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Volume 109

Number 3

Design Study of Lead- and Lead-Bismuth-Cooled Small Long-Life Nuclear Power Reactors Using Metallic and Nitride Fuel

Hiroshi Sekimoto, Zaki Su’ud

Nuclear Technology / Volume 109 / Number 3 / March 1995 / Pages 307-313

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT109-307

Design of Neutron Beams for Neutron Capture Therapy Using a 300-kW Slab TRIGA Reactor

Hungyuan B. Liu

Nuclear Technology / Volume 109 / Number 3 / March 1995 / Pages 314-326

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT95-A35080

Simulation of the IAEA’s Fourth Standard Problem Exercise Small-Break Loss-of-Coolant Accident Using RELAP5/MOD3.1

Peter P. Cebull, Yassin A. Hassan

Nuclear Technology / Volume 109 / Number 3 / March 1995 / Pages 327-337

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT95-A35081

Passive Safety Injection Experiments with a Large-Scale Pressurized Water Reactor Simulator

Taisuke Yonomoto, Yutaka Kukita, Yoshinari Anoda, Hideaki Asaka

Nuclear Technology / Volume 109 / Number 3 / March 1995 / Pages 338-345

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT95-A35082

Implementation of a New Model for Gravitational Collision Cross Sections in Nuclear Aerosol Codes

Robert L. Buckley, Sudarshan K. Loyalka

Nuclear Technology / Volume 109 / Number 3 / March 1995 / Pages 346-356

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT95-A35083

Nuclear Analysis for the Boraflex Used in a Typical Spent-Fuel Storage Assembly

Insoo Jun, Myung Jae Song

Nuclear Technology / Volume 109 / Number 3 / March 1995 / Pages 357-365

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT95-A35084

Investigation of Silver-Impregnated Alumina for Removal of Radioactive Methyl Iodide

Kiyomi Funabashi, Tetsuo Fukasawa, Makoto Kikuchi

Nuclear Technology / Volume 109 / Number 3 / March 1995 / Pages 366-372

Technical Paper / Enrichment and Reprocessing System / dx.doi.org/10.13182/NT95-A35085

Remodeling of the Oxidant Species During Radiolysis of High-Temperature Water in a Pressurized Water Reactor

Hilbert Christensen

Nuclear Technology / Volume 109 / Number 3 / March 1995 / Pages 373-382

Technical Paper / Material / dx.doi.org/10.13182/NT95-A35086

Calculation and Benchmarking of an Azimuthal Pressure Vessel Neutron Fluence Distribution Using the Boxer Code and Scraping Experiments

Frank Holzgrewe, Ferenc Hegedues, Jean M. Paratte

Nuclear Technology / Volume 109 / Number 3 / March 1995 / Pages 383-397

Technical Paper / Material / dx.doi.org/10.13182/NT95-A35087

Investigation of Scale-Up Capability of RELAP5/MOD3 and Scaling Distortion in the IIST Facility Via Natural Circulation Experiments

Yuh-Ming Ferng, Bau-Shei Pei, Tuan-Ji Ding

Nuclear Technology / Volume 109 / Number 3 / March 1995 / Pages 398-411

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT95-A35088

Operational Control of Boiling Water Reactor Stability

Christofer M. Mowry, Israel Nir

Nuclear Technology / Volume 109 / Number 3 / March 1995 / Pages 412-428

Technical Paper / Reactor Control / dx.doi.org/10.13182/NT95-A35089

Assessment of Costs and Benefits Associated with Resolution of Generic Safety Issue 143—Availability of Heating, Ventilation, and Air Conditioning and Chilled Water Systems

Philip M. Daling, Jay E. Marler, Truong V. Vo, Hanh K. Phan, John R. Friley

Nuclear Technology / Volume 109 / Number 3 / March 1995 / Pages 429-436

Technical Note / Nuclear Reactor Safety / dx.doi.org/10.13182/NT95-A35090

 

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