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Home / Publications / Journals / Nuclear Technology / Volume 73 / Number 3

Volume 73

Number 3

Statistical Analysis of Duplex-Tube Performance in Experimental Breeder Reactor II Superheater SU-712

Kenny C. Gross, B. R. Seidel

Nuclear Technology / Volume 73 / Number 3 / June 1986 / Pages 263-277

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT86-A16070

A Concept of a Small Controlled, Filtered Venting System and an Add-On Decay Heat Removal System to Mitigate the Consequences of Core-Melt Accidents

Sabyasachi Chakraborty, Bruno Covelli, Peter Michael Herttrich

Nuclear Technology / Volume 73 / Number 3 / June 1986 / Pages 278-285

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT86-A16071

Skyshine Radiation from a Pressurized Water Reactor Containment Dome

Wu-Hung Peng

Nuclear Technology / Volume 73 / Number 3 / June 1986 / Pages 286-295

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT86-A16072

Effects of Fuel Enrichment on the Physics Characteristics of Plutonium-Fueled Light Water High Converter Reactors

Rakesh Chawla, Rudolf Seiler, Kurt Gmür

Nuclear Technology / Volume 73 / Number 3 / June 1986 / Pages 296-305

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT86-A16073

Blind-Blind Prediction by RELAP5/MOD1 for a 0.1% Very Small Cold-Leg Break Experiment at ROSA-IV Large-Scale Test Facility

Yasuo Koizumi, Hiroshige Kumamaru, Yutaka Kukita, Masahiro Kawaji, Masahiro Osakabe, Richard R. Schultz,* Mitsugu Tanaka, Kanji Tasaka

Nuclear Technology / Volume 73 / Number 3 / June 1986 / Pages 306-319

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT86-A16074

Uncertainty and Sensitivity Analysis of a Model for Multicomponent Aerosol Dynamics

J. C. Helton,* R. L. Iman, J. D. Johnson,+, C. D. Leigh

Nuclear Technology / Volume 73 / Number 3 / June 1986 / Pages 320-342

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT86-A16075

Feasibility of the Once-Through Thorium Fuel Cycle for CANDU Reactors

Alex Galperin

Nuclear Technology / Volume 73 / Number 3 / June 1986 / Pages 343-349

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT86-A16076

Structural Chemistry of Solid Solutions in the UO2-Gd2O3 System

S. M. Ho, K. C. Radford

Nuclear Technology / Volume 73 / Number 3 / June 1986 / Pages 350-360

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT86-A16077

An Evaluation of the Influence of Fuel Design Parameters and Burnup on Pellet/Cladding Interaction for Boiling Water Reactor Fuel Rod Through In-Core Diameter Measurement

Kazuaki Yanagisawa

Nuclear Technology / Volume 73 / Number 3 / June 1986 / Pages 361-377

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT86-A16078

Effect of Heat Flux on the Concentration Factor in Crevices of Nuclear Steam Generators

Sang Woon Shin, Hee Cheon No

Nuclear Technology / Volume 73 / Number 3 / June 1986 / Pages 378-383

Technical Paper / Material / dx.doi.org/10.13182/NT86-A16079

Small Calciner for Drying and Calcination of SYNROC Slurry

Hisayoshi Mitamura, Takashi Murakami, Tsunetaka Banba, Takayuki Amaya

Nuclear Technology / Volume 73 / Number 3 / June 1986 / Pages 384-388

Technical Note / Radioactive Waste Management / dx.doi.org/10.13182/NT86-A16080

 

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