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Home / Publications / Journals / Nuclear Technology / Volume 117 / Number 2

Volume 117

Number 2

A Pressurized Water Reactor Design for Plutonium Incineration: Fuel Cycle Options

Alex Galperin, Gilad Raizes

Nuclear Technology / Volume 117 / Number 2 / February 1997 / Pages 125-132

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT97-A35319

Parallel and Serial Applications of the RETRAN-03 Power Plant Simulation Code Using Domain Decomposition and Krylov Subspace Methods

Thomas J. Downar, Jen-Ying Wu, John Steill, Raghunandan Janardhan

Nuclear Technology / Volume 117 / Number 2 / February 1997 / Pages 133-150

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT97-A35320

Mechanical Efficiency of the Energy Release During a Steam Explosion

R. Krieg

Nuclear Technology / Volume 117 / Number 2 / February 1997 / Pages 151-157

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT97-A35321

Material Distribution in Light Water Reactor-Type Bundles Tested Under Severe Accident Conditions

Volker Noack, Siegfried J. L. Hagen, Peter Hofmann, Gerhard Schanz, Leo K. Sepold

Nuclear Technology / Volume 117 / Number 2 / February 1997 / Pages 158-170

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT97-A35322

Transuranium Fuel Assembly for Transmutation in a Pressurized Water Reactor

Masaaki Mori, Mitsuru Kawamura, Akio Yamamoto

Nuclear Technology / Volume 117 / Number 2 / February 1997 / Pages 171-183

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT97-A35323

Boiling Water Reactor Benchmark Calculations

Farzad Rahnema, Dan Ilas, Shivakumar Sitaraman

Nuclear Technology / Volume 117 / Number 2 / February 1997 / Pages 184-194

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT97-A35324

Melting Tests for Recycling Slightly Radioactive Metallic Wastes Arising from Decommissioning

Hisashi Nakamura, Kazuo Fujiki

Nuclear Technology / Volume 117 / Number 2 / February 1997 / Pages 195-205

Technical Paper / Enrichment and Reprocessing System / dx.doi.org/10.13182/NT97-A35325

Evaluation of Shielding Analysis Methods in Spent-Fuel Cask Environments

Bryan L. Broadhead, Jabo S. Tang, Robert L. Childs, Cecil V. Parks, Hiroaki Taniuchi

Nuclear Technology / Volume 117 / Number 2 / February 1997 / Pages 206-222

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT97-A35326

Radionuclide Transport in Fractured Porous Media—Analytical Solutions for a System of Parallel Fractures with a Flux-Type Boundary Condition

Chu-Tien Chen, Shih-Hai Li

Nuclear Technology / Volume 117 / Number 2 / February 1997 / Pages 223-233

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT97-A35327

Evaluation of Subcooled Critical Heat Flux Correlations Using the PU-BTPFL CHF Database for Vertical Upflow of Water in a Uniformly Heated Round Tube

David D. Hall, Issam Mudawar

Nuclear Technology / Volume 117 / Number 2 / February 1997 / Pages 234-247

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT97-A35328

Criticality Safety Assessment of a TRIGA Reactor Spent-Fuel Pool Under Accident Conditions

Bogdan Glumac, Matjaž Ravnik, Marjan Logar

Nuclear Technology / Volume 117 / Number 2 / February 1997 / Pages 248-254

Technical Paper / Nuclear Criticality Safety / dx.doi.org/10.13182/NT97-A35329

Virtual Radiation Fields—A Virtual Environment Tool for Radiological Analysis and Simulation

Travis W. Knight, G. Ronald Dalton, James S. Tulenko

Nuclear Technology / Volume 117 / Number 2 / February 1997 / Pages 255-266

Technical Paper / Radiation Protection / dx.doi.org/10.13182/NT97-A35330

 

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