American Nuclear Society
Join ANS|Member Center|ANS Store|Contact Us
Home

Home / Publications / Journals / Nuclear Technology / Volume 93 / Number 2

Volume 93

Number 2

Sensitivity Analysis of Thermal-Hydraulic Parameters and Probability Estimation of Boiling Transition in a Standard BWR/6

Smaeil M. Aceil, Doyle R. Edwards

Nuclear Technology / Volume 93 / Number 2 / February 1991 / Pages 123-130

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT91-A34498

Sequential Probability Ratio Test for Nuclear Plant Component Surveillance

Kenny C. Gross, Keith E. Humenik

Nuclear Technology / Volume 93 / Number 2 / February 1991 / Pages 131-137

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT91-A34499

Core Simulations Using Actual Detector Readings for a Canada Deuterium Uranium Reactor

Bong Ghi Kim, In Sup Kim, Seong Yun Kim

Nuclear Technology / Volume 93 / Number 2 / February 1991 / Pages 138-146

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT91-A34500

Decontamination of Liquid-Metal Fast Breeder Reactor Components for Reuse: The French Experience

Patrick Michaille, Jean-Claude Moroni, Irma Lambert

Nuclear Technology / Volume 93 / Number 2 / February 1991 / Pages 147-157

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT91-A34501

The Potential for Catastrophic Fuel Damage During Beyond-Design-Basis Overpressurization Accidents in a Boiling Water Reactor

David J. Diamond, Dragan Mirkovic, Chia-Jung Hsu, Robert Fitzpatrick

Nuclear Technology / Volume 93 / Number 2 / February 1991 / Pages 158-165

Technical Paper / Nuclear Reactor Safet / dx.doi.org/10.13182/NT91-A34502

Countercurrent Flow Limitation Model for RELAP5/MOD3

Richard A. Riemke

Nuclear Technology / Volume 93 / Number 2 / February 1991 / Pages 166-173

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT91-A34503

Small-Scale Experiments Conducted to Support Investigation of HypotheticalDesign-Basis LOCA Phenomena in the Advanced Test Reactor

Thomas K. Larson, Keith G. Condie, Steven T. Polkinghorne, Brent J. Buescher

Nuclear Technology / Volume 93 / Number 2 / February 1991 / Pages 174-194

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT91-A34504

A Statistical Model for Prediction of Fuel Element Failure Using the Markov Process and Entropy Minimax Principles

Kie-Yong Choi, Young-Ku Yoon, Soon-Heung Chang

Nuclear Technology / Volume 93 / Number 2 / February 1991 / Pages 195-205

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT91-A34505

Development of Partitioning and Transmutation Technology for Long-Lived Nuclides

Tadashi Inoue, Masahiro Sakata, Hajime Miyashiro, Tetsuo Matsumura, Akihiro Sasahara, Nobuya Yoshiki

Nuclear Technology / Volume 93 / Number 2 / February 1991 / Pages 206-220

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT91-A34506

Severe Accident Zircaloy Oxidation/Hydrogen Generation Behavior Noted from In-Pile Test Data

August W. Cronenberg

Nuclear Technology / Volume 93 / Number 2 / February 1991 / Pages 221-239

Technical Paper / Material/Nuclear Safety / dx.doi.org/10.13182/NT91-A34507

RELAP5 Simulation of Advanced Test Reactor Scaled LOCA Experiments 7, 8, 12, and 14

Steven T. Polkinghorne, Thomas K. Larson, Brent J. Buescher

Nuclear Technology / Volume 93 / Number 2 / February 1991 / Pages 240-251

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT91-A34508

Development of a Computer Code to Simulate Aerosol Behavior in a Vented Containment

A. K. Ahluwalia, A. M. C. Chan

Nuclear Technology / Volume 93 / Number 2 / February 1991 / Pages 252-259

Technical Note / Nuclear Reactor Safety / dx.doi.org/10.13182/NT91-A34509

 

Home|Contact Us|Invoice Payment|Nuclear Links

Privacy Policy|Terms of Use