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Volume 65

Number 3

Table of Contents
Authors(Tohru Mitsutake, Shigeaki Tsunoyama, Shigeru Kanemoto, Hideaki Namba, Shirley A. Sandoz, Shigeaki Tsunoyama, Tohru Mitsutake, Shigeo Ebata, Shirley A. Sandoz, Wan-Li Zhong, J. Weisman, Susumu Ninomiya, Fumio Ohtsuka, Hiromichi Nei, Osamu Takikawa, Mituo Harata, Robert A. Fjeld, Thomas J. Overcamp, Ken Amano, Kotaro Inoue, C. D. Andriesse, R. H. J. Tanke, Robert P. Schuman, Berthold-Günter Brodda, Erich Richard Merz, Takashi Honda, Akira Minato, Katsumi Ohsumi, Hideo Matsubayashi, Shi-chune Yao, M. J. Loftus, L. E. Hochreiter, Yassin A. Hassan, James G. Rice, Jong H. Kim, Charles Hantouche)
Neutron Radiography, Proceedings of the First World Conference, San Diego, California, December 7–10, 1981(Raymond L. Murray)
Irradiation Technology(K. Linga Murty)

Core Stability Test Analysis Using the Autoregressive Model

Tohru Mitsutake, Shigeaki Tsunoyama, Shigeru Kanemoto, Hideaki Namba, Shirley A. Sandoz

Nuclear Technology / Volume 65 / Number 3 / June 1984 / Pages 365-373

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT84-A33391

Reactor Core Stability Analysis for a Boiling Water Reactor by a Transient Model

Shigeaki Tsunoyama, Tohru Mitsutake, Shigeo Ebata, Shirley A. Sandoz

Nuclear Technology / Volume 65 / Number 3 / June 1984 / Pages 374-382

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT84-A33392

Automated Control Rod Programming in Boiling Water Reactor Cores

Wan-Li Zhong, J. Weisman

Nuclear Technology / Volume 65 / Number 3 / June 1984 / Pages 383-394

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT84-A33393

Development of a Sodium Vapor Pressure Meter Using Beta-Alumina Ceramics

Susumu Ninomiya, Fumio Ohtsuka, Hiromichi Nei, Osamu Takikawa, Mituo Harata

Nuclear Technology / Volume 65 / Number 3 / June 1984 / Pages 395-401

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT84-A33394

Electrically Enhanced Deposition of a Confined Aerosol in the Presence of Ionizing Radiation

Robert A. FJeld, Thomas J. Overcamp

Nuclear Technology / Volume 65 / Number 3 / June 1984 / Pages 402-408

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT84-A33395

Analysis of Coolant Pressure Fluctuation and Induced Vibration of Liquid-Metal Fast Breeder Reactor Fuel Pins

Ken Amano, Kotaro Inoue

Nuclear Technology / Volume 65 / Number 3 / June 1984 / Pages 409-414

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT84-A33396

Dominant Factors in the Release of Fission Products from Overheated Urania

C. D. Andriesse, R. H. J. Tanke

Nuclear Technology / Volume 65 / Number 3 / June 1984 / Pages 415-421

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT84-A33397

Leach Testing of Idaho National Engineering Laboratory Waste Forms in a Gamma Field

Robert P. Schuman

Nuclear Technology / Volume 65 / Number 3 / June 1984 / Pages 422-431

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT84-A33398

The Leaching Behavior of Zircaloy Cladding and Its Impact on the Conditioning of Waste for Final Disposal

Berthold-Günter Brodda, Erich Richard Merz

Nuclear Technology / Volume 65 / Number 3 / June 1984 / Pages 432-437

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT84-A33399

Radioactive Contamination of Carbon Steel in a Boiling Water Reactor

Takashi Honda, Akira Minato, Katsumi Ohsumi, Hideo Matsubayashi

Nuclear Technology / Volume 65 / Number 3 / June 1984 / Pages 438-443

Technical Paper / Material / dx.doi.org/10.13182/NT84-A33400

Hydraulics of Blocked Rod Bundles

Shi-Chune Yao, M. J. Loftus, L. E. Hochreiter

Nuclear Technology / Volume 65 / Number 3 / June 1984 / Pages 444-453

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT84-A33401

An Improved Multidimensional Finite Difference Scheme for Predicting Stratified Horizontal Pipe Flow

Yassin A. Hassan, James G. Rice, Jong H. Kim

Nuclear Technology / Volume 65 / Number 3 / June 1984 / Pages 454-461

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT84-A33402

Comparative Study of Measurements by Means of Gamma Thermometer Strings with Fission Chamber Measurements

Charles Hantouche

Nuclear Technology / Volume 65 / Number 3 / June 1984 / Pages 462-466

Technical Note / Fission Reactor / dx.doi.org/10.13182/NT84-A33403

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