ANS / Publications / Journals / Nuclear Technology

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 / dx.doi.org/10.13182/NT99-A2954

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 / dx.doi.org/10.13182/NT99-A2955

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 / dx.doi.org/10.13182/NT99-A2956

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 / dx.doi.org/10.13182/NT99-A2957

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 / dx.doi.org/10.13182/NT99-A2958

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 / dx.doi.org/10.13182/NT99-A2959

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 / dx.doi.org/10.13182/NT99-A2960

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 / dx.doi.org/10.13182/NT99-A2961

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 / dx.doi.org/10.13182/NT99-A2962

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 / dx.doi.org/10.13182/NT99-A2963

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 / dx.doi.org/10.13182/NT99-A2964

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 / dx.doi.org/10.13182/NT99-A2965

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 / dx.doi.org/10.13182/NT99-A2966

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 / dx.doi.org/10.13182/NT99-A2967

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 / dx.doi.org/10.13182/NT99-A2968

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 / dx.doi.org/10.13182/NT99-A2969

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 / dx.doi.org/10.13182/NT99-A2970

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 / dx.doi.org/10.13182/NT99-A2971

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 / dx.doi.org/10.13182/NT99-A2972

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 / dx.doi.org/10.13182/NT99-A2973

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 / dx.doi.org/10.13182/NT99-A2974

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 / dx.doi.org/10.13182/NT99-A2975

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 / dx.doi.org/10.13182/NT99-A2976

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 / dx.doi.org/10.13182/NT99-A2977

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 / dx.doi.org/10.13182/NT99-A2978

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 / dx.doi.org/10.13182/NT99-A2979