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Number 1 · January 2000
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Table of Contents
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First In-Pile Experimental Results of High-Plutonium-Content Oxide Fuel for Plutonium Burning in Fast Reactors
Volume 129 · Number 1 · January 2000 · Pages 1-12
Technical Paper · Fission Reactors

Emmanuelle Picard, Jean Noirot, Raymond L. Moss, Helmut Plitz, Karl Richter, Jacques Rouault
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Code Development and Assessment for Reactor Outage Thermal-Hydraulic and Safety Analysis - Midloop Operation with Loss of Residual Heat Removal
Volume 129 · Number 1 · January 2000 · Pages 13-25
Technical Paper · Reactor Safety

Thomas K. S. Liang, Fu-Kuang Ko
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A Nodal Kinetics and Thermohydraulics Analysis (NOKTA) Code for Analyzing Rod-Ejection Accidents and Other Transients in Nuclear Power Reactor Cores
Volume 129 · Number 1 · January 2000 · Pages 26-35
Technical Paper · Reactor Safety

Sadi Kaya, Hasbi Yavuz
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An Evaluation of Emergency Operator Actions by an Experimental SGTR Event at the IIST Facility and a Comparison of Mihama-2 SGTR Event Record
Volume 129 · Number 1 · January 2000 · Pages 36-50
Technical Paper · Thermal Hydraulics

Tay-Jian Liu, Chien-Hsiung Lee, Ching-Chuan Yao, Show-Chyuan Chiang
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Full-Load-Rejection Design Analysis for the Lungmen Advanced Boiling Water Reactor Using RETRAN
Volume 129 · Number 1 · January 2000 · Pages 51-68
Technical Paper · Thermal Hydraulics

Jan-Ru Tang, Lainsu Kao, Jong-Rong Wang, Ruey-Yng Yuann
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Suppression of Vapor Explosions in a Water-Molten-Tin System by Augmentation of the Void Fraction
Volume 129 · Number 1 · January 2000 · Pages 69-81
Technical Paper · Thermal Hydraulics

Michael K. Meeks, Michael C. Baker, Riccardo Bonazza
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Simulation of Two Loss-of-Flow Transients in a VVER-1000 Nuclear Power Plant with RELAP5/MOD3.2 System Code
Volume 129 · Number 1 · January 2000 · Pages 82-92
Technical Paper · Thermal Hydraulics

Yassin A. Hassan, Dionisie R. Moscalu
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Nonphosphate Degradation Products of Tributyl Phosphate and Their Reactivities in Purex Media Under Extreme Conditions
Volume 129 · Number 1 · January 2000 · Pages 93-100
Technical Paper · Reprocessing

Yoshikazu Tashiro, Ryuji Kodama, Hiroshi Sugai, Katsuhiko Suzuki, Shingo Matsuoka
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Long-Term Leaching Experiments of Full-Scale Cemented Waste Forms: Experiments and Modeling
Volume 129 · Number 1 · January 2000 · Pages 101-118
Technical Paper · Radioactive Waste Management and Disposal

Bernhard Kienzler, Peter Vejmelka, Horst-Jürgen Herbert, Herbert Meyer, Corinna Altenhein-Haese
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Radiation Chemical Effects in the Near Field of a Final Disposal Site - I: Radiolytic Products Formed in Concentrated NaCl Solutions
Volume 129 · Number 1 · January 2000 · Pages 119-122
Technical Paper · Radioactive Waste Management and Disposal

M. Kelm, E. Bohnert
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Radiation Chemical Effects in the Near Field of a Final Disposal Site - II: Simulation of the Radiolytic Processes in Concentrated NaCl Solutions
Volume 129 · Number 1 · January 2000 · Pages 123-130
Technical Paper · Radioactive Waste Management and Disposal

M. Kelm, E. Bohnert
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The Self-Ignition Temperatures of Bitumen Mixtures Containing Transition Metal Nitrates
Volume 129 · Number 1 · January 2000 · Pages 131-139
Technical Paper · Radioactive Waste Management and Disposal

Ken Okada, Masao Nomura, Yasuhiko Fujii
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Number 2 · February 2000
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Table of Contents
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Boiling Water Reactor Fuel Behavior Under Reactivity-Initiated-Accident Conditions at Burnup of 41 to 45 GWd/tonne U
Volume 129 · Number 2 · February 2000 · Pages 141-151
Technical Paper · Fuel Cycle and Management

Takehiko Nakamura, Makio Yoshinaga, Masato Takahashi, Kazunari Okonogi, Kiyomi Ishijima
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Process Modeling of Plutonium Conversion and Mixed-Oxide Fuel Fabrication for Plutonium Disposition
Volume 129 · Number 2 · February 2000 · Pages 152-174
Technical Paper · Fuel Cycle and Management

Kenneth L. Schwartz, Carl A. Beard
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A Personal Computer-Based Simulator for Nuclear-Heating Reactors
Volume 129 · Number 2 · February 2000 · Pages 175-186
Technical Paper · Thermal Hydraulics

Jie Liu, Zuoyi Zhang, Dongsen Lu, Zhengang Shi, Xiaoming Chen, Yujie Dong
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Experimental Investigation of Early Initiation of Primary Cooldown by Secondary-Side Depressurization in a PWR Inadequate Core-Cooling Accident
Volume 129 · Number 2 · February 2000 · Pages 187-200
Technical Paper · Thermal Hydraulics

Tay-Jian Liu, Yea-Kuang Chan, Yuh-Ming Ferng, Chien-Yeh Chang
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Validation of the VITAMIN-B6 and BUGLE-96 Cross-Section Libraries for Moderate-Energy Neutron and Photon Transport Calculations
Volume 129 · Number 2 · February 2000 · Pages 201-217
Technical Paper · Radiation Protection

Charles O. Slater, Hamilton T. Hunter
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Formulas to Correct Excess Pressure and Pressure Shift to be Used in Volume Measurement for Plutonium Nitrate Solution
Volume 129 · Number 2 · February 2000 · Pages 218-235
Technical Paper · Reprocessing

Takashi Hosoma, Masanori Aritomi, Tsunemichi Kawa
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Effect of Solution Concentration on the Properties of a Cementitious Grout Wasteform for Low-Level Nuclear Waste
Volume 129 · Number 2 · February 2000 · Pages 236-245
Technical Paper · Radioactive Waste Management and Disposal

Amnon Katz, Adrian R. Brough, R. James Kirkpatrick, Leslie J. Struble, J. Francis Young
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Vitrification of Polyvinyl Chloride Waste from Korean Nuclear Power Plants
Volume 129 · Number 2 · February 2000 · Pages 246-256
Technical Paper · Radioactive Waste Management and Disposal

Jiawei Sheng, Kwansik Choi, Kyung-Hwa Yang, Myung-Chan Lee, Myung-Jae Song
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Neutron Beam Optimization for Boron Neutron Capture Therapy Using the D-D and D-T High-Energy Neutron Sources
Volume 129 · Number 2 · February 2000 · Pages 257-278
Technical Paper · Radiation Biology and Medicine

Jérôme M. Verbeke, Jasmina L. Vujic, Ka-Ngo Leung
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Salt Effect Model for Aqueous Solubility of TBP in a 5 to 100% TBP/n-Dodecane-Nitric Acid-Water Biphasic System at 298.2 K
Volume 129 · Number 2 · February 2000 · Pages 279-283
Technical Note · Reprocessing

Shekhar Kumar, Sudhir Babu Koganti
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Number 3 · March 2000
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Table of Contents
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Neutron Fluence, Dosimetry and Damage Response Determination in In-Core/Ex-Core Components of the VENUS CEN/SCK LWR Using 3-D Monte Carlo Simulations: NEA's VENUS-3 Benchmark
Volume 129 · Number 3 · March 2000 · Pages 285-296
Technical Paper · Fission Reactors

J. Manuel Perlado, Jaime Marian, Jesús García Sanz
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The Chemistry of Iodine in Containment
Volume 129 · Number 3 · March 2000 · Pages 297-325
Technical Paper · Reactor Safety

Jungsook Clara Wren, Joanne M. Ball, Glenn A. Glowa
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Depletion Analysis of Mixed-Oxide Fuel Pins in Light Water Reactors and the Advanced Test Reactor
Volume 129 · Number 3 · March 2000 · Pages 326-337
Technical Paper · Fuel Cycle and Management

Gray S. Chang, John M. Ryskamp
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Numerical Simulation of Accumulated Steam Generator Tube Sheet Damage and Loose Part Impact Distributions
Volume 129 · Number 3 · March 2000 · Pages 338-355
Technical Paper · Thermal Hydraulics

Liang Shi, J. Michael Doster, Charles W. Mayo
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Testing a Passive Autocatalytic Recombiner in the Surtsey Facility
Volume 129 · Number 3 · March 2000 · Pages 356-373
Technical Paper · Thermal Hydraulics

Thomas K. Blanchat, Asimios C. Malliakos
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Development of the INSPECT Model for the Prediction of Iodine Volatility from Irradiated Solutions
Volume 129 · Number 3 · March 2000 · Pages 374-386
Technical Paper · Reactor Operations and Control

Shirley Dickinson, Howard E. Sims
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Measurements of the Radiolytic Oxidation of Aqueous CsI Using a Sparging Apparatus
Volume 129 · Number 3 · March 2000 · Pages 387-397
Technical Paper · Reactor Operations and Control

C. B. Ashmore, D. Brown, S. Dickinson, H. E. Sims
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Estimating the Impurity Concentration Factor on the Boiling Heat Transfer Surface of a Simulated Steam-Generator Tube-Support-Plate Crevice Using an In Situ High-Temperature Conductivity Measurement Technique
Volume 129 · Number 3 · March 2000 · Pages 398-406
Technical Paper · Reactor Operations and Control

Hirotaka Kawamura, Hideo Hirano
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A Novel Method for Energy Production Using 242mAm as a Nuclear Fuel
Volume 129 · Number 3 · March 2000 · Pages 407-417
Technical Note · Fission Reactors

Yigal Ronen, Menashe Aboudy, Dror Regev
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