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Volume 124

Number 1 | Number 2 | Number 3

Number 1

An Experimental Study of Meteorological Dispersion in Siting Phases II and III of the Qinshan Nuclear Power Plant

Erbang Hu, Maoshuan Zhang, Shoushu Wang, Zhanrong Gao, Rentai Yao, Naixian Pan, Jiayi Chen, Zhong Chen, Jinsong Qiao, Huaide Zhang

Nuclear Technology / Volume 124 / Number 1 / October 1998 / Pages 1-17

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT98-A2905

Heat Transfer Analysis of the Passive Residual Heat Removal System in ROSA/AP600 Experiments

Taisuke Yonomoto, Yutaka Kukita, Richard R. Schultz

Nuclear Technology / Volume 124 / Number 1 / October 1998 / Pages 18-30

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT98-A2906

FlowAct, Flow Rate Measurements in Pipes with the Pulsed-Neutron Activation Method

Per Lindén, Gudmar Grosshög, Imre Pázsit

Nuclear Technology / Volume 124 / Number 1 / October 1998 / Pages 31-51

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT98-A2907

Modification of the Reflood Model in RELAP5/MOD3.1

Hae Yong Jeong, Hee Cheon No

Nuclear Technology / Volume 124 / Number 1 / October 1998 / Pages 52-64

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT98-A2908

Emergency Core Cooling Mode of the European Pressurized Water Reactor: The Evolution from Combined Injection to Cold-Leg Injection

Florin Curca-Tivig

Nuclear Technology / Volume 124 / Number 1 / October 1998 / Pages 65-81

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT98-A2909

Estimating Heat Generation Rates for Wastes Contaminated Primarily by 137Cs and 90Sr

Mark S. Jarzemba

Nuclear Technology / Volume 124 / Number 1 / October 1998 / Pages 82-87

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT98-A2910

Flow Barrier System for Long-Term High-Level-Waste Isolation: Experimental Results

James L. Conca, Michael J. Apted, Wei Zhou, Randolph C. Arthur, John H. Kessler

Nuclear Technology / Volume 124 / Number 1 / October 1998 / Pages 88-100

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT98-A2911

Number 2

Assessment and Improvement of Condensation Models in RELAP5/MOD3.2

Ki Yong Choi, Hyun Sik Park, Sang Jae Kim, Hee Cheon No, Yong Seok Bang

Nuclear Technology / Volume 124 / Number 2 / November 1998 / Pages 103-117

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT98-A2912

Nuclear Power Plant Transient Diagnostics Using Transfer Functions as Estimators

Igor Salamun, Andrej Stritar

Nuclear Technology / Volume 124 / Number 2 / November 1998 / Pages 118-137

Technical Paper / Reactor Operations and Control / dx.doi.org/10.13182/NT98-A2913

Dose-Reduction Improvements in Storage Basins of Spent Nuclear Fuel

Frank H. Huang, Francis W. Moore

Nuclear Technology / Volume 124 / Number 2 / November 1998 / Pages 138-146

Technical Paper / Decontamination/Decommissioning / dx.doi.org/10.13182/NT98-A2914

Newly Developed Decontamination Technology Based on Gaseous Reactions Converting to Carbonyl and Fluoric Compounds

Katsuyoshi Tatenuma, Yukio Hishinuma, Satoshi Tomatsuri, Kousaburo Ohashi, Yoshiharu Usui

Nuclear Technology / Volume 124 / Number 2 / November 1998 / Pages 147-164

Technical Paper / Decontamination/Decommissioning / dx.doi.org/10.13182/NT98-A2915

Calculations Simulating Spent-Fuel Leaching Experiments

Hilbert Christensen

Nuclear Technology / Volume 124 / Number 2 / November 1998 / Pages 165-174

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT98-A2916

Conceptual Design of a Californium-Based Epithermal Neutron Beam for Boron Neutron Capture Therapy Using a Subcritical Multiplying Assembly

Do Heon Kim, Jong Kyung Kim

Nuclear Technology / Volume 124 / Number 2 / November 1998 / Pages 175-182

Technical Paper / Radiation Biology and Medicine / dx.doi.org/10.13182/NT98-A2917

Estimate of the Radiation Environment and of the Shielding Aspect for the Large Hadron Collider POINT2 Area

Galina Chabratova, Lars Leistam

Nuclear Technology / Volume 124 / Number 2 / November 1998 / Pages 183-191

Technical Paper / Accelerators / dx.doi.org/10.13182/NT98-A2918

Radioactive Release and Dose Calculations for the HTR-10

Yuan-Zhong Liu

Nuclear Technology / Volume 124 / Number 2 / November 1998 / Pages 192-197

Technical Note / Reactor Safety / dx.doi.org/10.13182/NT98-A2919

Number 3

Criticality Studies on Molten Lead Energy Amplifiers

Akinori Oda, José M. Martinez-Val, J. Manuel Perlado

Nuclear Technology / Volume 124 / Number 3 / December 1998 / Pages 201-214

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT98-A2920

The Nonproliferative Light Water Thorium Reactor: A New Approach to Light Water Reactor Core Technology

Alvin Radkowsky, Alex Galperin

Nuclear Technology / Volume 124 / Number 3 / December 1998 / Pages 215-222

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT98-A2921

Modeling of Boiling Water Reactor Feedwater Control Algorithms

J. A. Mowrey, P. R. Boylan, S. I. Abdel-Khalik

Nuclear Technology / Volume 124 / Number 3 / December 1998 / Pages 223-242

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT98-A2922

A New Mechanistic Critical Heat Flux Model at Low-Pressure and Low-Flow Conditions

Kuan-Chywan Tu, Chien-Hsiung Lee, Shih-Jen Wang, Bau-Shei Pei

Nuclear Technology / Volume 124 / Number 3 / December 1998 / Pages 243-254

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT98-A2923

Application of Algebraic Specification to Verify the Design of Safety Logic in Nuclear Power Plants

Akira Fukumoto, Toshifumi Hayashi, Akihiko Ohsuga, Shinichi Honiden, Nobuyuki Mori

Nuclear Technology / Volume 124 / Number 3 / December 1998 / Pages 255-264

Technical Paper / Reactor Operations and Control / dx.doi.org/10.13182/NT98-A2924

A High-Definition Gamma Scanning Method for the Near-Field Nondestructive Assay of Large Nuclear Waste Barrels

Chin-Jen Chang, Samim Anghaie

Nuclear Technology / Volume 124 / Number 3 / December 1998 / Pages 265-275

Technical Paper / Radiation Measurements and Instrumentation / dx.doi.org/10.13182/NT98-A2925

A Feasibility Study of Gross Alpha Counting in Environmental Samples Using a Superheated-Liquid-Droplet Technique

Lung Kwang Pan

Nuclear Technology / Volume 124 / Number 3 / December 1998 / Pages 276-283

Technical Paper / Radiation Measurements and Instrumentation / dx.doi.org/10.13182/NT98-A2926

Analysis of the Reactivity During a Pressurized Water Reactor Main-Steam-Line-Break Transient

Garry C. Gose, Thomas J. Downar, Karl O. Ott

Nuclear Technology / Volume 124 / Number 3 / December 1998 / Pages 284-290

Technical Note / Reactor Safety / dx.doi.org/10.13182/NT98-A2927