The HEVA Experimental Program

Jean-Pierre Leveque, Bernard Andre, Gérard Ducros, Gilles Le Marois, Gilbert Lhiaubet

Nuclear Technology / Volume 108 / Number 1 / October 1994 / Pages 33-44

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A35041

Boiling Water Reactor Fuel Behavior at Burnup of 26 GWd/tonne U Under Reactivity-Initiated Accident Conditions

Takehiko Nakamura, Makio Yoshinaga, Makoto Sobajima, Kiyomi Ishijima, Toshio Fujishiro

Nuclear Technology / Volume 108 / Number 1 / October 1994 / Pages 45-60

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT94-A35042

Equilibrium Cycle Calculations for Transuranics Recycling in Pressurized Water Reactors

John C. Lee, Jie Du

Nuclear Technology / Volume 108 / Number 1 / October 1994 / Pages 61-79

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT94-A35043

Near-Field Diffusion Releases Through One and Two Finite Planar Zones from a Nuclear Waste Package

Tzou-Shin Ueng, William J. O’Connell

Nuclear Technology / Volume 108 / Number 1 / October 1994 / Pages 80-89

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT94-A35044

Treatability Testing to Evaluate What Can Work

Dirk Gombert II

Nuclear Technology / Volume 108 / Number 1 / October 1994 / Pages 90-99

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT94-A35045

Factors Influencing the Precoat Filtration of Boiling Water Reactor Water Streams

Hans-Peter Hermansson, Göran Persson, Anneli Reinvall

Nuclear Technology / Volume 108 / Number 1 / October 1994 / Pages 100-111

Technical Paper / Material / dx.doi.org/10.13182/NT94-A35046

Two-Dimensional Steady-State and Transient Analyses of Single-Cell Thermionic Fuel Elements

Mohamed S. El-Genk, Huimin Xue

Nuclear Technology / Volume 108 / Number 1 / October 1994 / Pages 112-125

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT94-A35047

Mass Optimization Studies of Gamma Shield Materials for Space Nuclear Reactors

Vojislav Banjac, A. Sharif Heger

Nuclear Technology / Volume 108 / Number 1 / October 1994 / Pages 126-136

Technical Paper / Radiation Protection / dx.doi.org/10.13182/NT94-A35048

Qualification of the ARROTTA Code for Light Water Reactor Accident Analysis

Ping-Hue Huang, Jing-Tong Yang, Jen-Ying Wu

Nuclear Technology / Volume 108 / Number 1 / October 1994 / Pages 137-150

Technical Note / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A35049

Conceptual Designs of Epithermal Neutron Beams for Boron Neutron Capture Therapy from Low-Power Reactors

Hungyuan B. Liu, Robert M. Brugger

Nuclear Technology / Volume 108 / Number 2 / November 1994 / Pages 151-156

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT94-A35026

Development and Comparison of a TOPAZ-II System Model with Experimental Data

Dmitry V. Paramonov, Mohamed S. El-Genk

Nuclear Technology / Volume 108 / Number 2 / November 1994 / Pages 157-170

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT94-A35027

An Integrated Model of the TOPAZ-II Electromagnetic Pump

Mohamed S. El-Genk, Dmitry V. Paramonov

Nuclear Technology / Volume 108 / Number 2 / November 1994 / Pages 171-180

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT94-A35028

Characteristics of the Flow-Controlled Accumulator

Tadashi Shiraishi, Hisato Watakabe, Nobuo Nakamori, Kozo Tabuchi, Yoji Takayama, Takayoshi Sugizaki

Nuclear Technology / Volume 108 / Number 2 / November 1994 / Pages 181-190

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT94-A35029

RELAP5/MOD3 Simulation of the Loss of the Residual Heat Removal System During a Midloop Operation Experiment Conducted at the ROSA-IV Large-Scale Test Facility

Yassin A. Hassan, Sibashis S. Banerjee

Nuclear Technology / Volume 108 / Number 2 / November 1994 / Pages 191-206

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A35030

Strength of Silicon Carbide Layers of Fuel Particles for High-Temperature Gas-Cooled Reactors

Paul A. Lessing, Ronald J. Heaps

Nuclear Technology / Volume 108 / Number 2 / November 1994 / Pages 207-234

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT94-A35031

Preliminary Neutronics Investigation of the Delayed Neutron Nondestructive Assay of an Integral Fast Reactor Waste Canister

Cheng-Wei Wu, Douglass L. Henderson, Edgar F. Bennett

Nuclear Technology / Volume 108 / Number 2 / November 1994 / Pages 235-255

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT94-A35032

A Modeling Study of Parameters ControIIing Local Concentration Processes in Pressurized Water Reactor Steam Generators

Peter J. Millett, James M. Fenton

Nuclear Technology / Volume 108 / Number 2 / November 1994 / Pages 256-265

Technical Paper / Material / dx.doi.org/10.13182/NT94-A35033

Effect of External Cooling on the Thermal Behavior of a Boiling Water Reactor Vessel Lower Head

Hyunjae Park, V. K. Dhir, William E. Kastenberg

Nuclear Technology / Volume 108 / Number 2 / November 1994 / Pages 266-282

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT94-A35034

Error Prediction for a Nuclear Power Plant Fault-Diagnostic Advisor Using Neural Networks

Keehoon Kim, Eric B. Bartlett

Nuclear Technology / Volume 108 / Number 2 / November 1994 / Pages 283-297

Technical Paper / Reactor Control / dx.doi.org/10.13182/NT94-A35035

Cross-Section Parameterization Using Irradiation Time and Exposure for Global Depletion Analysis

Steven E. Aumeier, John C. Lee, Derek M. Cribley, William R. Martin

Nuclear Technology / Volume 108 / Number 3 / December 1994 / Pages 299-319

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT94-A35014

Rough Estimates of Severe Accident Containment Loads Accompanying Vessel Breach in Boiling Water Reactors

Mark T. Leonard

Nuclear Technology / Volume 108 / Number 3 / December 1994 / Pages 320-337

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A35015

Analysis of a Core Disruptive Accident in a Liquid-Metal-Cooled Fast Breeder Reactor Using the Near-Characteristic Method

Jayan K. George, Jagdeep B. Doshi

Nuclear Technology / Volume 108 / Number 3 / December 1994 / Pages 338-349

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A35016

Stability Measurements in the German Nuclear Power Plant Wuergassen During Cycle 14

Ethwart Pollmann, Joachim Schulze, Dieter Kreuter

Nuclear Technology / Volume 108 / Number 3 / December 1994 / Pages 350-360

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A35017

Chinese Experience in the Removal of Actinides from Highly Active Waste by Trialkylphosphine-Oxide Extraction

Yongjun Zhu, Rongzhou Jiao

Nuclear Technology / Volume 108 / Number 3 / December 1994 / Pages 361-369

Technical Paper / Enrichment and Reprocessing System / dx.doi.org/10.13182/NT94-A35018

Development of a Demister for a Waste Evaporator Using a Hydrophobic Membrane Filter

Kiyomi Funabashi, Koichi Chino, Tsutomu Baba, Hiroyuki Tsuchiya, Tatsuo Izumida, Toshio Sawa

Nuclear Technology / Volume 108 / Number 3 / December 1994 / Pages 370-378

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT94-A35019

The Benchmarking of a Homogeneous Equilibrium Model for Analysis of Spent-Fuel Shipping Containers

Steven J. Manson, Dale E. Klein

Nuclear Technology / Volume 108 / Number 3 / December 1994 / Pages 379-386

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT94-A35020

RELAP5/MOD3 Modeling of Water Column Rejoining and a Water Slug Propelled by Noncondensable Gas

W. S. Yeung, J. Shirkov, F. Seifaee

Nuclear Technology / Volume 108 / Number 3 / December 1994 / Pages 387-394

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT94-A35021

Validation of the ATR-SINDA Fuel Plate Model Using Advanced Test Reactor Startup Data

Steven T. Polkinghorne

Nuclear Technology / Volume 108 / Number 3 / December 1994 / Pages 395-412

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT94-A35022

A Transient Analysis of Decomposition and Erosion of Concrete Exposed to a Surface Heat Flux

Arif Nesimi Kiliç

Nuclear Technology / Volume 108 / Number 3 / December 1994 / Pages 413-420

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT94-A35023

Maximum Likelihood Factor Analysis of the Reactor Coolant Pump System

William S. Grenzebach, Carolyn D. Heising, Thomas J. Marx

Nuclear Technology / Volume 108 / Number 3 / December 1994 / Pages 421-433

Technical Paper / Reactor Operation / dx.doi.org/10.13182/NT94-A35024