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Volume 71

Number 3

Table of Contents
Authors(Farhang Sefidvash, Dawk Hwan Ahn, Samuel H. Levine, Takanobu Kamei, Mitsuaki Yamaoka, Yasuyuki Moriki, Masao Suzuki, Kazuo Arie, Martin Victor Polley, Shinji Tokumasu, Michihiro Ozawa, Hiroshi Hiranuma, Michiro Yokomi, Junichi Tanji, Shunsuke Utena, Bernhard Kienzler, Rainer H. Köster, Jitze Bergsma, Robert B. Helmholdt, Roel J. Heijboer, T. C. Wiencek, R. F. Domagala, H. R. Thresh, Yoshiko Harima, Kohtaro Ueki, Otohiko Aizawa, K. Tasaka, Y. Koizumi, Y. Kukita, H. Nakamura, Y. Anoda, M. Iriko, H. Kumamaru, M. Suzuki, James Y. Yaung, D. Okrent, A. R. Wazzan)
Technical Reviewers

A Fluidized-Bed Nuclear Reactor Concept

Farhang Sefidvash

Nuclear Technology / Volume 71 / Number 3 / December 1985 / Pages 527-534

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A33675

Automatic Optimized Reload and Depletion Method for a Pressurized Water Reactor

Dawk Hwan Ahn, Samuel H. Levine

Nuclear Technology / Volume 71 / Number 3 / December 1985 / Pages 535-547

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A33676

An Axially and Radially Two-Zoned Large Liquid-Metal Fast Breeder Reactor Core Concept

Takanobu Kamei, Mitsuaki Yamaoka, Yasuyuki Moriki, Masao Suzuki, Kazuo Arie

Nuclear Technology / Volume 71 / Number 3 / December 1985 / Pages 548-556

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A33677

A Correlation Between Operation of Primary Coolants at Low pH_T with Steam Generator Channel Head Dose Rates in Westinghouse Pressurized Water Reactors

Martin Victor Polley

Nuclear Technology / Volume 71 / Number 3 / December 1985 / Pages 557-567

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A33678

A Mathematical Method for Boiling Water Reactor Control Rod Programming

Shinji Tokumasu, Michihiro Ozawa, Hiroshi Hiranuma, Michiro Yokomi

Nuclear Technology / Volume 71 / Number 3 / December 1985 / Pages 568-579

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A33679

A Symptom-Oriented Method for Posttrip Operation Guidance in Boiling Water Reactors

Junichi Tanji, Shunsuke Utena

Nuclear Technology / Volume 71 / Number 3 / December 1985 / Pages 580-589

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT85-A33680

Experimental and Theoretical Investigations of Corrosion Mechanisms in Cemented Waste Forms

Bernhard Kienzler, Rainer H. Köster

Nuclear Technology / Volume 71 / Number 3 / December 1985 / Pages 590-596

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT85-A33681

Radiation Dose Deposition and Colloid Formation in a Rock Salt Waste Repository

Jitze Bergsma, Robert B. Helmholdt, Roel J. Heijboer

Nuclear Technology / Volume 71 / Number 3 / December 1985 / Pages 597-607

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT85-A33682

Thermal Compatibility Studies of Unirradiated Uranium Silicide Dispersed in Aluminum

T. C. Wiencek, R. F. Domagala, H. R. Thresh

Nuclear Technology / Volume 71 / Number 3 / December 1985 / Pages 608-616

Technical Paper / Material / dx.doi.org/10.13182/NT85-A33683

Three-Dimensional Neutron Streaming Analysis Using the Monte Carlo Coupling Technique in a Medical Irradiation Room of the Musashi Reactor: Comparison with Experiments

Yoshiko Harima, Kohtaro Ueki, Otohiko Aizawa

Nuclear Technology / Volume 71 / Number 3 / December 1985 / Pages 617-627

Technical Paper / Radiation Biology and Environment / dx.doi.org/10.13182/NT85-A33684

Analyses of ROSA-III Break Area Spectrum Experiments on a Boiling Water Reactor Loss-of-Coolant Accident

K. Tasaka, Y. Koizumi, Y. Kukita, H. Nakamura, Y. Anoda, M. Iriko, H. Kumamaru, M. Suzuki

Nuclear Technology / Volume 71 / Number 3 / December 1985 / Pages 628-643

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33685

A Simple Computer Model of Pellet/Cladding Interaction Including Stress Corrosion Cracking

James Y. Yaung, D. Okrent, A. R. Wazzan

Nuclear Technology / Volume 71 / Number 3 / December 1985 / Pages 644-650

Technical Note / Nuclear Fuel / dx.doi.org/10.13182/NT85-A33686

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