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Volume 126

Number 1 | Number 2 | Number 3

Number 1

Simulation of Maanshan TMLB' Sequence with MELCOR 1.8.3

Shih-Jen Wang, Chun-Sheng Chien, Te-Chuan Wang

Nuclear Technology / Volume 126 / Number 1 / April 1999 / Pages 1-9

Technical Paper / Reactor Safety

A Study on Boiling Water Reactor Stability Behavior

Dieter Hennig

Nuclear Technology / Volume 126 / Number 1 / April 1999 / Pages 10-31

Technical Paper / Reactor Safety

Reload Light Water Reactor Core Designs for an Ultralong Operating Cycle

Michael V. McMahon, Michael J. Driscoll, Edward E. Pilat, Neil E. Todreas

Nuclear Technology / Volume 126 / Number 1 / April 1999 / Pages 32-47

Technical Paper / Fuel Cycle And Management

Using an IIST SBLOCA Experiment to Assess RELAP5/MOD3.2

Chien-Hsiung Lee, I-Ming Huang, Chin-Jang Chang, Tay-Jian Liu, Yuh-Ming Ferng

Nuclear Technology / Volume 126 / Number 1 / April 1999 / Pages 48-61

Technical Paper / Thermal Hydraulics

Hand Calculation of Safe Separation Distances Between Natural-Gas Pipelines and Boilers and Nuclear Facilities in the Hanford Site 300 Area

Philip M. Daling, Tonia M. Graham

Nuclear Technology / Volume 126 / Number 1 / April 1999 / Pages 62-74

Technical Paper / Criticality of Nuclear Materials

Pitfalls in the Use of Solubility Limits for Radioactive Waste Disposal: The Case of Nickel in Sulfidic Groundwaters

Tres Thoenen

Nuclear Technology / Volume 126 / Number 1 / April 1999 / Pages 75-87

Technical Paper / Radioactive Waste Management and Disposal

DART Model for Irradiation-Induced Swelling of Uranium Silicide Dispersion Fuel Elements

Jeffrey Rest, Gerard L. Hofman

Nuclear Technology / Volume 126 / Number 1 / April 1999 / Pages 88-101

Technical Paper / Materials for Nuclear Systems

A System of 99mTc Production Based on Distributed Electron Accelerators and Thermal Separation

Ralph G. Bennett, Jerry D. Christian, David A. Petti, William K. Terry, S. Blaine Grover

Nuclear Technology / Volume 126 / Number 1 / April 1999 / Pages 102-121

Technical Paper / Radioisotopes

Number 2

Experimental and Analytical Investigation of the Operation Mode of the Emergency Condenser of the SWR1000

Andreas Schaffrath, E. F. Hicken, H. Jaegers, H.-M. Prasser

Nuclear Technology / Volume 126 / Number 2 / May 1999 / Pages 123-142

Technical Paper / Fission Reactors

Assessment of the Severe Accident Mitigation Features of the European Pressurized Water Reactor by Cooperative Research and Development

Wolfgang Eglin, Ulrich Krugmann, Horst A. Weisshäupl, Werner Scholtyssek

Nuclear Technology / Volume 126 / Number 2 / May 1999 / Pages 143-152

Technical Paper / Reactor Safety

FORMOSA-B: A Boiling Water Reactor In-Core Fuel Management Optimization Package

Brian R. Moore, Paul J. Turinsky, Atul A. Karve

Nuclear Technology / Volume 126 / Number 2 / May 1999 / Pages 153-169

Technical Paper / Fuel Cycle and Management

Evaluating Code Uncertainty - I: Using the CSAU Method for Uncertainty Analysis of a Two-Loop PWR SBLOCA

Andrej Prosek, Borut Mavko

Nuclear Technology / Volume 126 / Number 2 / May 1999 / Pages 170-185

Technical Paper / Thermal Hydraulics

Evaluating Code Uncertainty - II: An Optimal Statistical Estimator Method to Evaluate the Uncertainties of Calculated Time Trends

Andrej Prosek, Borut Mavko

Nuclear Technology / Volume 126 / Number 2 / May 1999 / Pages 186-195

Technical Paper / Thermal Hydraulics

Studies on the Shielding Properties of Polyboron and Ilmenite-Magnetite Concrete Using a Reactor Neutron Beam

F. U. Ahmed, S. I. Bhuiyan, A. S. Mollah, M. R. Sarder, M. Q. Huda, M. Rahman, M. A. W. Mondal

Nuclear Technology / Volume 126 / Number 2 / May 1999 / Pages 196-204

Technical Paper / Radiation

Self-Excited Plutonium X-Ray Emission in Plutonium-Bearing Materials

Franco Vittorio Frazzoli, Romolo Remetti, Sergio Guardini, Valeri Maiorov

Nuclear Technology / Volume 126 / Number 2 / May 1999 / Pages 205-214

Technical Paper / Reprocessing

The Volatility of Iodine from Irradiated Iodide Solutions in the Presence or Absence of Painted Surfaces: Modeling Work on the IODE Code at IPSN

Christian Poletiko, Didier Jacquemain, Claude Hueber

Nuclear Technology / Volume 126 / Number 2 / May 1999 / Pages 215-228

Technical Paper / Materials for Nuclear Systems

Analysis of the Mass Transfer Characteristics of a Chemical Addition System

Byong Hoon Chang, Chang Kyu Chung, Anthony F. Mills

Nuclear Technology / Volume 126 / Number 2 / May 1999 / Pages 229-236

Technical Note / Reactor Operations and Control

An Empirical Equation for Vapor Pressure of Tri-n-Butyl Phosphate in the Temperature Range of 273.15 to 562.15 K

Shekhar Kumar, S. B. Koganti

Nuclear Technology / Volume 126 / Number 2 / May 1999 / Pages 237-239

Technical Note / Reprocessing

Number 3

Boundary-Layer-Boiling and Critical-Heat-Flux Phenomena on a Downward-Facing Hemispherical Surface

Fan-Bill Cheung, K. H. Haddad, Y. C. Liu

Nuclear Technology / Volume 126 / Number 3 / June 1999 / Pages 243-264

Technical Paper / Thermal Hydraulics

Plant Behavior Following a Loss-of-Residual-Heat-Removal Event Under a Shutdown Condition

Kwang Won Seul, Young Seok Bang, Hho Jung Kim

Nuclear Technology / Volume 126 / Number 3 / June 1999 / Pages 265-278

Technical Paper / Thermal Hydraulics

Monte Carlo Approach to the Detectability of a Gamma Source Within a Scrap-Iron Truckload

Marzio Marseguerra, Enrico Zio

Nuclear Technology / Volume 126 / Number 3 / June 1999 / Pages 279-288

Technical Paper / Radiation

Behavior of Uranium and Zirconium in Direct Transport Tests with Irradiated EBR-II Fuel

Rajesh Ahluwalia, Thanh Q. Hua, Howard K. Geyer

Nuclear Technology / Volume 126 / Number 3 / June 1999 / Pages 289-302

Technical Paper / Reprocessing

Criticality Safety Assessment for a Conceptual High-Level-Waste Repository in Water-Saturated Geologic Media

Joonhong Ahn

Nuclear Technology / Volume 126 / Number 3 / June 1999 / Pages 303-318

Technical Paper / Radioactive Waste Management and Disposal

A Physical Model to Predict Wear Sites Engendered by Flow-Assisted Corrosion

Yuh-Ming Ferng, Yin-Pang Ma, Kuo-Tong Ma, Nien-Mien Chung

Nuclear Technology / Volume 126 / Number 3 / June 1999 / Pages 319-330

Technical Paper / Materials for Nuclear Systems

RELAP5/MOD3 Code Analyses of LSTF Experiments on Intentional Primary-Side Depressurization Following SBLOCAs with Totally Failed HPI

Hiroshige Kumamaru, Yutaka Kukita, Hideaki Asaka, Ming Wang, Etsuo Ohtani

Nuclear Technology / Volume 126 / Number 3 / June 1999 / Pages 331-339

Technical Note / Thermal Hydraulics

Protection System of the New Control Console of a TRIGA Mark III Nuclear Research Reactor

Tonatiuh Rivero-Gutiérrez, Eduardo Sáinz-Mejía, Jorge S. Benítez-Read, José L. González-Marroquín

Nuclear Technology / Volume 126 / Number 3 / June 1999 / Pages 340-347

Technical Note / Reactor Operations and Control

 

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