ANS / Publications / Journals / Nuclear Technology

BWR Regional Instability Analysis by TRAC/BF1-ENTRÉE - I: Application to Density-Wave Oscillation

Akitoshi Hotta, Makoto Honma, Hisashi Ninokata, Yusuke Matsui

Nuclear Technology / Volume 135 / Number 1 / July 2001 / Pages 1-16

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT01-A3202

BWR Regional Instability Analysis by TRAC/BF1-ENTRÉE - II: Application to Ringhals Unit-1 Stability Test

Akitoshi Hotta, Minyan Zhang, Hisashi Ninokata

Nuclear Technology / Volume 135 / Number 1 / July 2001 / Pages 17-38

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT01-A3203

Parallel Computing Adaptive Simulated Annealing Scheme for Fuel Assembly Loading Pattern Optimization in PWRs

Hyun Chul Lee, Hyung Jin Shim, Chang Hyo Kim

Nuclear Technology / Volume 135 / Number 1 / July 2001 / Pages 39-50

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT01-A3204

Thermal-Hydraulic Analysis of the 3-MW TRIGA MARK-II Research Reactor Under Steady-State and Transient Conditions

M. Q. Huda, S. I. Bhuiyan, T. K. Chakrobortty, M. M. Sarker, M. A. W. Mondal

Nuclear Technology / Volume 135 / Number 1 / July 2001 / Pages 51-66

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT01-A3205

An Innovative Fuzzy-Logic-Based Methodology for Trend Identification

Xin Wang, Lefteri H. Tsoukalas, Thomas Y. C. Wei, Jaques Reifman

Nuclear Technology / Volume 135 / Number 1 / July 2001 / Pages 67-84

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT01-A3206

Seismic Design and Analysis of the Support System of the HTR-10 Primary Loop Boundary Components

Zheng-Ming Zhang, Min-Zhi Wang, Shu-Yan He

Nuclear Technology / Volume 135 / Number 2 / August 2001 / Pages 85-91

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT01-A3207

Characterization of the Mobilities of Selected Actinides and Fission/Activation Products in Laboratory Columns Containing Subsurface Material from the Snake River Plain

Robert A. Fjeld, Timothy A. DeVol, Russell W. Goff, Matthew D. Blevins, David D. Brown, Steven M. Ince, Alan W. Elzerman, Meredith E. Newman

Nuclear Technology / Volume 135 / Number 2 / August 2001 / Pages 92-108

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT01-A3208

Using an IIST 1% Cold-Leg SBLOCA Experiment with Passive Safety Injection to Assess the RELAP5/MOD3.2 Code

Chien-Hsiung Lee, I-Ming Huang, Chin-Jang Chang

Nuclear Technology / Volume 135 / Number 2 / August 2001 / Pages 109-122

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT01-A3209

The EOP Visualization Module Integrated into the Plasma On-Line Nuclear Power Plant Safety Monitoring and Assessment System

Arne Hornaes, John Einar Hulsund, János Végh, Csaba Major, Csaba Horváth, Sándor Lipcsei, György Kapocs

Nuclear Technology / Volume 135 / Number 2 / August 2001 / Pages 123-130

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT01-A3210

A Tomographic Method for Verification of the Integrity of Spent Nuclear Fuel Assemblies - I: Simulation Studies

Staffan Jacobsson, Camilla Andersson, Ane Håkansson, Anders Bäcklin

Nuclear Technology / Volume 135 / Number 2 / August 2001 / Pages 131-145

Technical Paper / Enrichment / dx.doi.org/10.13182/NT01-A3211

A Tomographic Method for Verification of the Integrity of Spent Nuclear Fuel Assemblies - II: Experimental Investigation

Staffan Jacobsson, Ane Håkansson, Peter Jansson, Anders Bäcklin

Nuclear Technology / Volume 135 / Number 2 / August 2001 / Pages 146-153

Technical Paper / Enrichment / dx.doi.org/10.13182/NT01-A3212

Effect of Water Radiolysis Caused by Dispersed Radionuclides on Oxidative Dissolution of Spent Fuel in a Final Repository

Jinsong Liu, Ivars Neretnieks

Nuclear Technology / Volume 135 / Number 2 / August 2001 / Pages 154-161

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT01-A3213

Blanket Design Studies of a Lead-Bismuth Eutectic-Cooled Accelerator Transmutation of Waste System

Won Sik Yang, Hussein S. Khalil

Nuclear Technology / Volume 135 / Number 2 / August 2001 / Pages 162-182

Technical Paper / Accelerators / dx.doi.org/10.13182/NT135-162

Source Term Estimation for Small-Sized HTRs: Status and Further Needs, Extracted from German Safety Analyses

Rainer Moormann, Werner Schenk, Karl Verfondern

Nuclear Technology / Volume 135 / Number 3 / September 2001 / Pages 183-193

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT01-A3215

Criticality Behavior of Dilute Plutonium Solutions

Christopher C. Pain, Cassiano R. E. de Oliveira, Antony J. H. Goddard, Adrian P. Umpleby

Nuclear Technology / Volume 135 / Number 3 / September 2001 / Pages 194-215

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT01-A3216

Nondestructive Assay of Nuclear Low-Enriched Uranium Spent Fuels for Burnup Credit Application

Alain Lebrun, Gilles Bignan

Nuclear Technology / Volume 135 / Number 3 / September 2001 / Pages 216-229

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT01-A3217

An Estimation Method for Off-Gas Sources in a Boiling Water Reactor with Nondefective Fuel

Masato Takahashi

Nuclear Technology / Volume 135 / Number 3 / September 2001 / Pages 230-240

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT01-A3218

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

Atul A. Karve, Paul J. Turinsky

Nuclear Technology / Volume 135 / Number 3 / September 2001 / Pages 241-251

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT01-A3219

Refinement of Transient Criteria and Safety Analysis for a High-Temperature Reactor Cooled by Supercritical Water

Kazuaki Kitoh, Seiichi Koshizuka, Yoshiaki Oka

Nuclear Technology / Volume 135 / Number 3 / September 2001 / Pages 252-264

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT01-A3220

KAMINI Reactor South Beam Port Shield-Structure Optimization

K. V. Subbaiah, C. Sunil Sunny

Nuclear Technology / Volume 135 / Number 3 / September 2001 / Pages 265-272

Technical Paper / Radiation Protection / dx.doi.org/10.13182/NT01-A3221

A Coupled Model for Oxidative Dissolution of Spent Fuel and Transport of Radionuclides from an Initially Defective Canister

Longcheng Liu, Ivars Neretnieks

Nuclear Technology / Volume 135 / Number 3 / September 2001 / Pages 273-285

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT01-2

Boron Carbide Deposition on Urania and Urania-Gadolinia Fuels

H. Disbudak, I. Uslu, A. Y. Bilgesu, G. Gündüz

Nuclear Technology / Volume 135 / Number 3 / September 2001 / Pages 286-294

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT01-A3223