Home / Publications / Journals / Nuclear Technology / Volume 61 / Number 2
Nuclear Technology / Volume 61 / Number 2 / May 1983 / Pages 143-152
Technical Paper / Second International RETRAN Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT83-A33186
RETRAN Nonequilibrium Two-Phase Flow Model for Operational Transient Analyses
Nuclear Technology / Volume 61 / Number 2 / May 1983 / Pages 153-166
Technical Paper / Second International RETRAN Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT83-A33187
Numerical Solution Method Improvements for RETRAN
Nuclear Technology / Volume 61 / Number 2 / May 1983 / Pages 167-180
Technical Paper / Second International RETRAN Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT83-A33188
RETRAN-02 Calculations of Operational Transients in the Loss-of-Fluid Test Facility
Nuclear Technology / Volume 61 / Number 2 / May 1983 / Pages 181-192
Technical Paper / Second International RETRAN Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT83-A33189
RETRAN Safety Analyses of the Nuclear-Powered Ship Mutsu
Nuclear Technology / Volume 61 / Number 2 / May 1983 / Pages 193-204
Technical Paper / Second International RETRAN Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT83-A33190
Prediction of GE-Atlas Transient Boiling Transition Data Using RETRAN-02/RETRAN-15F
Nuclear Technology / Volume 61 / Number 2 / May 1983 / Pages 205-211
Technical Paper / Second International RETRAN Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT83-A33191
RETRANS’s Role in the Development of Northeast Utilities’ Analytical Capabilities
Nuclear Technology / Volume 61 / Number 2 / May 1983 / Pages 212-223
Technical Paper / Second International RETRAN Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT83-A33192
RETRAN-02 and DYNODE-P Analyses of a Steam Generator Tube Break Transient
Nuclear Technology / Volume 61 / Number 2 / May 1983 / Pages 224-237
Technical Paper / Second International RETRAN Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT83-A33193
RETRAN-02 Analysis of Arkansas Nuclear One Unit 2 Tests
Nuclear Technology / Volume 61 / Number 2 / May 1983 / Pages 238-252
Technical Paper / Second International RETRAN Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT83-A33194
RETRAN Analyses for Improving Plant Procedures and Operator Training
Nuclear Technology / Volume 61 / Number 2 / May 1983 / Pages 253-259
Technical Paper / Second International RETRAN Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT83-A33195
Nuclear Technology / Volume 61 / Number 2 / May 1983 / Pages 260-275
Technical Paper / Second International RETRAN Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT83-A33196
Qualification of a RETRAN-02 Model for Boiling Water Reactor Transient Analysis
Nuclear Technology / Volume 61 / Number 2 / May 1983 / Pages 276-295
Technical Paper / Second International RETRAN Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT83-A33197
Boiling Water Reactor Stability Analysis with RETRAN
Nuclear Technology / Volume 61 / Number 2 / May 1983 / Pages 296-312
Technical Paper / Second International RETRAN Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT83-A33198
Evaluation of RETRAN-02 Options with Peach Bottom Data
Nuclear Technology / Volume 61 / Number 2 / May 1983 / Pages 313-328
Technical Paper / Second International RETRAN Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT83-A33199
Simplified Tornado Depressurization Design Methods for Nuclear Power Plants
Nuclear Technology / Volume 61 / Number 2 / May 1983 / Pages 329-337
Technical Paper / Second International RETRAN Meeting / Fission reactor / dx.doi.org/10.13182/NT83-A33200
Deactivation of Silver Zeolite Adsorbers by Airborne Organics
Nuclear Technology / Volume 61 / Number 2 / May 1983 / Pages 338-343
Technical Paper / Second International RETRAN Meeting / Nuclear Safety / dx.doi.org/10.13182/NT83-A33201
Analysis of Creep for Nuclear Waste Storage in a Salt Formation
Nuclear Technology / Volume 61 / Number 2 / May 1983 / Pages 344-352
Technical Paper / Second International RETRAN Meeting / Radioactive Waste Management / dx.doi.org/10.13182/NT83-A33202
Optimal Step Assays and Flow Rates in Gaseous Diffusion Squared-Off Cascades for Uranium Enrichment
Nuclear Technology / Volume 61 / Number 2 / May 1983 / Pages 353-361
Technical Paper / Second International RETRAN Meeting / Radioisotopes and Isotope / dx.doi.org/10.13182/NT83-A33203