American Nuclear Society
Home

Home / Publications / Journals / Nuclear Technology / Volume 135 / Number 3

Volume 135

Number 3

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