ANS / Publications / Journals / Nuclear Technology

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NT00-A3052

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NT00-A3062

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NT00-A3071