ANS / Publications / Journals / Nuclear Technology

Design of a Simulated Void-Reactivity Feedback in a Boiling Water Reactor Loop

H. V. Kok, T. H. J. J. Van der Hagen

Nuclear Technology / Volume 128 / Number 1 / October 1999 / Pages 1-11

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT99-A3009

RAPID-A Fast Reactor Concept Without Any Control Rods

Mitsuru Kambe

Nuclear Technology / Volume 128 / Number 1 / October 1999 / Pages 12-24

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT99-A3010

Radiological Impact at the Extraction Stage of the Thorium Fuel Cycle

J. P. Schapira, R. K. Singhal

Nuclear Technology / Volume 128 / Number 1 / October 1999 / Pages 25-34

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT99-A3011

Fuel Element Burnup Determination in Mixed TRIGA Core Using Reactor Calculations

Matjaz Ravnik, Tomaz Zagar, Andreja Persic

Nuclear Technology / Volume 128 / Number 1 / October 1999 / Pages 35-45

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT99-A3012

Finite Element-Based Vibration Analysis of WWER-440 Reactors

Eberhard Alstadt, Frank-Peter Weiss

Nuclear Technology / Volume 128 / Number 1 / October 1999 / Pages 46-57

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT99-A3013

Turbulence Simulation in Tube Bundle Geometries Using the Dynamic Subgrid-Scale Model

Yassin A. Hassan, Hagop R. Barsamian

Nuclear Technology / Volume 128 / Number 1 / October 1999 / Pages 58-74

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT99-A3014

Natural Circulation Experiments at the ISB-VVER Integral Test Facility and Calculations Using the Thermal-Hydraulic Code ATHLET

Eckhard Krepper, Horst-Michael Prasser

Nuclear Technology / Volume 128 / Number 1 / October 1999 / Pages 75-86

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT99-A3015

RELAP5-3D Multidimensional Heat Conduction Enclosure Model for RBMK Reactor Application

Seungho Paik

Nuclear Technology / Volume 128 / Number 1 / October 1999 / Pages 87-102

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT99-A3016

Precipitation of Uranium and Plutonium from Alkaline Salt Solutions

David T. Hobbs

Nuclear Technology / Volume 128 / Number 1 / October 1999 / Pages 103-112

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT128-103

Development and Validation of ALFUS: An Irradiation Behavior Analysis Code for Metallic Fast Reactor Fuels

Takanari Ogata, Takeshi Yokoo

Nuclear Technology / Volume 128 / Number 1 / October 1999 / Pages 113-123

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT99-A3018

Multinodal Treatment of Production, Decay, and Spreading of Radioactive Isotopes

Péter Vértes

Nuclear Technology / Volume 128 / Number 1 / October 1999 / Pages 124-130

Technical Note / Reactor Safety / dx.doi.org/10.13182/NT99-A3019

Overview of RETRAN Related Activities

Lance J. Agee

Nuclear Technology / Volume 128 / Number 2 / November 1999 / Pages 131-138

Technical Paper / RETRAN / dx.doi.org/10.13182/NT99-A3020

Implementation of an Improved Interfacial Mass and Energy Transfer Model in RETRAN-3D

Rafael Macian, Peter Cebull, Paul Coddington, Mark Paulsen

Nuclear Technology / Volume 128 / Number 2 / November 1999 / Pages 139-152

Technical Paper / RETRAN / dx.doi.org/10.13182/NT99-A3021

Evaluation of the Slip Options in RETRAN-3D

Daniel Maier, Paul Coddington

Nuclear Technology / Volume 128 / Number 2 / November 1999 / Pages 153-168

Technical Paper / RETRAN / dx.doi.org/10.13182/NT99-A3022

Tenth Cofrentes Reload Licensing Analysis with RETRAN-03 Methodology

Rafael de la Fuente, J. Manuel Dey, Pablo G. Sedano, Pedro Mata

Nuclear Technology / Volume 128 / Number 2 / November 1999 / Pages 169-185

Technical Paper / RETRAN / dx.doi.org/10.13182/NT99-A3023

Analyses of Startup Test, Reload Limiting Transient, and Plant Event for the Kuosheng BWR-6 Related to MSIV Closure

Jan-Ru Tang, Shao-Shei Ma, Jan-Der Wang, Show-Chyuan Chiang, Lin-Yao Chou, Ching-Chuan Yao, Ying-Tsen Liao

Nuclear Technology / Volume 128 / Number 2 / November 1999 / Pages 186-204

Technical Paper / RETRAN / dx.doi.org/10.13182/NT99-A3024

Modeling and Simulation of the First ABWR for Validation of RETRAN-3D

Michitsugu Mori

Nuclear Technology / Volume 128 / Number 2 / November 1999 / Pages 205-215

Technical Paper / RETRAN / dx.doi.org/10.13182/NT99-A3025

Mihama Unit 2 Steam Generator Tube Rupture Analysis

Tomohiko Tamaki, Masanori Ohtani, Yasuharu Kawabe

Nuclear Technology / Volume 128 / Number 2 / November 1999 / Pages 216-224

Technical Paper / RETRAN / dx.doi.org/10.13182/NT99-A3026

VIPRE-02 Subchannel Validation Against NUPEC BWR Void Fraction Data

Yacine Aounallah, Paul Coddington

Nuclear Technology / Volume 128 / Number 2 / November 1999 / Pages 225-232

Technical Paper / RETRAN / dx.doi.org/10.13182/NT99-A3027

Main-Steam-Line-Break Analysis of TMI-1 Using RETRAN-3D

Craig E. Peterson, John G. Shatford, Ardesar Irani, Nicholas G. Trikouros, Antonio F. Dias, Lance J. Agee

Nuclear Technology / Volume 128 / Number 2 / November 1999 / Pages 233-244

Technical Paper / RETRAN / dx.doi.org/10.13182/NT99-A3028

Plutonium Recycling in a Full-MOX 900-MW(electric) PWR: Physical Analysis of Accident Behaviors

Sylvie Aniel-Buchheit, André Puill, Richard Sanchez, Mireille Coste

Nuclear Technology / Volume 128 / Number 2 / November 1999 / Pages 245-256

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT99-A3029

A Study on Regional Stability Analysis Methodology with a One-Point Neutron Kinetics Model

Yutaka Takeuchi, Yukio Takigawa, Shiho Miyamoto

Nuclear Technology / Volume 128 / Number 2 / November 1999 / Pages 257-275

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT99-A3030

Application of Neural Networks to Analyze Load-Follow Operation in a Pressurized Water Reactor

Seung Hwan Seong, Un Chul Lee, Si Hwan Kim, Jin Wook Jang

Nuclear Technology / Volume 128 / Number 2 / November 1999 / Pages 276-283

Technical Paper / Reactor Operations and Control / dx.doi.org/10.13182/NT99-A3031

Comparisons of Calculated and Measured ²³⁷Np, ²⁴¹Am, and ²⁴³Am Concentrations as a Function of the ²⁴⁰Pu/²³⁹Pu Isotopic Ratio in Spent Fuel

William S. Charlton, William D. Stanbro, R. T. Perry, Bryan L. Fearey

Nuclear Technology / Volume 128 / Number 3 / December 1999 / Pages 285-299

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT99-A3032

Liquid-Metal-Bonded Gap for Light Water Reactor Fuel Rods

Yeon Soo Kim, D. R. Olander, S. K. Yagnik

Nuclear Technology / Volume 128 / Number 3 / December 1999 / Pages 300-312

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT99-A3033

Applicability of the CONTAIN Code Heat and Mass-Transfer Models to Asymmetrically Heated Vertical Channels

Rajgopal Vijaykumar, Mohsen Khatib-Rahbar

Nuclear Technology / Volume 128 / Number 3 / December 1999 / Pages 313-326

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT99-A3034

Application of a Genetic Neuro-Fuzzy Logic to Departure from Nucleate Boiling Protection Limit Estimation

Man Gyun Na

Nuclear Technology / Volume 128 / Number 3 / December 1999 / Pages 327-340

Technical Paper / Reactor Operations and Control / dx.doi.org/10.13182/NT99-A3035

Impurity Evaluation of Fused Lithium Chloride Salt for a Pilot-Scale Spent-Oxide-Fuel Reduction Process

C. S. Eberle

Nuclear Technology / Volume 128 / Number 3 / December 1999 / Pages 341-358

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT99-A3036

Radiolytic and Chemical Degradation of Strong Acidic Ion-Exchange Resins: Study of the Ligands Formed

L. R. van Loon, W. Hummel

Nuclear Technology / Volume 128 / Number 3 / December 1999 / Pages 359-371

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT99-A3037

The Effect of Degradation Products of Strong Acidic Cation Exchange Resins on Radionuclide Speciation: A Case Study with Ni²⁺

W. Hummel, L. R. van Loon

Nuclear Technology / Volume 128 / Number 3 / December 1999 / Pages 372-387

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT99-A3038

The Degradation of Strong Basic Anion Exchange Resins and Mixed-Bed Ion-Exchange Resins: Effect of Degradation Products on Radionuclide Speciation

L. R. van Loon, W. Hummel

Nuclear Technology / Volume 128 / Number 3 / December 1999 / Pages 388-401

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT99-A3039

The Effective Delayed Neutron Fraction for Bare-Metal Criticals

Sol Pearlstein

Nuclear Technology / Volume 128 / Number 3 / December 1999 / Pages 402-408

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT99-A3040