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Number 1

Table of Contents

First In-Pile Experimental Results of High-Plutonium-Content Oxide Fuel for Plutonium Burning in Fast Reactors
Emmanuelle Picard, Jean Noirot, Raymond L. Moss, Helmut Plitz, Karl Richter, Jacques Rouault
Nuclear Technology | Volume 129 | Number 1 | January 2000 | Pages 1-12
Technical Paper | Fission Reactors | doi.org/10.13182/NT00-2
Code Development and Assessment for Reactor Outage Thermal-Hydraulic and Safety Analysis - Midloop Operation with Loss of Residual Heat Removal
Thomas K. S. Liang, Fu-Kuang Ko
Nuclear Technology | Volume 129 | Number 1 | January 2000 | Pages 13-25
Technical Paper | Reactor Safety | doi.org/10.13182/NT00-A3042
A Nodal Kinetics and Thermohydraulics Analysis (NOKTA) Code for Analyzing Rod-Ejection Accidents and Other Transients in Nuclear Power Reactor Cores
Sadi Kaya, Hasbi Yavuz
Nuclear Technology | Volume 129 | Number 1 | January 2000 | Pages 26-35
Technical Paper | Reactor Safety | doi.org/10.13182/NT00-A3043
An Evaluation of Emergency Operator Actions by an Experimental SGTR Event at the IIST Facility and a Comparison of Mihama-2 SGTR Event Record
Tay-Jian Liu, Chien-Hsiung Lee, Ching-Chuan Yao, Show-Chyuan Chiang
Nuclear Technology | Volume 129 | Number 1 | January 2000 | Pages 36-50
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3044
Full-Load-Rejection Design Analysis for the Lungmen Advanced Boiling Water Reactor Using RETRAN
Jan-Ru Tang, Lainsu Kao, Jong-Rong Wang, Ruey-Yng Yuann
Nuclear Technology | Volume 129 | Number 1 | January 2000 | Pages 51-68
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3045
Suppression of Vapor Explosions in a Water-Molten-Tin System by Augmentation of the Void Fraction
Michael K. Meeks, Michael C. Baker, Riccardo Bonazza
Nuclear Technology | Volume 129 | Number 1 | January 2000 | Pages 69-81
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3046
Simulation of Two Loss-of-Flow Transients in a VVER-1000 Nuclear Power Plant with RELAP5/MOD3.2 System Code
Yassin A. Hassan, Dionisie R. Moscalu
Nuclear Technology | Volume 129 | Number 1 | January 2000 | Pages 82-92
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3047
Nonphosphate Degradation Products of Tributyl Phosphate and Their Reactivities in Purex Media Under Extreme Conditions
Yoshikazu Tashiro, Ryuji Kodama, Hiroshi Sugai, Katsuhiko Suzuki, Shingo Matsuoka
Nuclear Technology | Volume 129 | Number 1 | January 2000 | Pages 93-100
Technical Paper | Reprocessing | doi.org/10.13182/NT00-A3048
Long-Term Leaching Experiments of Full-Scale Cemented Waste Forms: Experiments and Modeling
Bernhard Kienzler, Peter Vejmelka, Horst-Jürgen Herbert, Herbert Meyer, Corinna Altenhein-Haese
Nuclear Technology | Volume 129 | Number 1 | January 2000 | Pages 101-118
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT00-A3049
Radiation Chemical Effects in the Near Field of a Final Disposal Site - I: Radiolytic Products Formed in Concentrated NaCl Solutions
M. Kelm, E. Bohnert
Nuclear Technology | Volume 129 | Number 1 | January 2000 | Pages 119-122
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT00-A3050
Radiation Chemical Effects in the Near Field of a Final Disposal Site - II: Simulation of the Radiolytic Processes in Concentrated NaCl Solutions
M. Kelm, E. Bohnert
Nuclear Technology | Volume 129 | Number 1 | January 2000 | Pages 123-130
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT00-A3051
The Self-Ignition Temperatures of Bitumen Mixtures Containing Transition Metal Nitrates
Ken Okada, Masao Nomura, Yasuhiko Fujii
Nuclear Technology | Volume 129 | Number 1 | January 2000 | Pages 131-139
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT00-A3052

Number 2

Table of Contents

Boiling Water Reactor Fuel Behavior Under Reactivity-Initiated-Accident Conditions at Burnup of 41 to 45 GWd/tonne U
Takehiko Nakamura, Makio Yoshinaga, Masato Takahashi, Kazunari Okonogi, Kiyomi Ishijima
Nuclear Technology | Volume 129 | Number 2 | February 2000 | Pages 141-151
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT00-A3053
Process Modeling of Plutonium Conversion and Mixed-Oxide Fuel Fabrication for Plutonium Disposition
Kenneth L. Schwartz, Carl A. Beard
Nuclear Technology | Volume 129 | Number 2 | February 2000 | Pages 152-174
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT00-A3054
A Personal Computer-Based Simulator for Nuclear-Heating Reactors
Jie Liu, Zuoyi Zhang, Dongsen Lu, Zhengang Shi, Xiaoming Chen, Yujie Dong
Nuclear Technology | Volume 129 | Number 2 | February 2000 | Pages 175-186
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3055
Experimental Investigation of Early Initiation of Primary Cooldown by Secondary-Side Depressurization in a PWR Inadequate Core-Cooling Accident
Tay-Jian Liu, Yea-Kuang Chan, Yuh-Ming Ferng, Chien-Yeh Chang
Nuclear Technology | Volume 129 | Number 2 | February 2000 | Pages 187-200
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3056
Validation of the VITAMIN-B6 and BUGLE-96 Cross-Section Libraries for Moderate-Energy Neutron and Photon Transport Calculations
Charles O. Slater, Hamilton T. Hunter
Nuclear Technology | Volume 129 | Number 2 | February 2000 | Pages 201-217
Technical Paper | Radiation Protection | doi.org/10.13182/NT00-A3057
Formulas to Correct Excess Pressure and Pressure Shift to be Used in Volume Measurement for Plutonium Nitrate Solution
Takashi Hosoma, Masanori Aritomi, Tsunemichi Kawa
Nuclear Technology | Volume 129 | Number 2 | February 2000 | Pages 218-235
Technical Paper | Reprocessing | doi.org/10.13182/NT00-A3058
Effect of Solution Concentration on the Properties of a Cementitious Grout Wasteform for Low-Level Nuclear Waste
Amnon Katz, Adrian R. Brough, R. James Kirkpatrick, Leslie J. Struble, J. Francis Young
Nuclear Technology | Volume 129 | Number 2 | February 2000 | Pages 236-245
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT00-A3059
Vitrification of Polyvinyl Chloride Waste from Korean Nuclear Power Plants
Jiawei Sheng, Kwansik Choi, Kyung-Hwa Yang, Myung-Chan Lee, Myung-Jae Song
Nuclear Technology | Volume 129 | Number 2 | February 2000 | Pages 246-256
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT00-A3060
Neutron Beam Optimization for Boron Neutron Capture Therapy Using the D-D and D-T High-Energy Neutron Sources
Jérôme M. Verbeke, Jasmina L. Vujic, Ka-Ngo Leung
Nuclear Technology | Volume 129 | Number 2 | February 2000 | Pages 257-278
Technical Paper | Radiation Biology and Medicine | doi.org/10.13182/NT00-A3061
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
Shekhar Kumar, Sudhir Babu Koganti
Nuclear Technology | Volume 129 | Number 2 | February 2000 | Pages 279-283
Technical Note | Reprocessing | doi.org/10.13182/NT00-A3062

Number 3

Table of Contents

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
J. Manuel Perlado, Jaime Marian, Jesús García Sanz
Nuclear Technology | Volume 129 | Number 3 | March 2000 | Pages 285-296
Technical Paper | Fission Reactors | doi.org/10.13182/NT00-A3063
The Chemistry of Iodine in Containment
Jungsook Clara Wren, Joanne M. Ball, Glenn A. Glowa
Nuclear Technology | Volume 129 | Number 3 | March 2000 | Pages 297-325
Technical Paper | Reactor Safety | doi.org/10.13182/NT129-297
Depletion Analysis of Mixed-Oxide Fuel Pins in Light Water Reactors and the Advanced Test Reactor
Gray S. Chang, John M. Ryskamp
Nuclear Technology | Volume 129 | Number 3 | March 2000 | Pages 326-337
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT00-A3065
Numerical Simulation of Accumulated Steam Generator Tube Sheet Damage and Loose Part Impact Distributions
Liang Shi, J. Michael Doster, Charles W. Mayo
Nuclear Technology | Volume 129 | Number 3 | March 2000 | Pages 338-355
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3066
Testing a Passive Autocatalytic Recombiner in the Surtsey Facility
Thomas K. Blanchat, Asimios C. Malliakos
Nuclear Technology | Volume 129 | Number 3 | March 2000 | Pages 356-373
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3067
Development of the INSPECT Model for the Prediction of Iodine Volatility from Irradiated Solutions
Shirley Dickinson, Howard E. Sims
Nuclear Technology | Volume 129 | Number 3 | March 2000 | Pages 374-386
Technical Paper | Reactor Operations and Control | doi.org/10.13182/NT00-A3068
Measurements of the Radiolytic Oxidation of Aqueous CsI Using a Sparging Apparatus
C. B. Ashmore, D. Brown, S. Dickinson, H. E. Sims
Nuclear Technology | Volume 129 | Number 3 | March 2000 | Pages 387-397
Technical Paper | Reactor Operations and Control | doi.org/10.13182/NT00-A3069
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
Hirotaka Kawamura, Hideo Hirano
Nuclear Technology | Volume 129 | Number 3 | March 2000 | Pages 398-406
Technical Paper | Reactor Operations and Control | doi.org/10.13182/NT00-A3070
A Novel Method for Energy Production Using ^242mAm as a Nuclear Fuel
Yigal Ronen, Menashe Aboudy, Dror Regev
Nuclear Technology | Volume 129 | Number 3 | March 2000 | Pages 407-417
Technical Note | Fission Reactors | doi.org/10.13182/NT00-A3071

Volume 129

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