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Volume 97

Number 3

Generation of a Library for Reactor Calculations and Some Applications in Core and Safety Parameter Studies of the 3-MW Triga Mark-II Research Reactor

S. I. Bhuiyan, Anisur Rashid Khan, M. M. Sarker, M. Rahman, Z. Gulshan Ara, M. Musa, M. A. Mannan, I. Mele

Nuclear Technology / Volume 97 / Number 3 / March 1992 / Pages 253-263

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT92-A34633

An Axially Multilayered Low Void Worth Liquid-Metal Fast Breeder Reactor Core Concept

Takanobu Kamei, Mitsuaki Yamaoka

Nuclear Technology / Volume 97 / Number 3 / March 1992 / Pages 264-271

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT92-A34634

Nuclear Power Plant Status Diagnostics Using an Artificial Neural Network

Eric B. Bartlett, Robert E. Uhrig

Nuclear Technology / Volume 97 / Number 3 / March 1992 / Pages 272-281

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT92-A34635

Thermal-Hydraulic Analysis of a Hypothetical Complete Failure of One Shroud Access Hole in a Boiling Water Reactor

Lih-Yih Liao

Nuclear Technology / Volume 97 / Number 3 / March 1992 / Pages 282-293

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT92-A34636

Depressurization Accidents in a Medium-Sized High-Temperature Gas Reactor: Break Size Parametric Study

Shlomo Ron, Judah Tzoref, Doron Gal

Nuclear Technology / Volume 97 / Number 3 / March 1992 / Pages 294-302

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT92-A34637

Chemotoxicity of Nuclear Waste Repositories

Bernd Buchheim, Lars Persson

Nuclear Technology / Volume 97 / Number 3 / March 1992 / Pages 303-315

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT92-A34638

Zircaloy Cladding Rupture During Repository Storage

Lakshman Santanam, Suresh Raghavan, Bryan A. Chin

Nuclear Technology / Volume 97 / Number 3 / March 1992 / Pages 316-322

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT92-A34639

Modeling for Migration of a Redox-Sensitive Radionuclide in Engineered Barriers

Joonhong Ahn, Shinichi Nakayama

Nuclear Technology / Volume 97 / Number 3 / March 1992 / Pages 323-335

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT92-A34640

Dynamic Strain-Aging Effect on Fracture Toughness of Vessel Steels

Sung Sik Kang, In Sup Kim

Nuclear Technology / Volume 97 / Number 3 / March 1992 / Pages 336-343

Technical Paper / Material / dx.doi.org/10.13182/NT92-A34641

Three-Dimensional Thermal Aspects of Aluminum Fuel Elements

Robert P. Wadkins, Richard G. Ambrosek

Nuclear Technology / Volume 97 / Number 3 / March 1992 / Pages 344-351

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT92-A34642

Development of an Efficient Three-Dimensional Reactor Core Model for Simulator Applications

Mankit Ray Yeung, Guo Bing Jiang

Nuclear Technology / Volume 97 / Number 3 / March 1992 / Pages 352-361

Technical Paper / Reactor Operation / dx.doi.org/10.13182/NT92-A34643

Life Testing of a Low-Voltage Air Circuit Breaker to Assess Age-Related Degradation

Mano Subudhi

Nuclear Technology / Volume 97 / Number 3 / March 1992 / Pages 362-370

Technical Paper / Reactor Operation / dx.doi.org/10.13182/NT92-A34644

 

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