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Volume 106

Number 3

A Study of Plateout Fission Product Behavior During a Large-Scale Pipe Rupture Accident in a High-Temperature Gas-Cooled Reactor

Kazuhiro Sawa, Isao Murata, Shusaku Shiozawa, Mikio Matsumoto

Nuclear Technology / Volume 106 / Number 3 / June 1994 / Pages 265-273

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A34957

Modeling of Heat Transfer to Nuclear Steam Supply System Heat Sinks and Application to Severe Accident Sequences

Kune Y. Suh

Nuclear Technology / Volume 106 / Number 3 / June 1994 / Pages 274-291

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A34958

Xenon Stability Analysis Using the Generalized Nyquist Criterion

You-Cho Choi, Goon-Cherl Park, Chang-Hyun Chung

Nuclear Technology / Volume 106 / Number 3 / June 1994 / Pages 292-299

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A34959

A Study on Boiling Water Reactor Regional Stability from the Viewpoint of Higher Harmonics

Yutaka Takeuchi, Yukio Takigawa, Hitoshi Uematsu

Nuclear Technology / Volume 106 / Number 3 / June 1994 / Pages 300-314

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A34960

Use of an Influence Diagram and Fuzzy Probability for Evaluating Accident Management in a Boiling Water Reactor

Donghan Yu, William E. Kastenberg, David Okrent

Nuclear Technology / Volume 106 / Number 3 / June 1994 / Pages 315-325

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A34961

Trace Metal Assay of Uranium Silicide Fuel

M. J. Kulkarni, A. A. Argekar, S. K. Thulasidas, B. A. Dhawale, B. Rajeswari, V. C. Adya, P. J. Purohit, G. Neelam, T. R. Bangia, A. G. Page, M. D. Sastry, R. H. Iyer

Nuclear Technology / Volume 106 / Number 3 / June 1994 / Pages 326-333

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT94-A34962

Numerical Analysis for Microstructure Change of a Light Water Reactor Fuel Pellet at High Burnup

Takanori Kameyama, Tetsuo Matsumura, Motoyasu Kinoshita

Nuclear Technology / Volume 106 / Number 3 / June 1994 / Pages 334-341

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT94-A34963

Internal Flaws in the Silicon Carbide Coating of Fuel Particles for High-Temperature Gas-Cooled Reactors

Kazuo Minato, Hironobu Kikuchi, Kousaku Fukuda, Nobuyuki Suzuki, Hiroshi Tomimoto, Nobu Kitamura, Mitsunobu Kaneko

Nuclear Technology / Volume 106 / Number 3 / June 1994 / Pages 342-349

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT94-A34964

An Evaluation of the Deployment of AIROX-Recycled Fuel in Pressurized Water Reactors

Salim N. Jahshan, Thomas J. McGeehan

Nuclear Technology / Volume 106 / Number 3 / June 1994 / Pages 350-359

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT94-A34965

Transport Phenomena and Occupational Consequences of a Tritium Release

Dong H. Nguyen

Nuclear Technology / Volume 106 / Number 3 / June 1994 / Pages 360-372

Technical Paper / Radiation Protection / dx.doi.org/10.13182/NT94-A34966

Measurement of Neutron Radiation Exposure of Commercial Airline Pilots Using Bubble Detectors

Brent J. Lewis, Richard Kosierb, Tom Cousins, Donald F. Hudson, Georges Guéry

Nuclear Technology / Volume 106 / Number 3 / June 1994 / Pages 373-383

Technical Paper / Radiation Protection / dx.doi.org/10.13182/NT94-A34967

Development of Software for the Microsimulator for the KO-RI Nuclear Power Plant Unit 2

Ho Seok, Hee Cheon No, Sung Jae Cho, Sang Doug Park, Hwang Young Jun, Yong Kwan Lee

Nuclear Technology / Volume 106 / Number 3 / June 1994 / Pages 384-396

Technical Paper / Reactor Operation / dx.doi.org/10.13182/NT94-A34968

Verification of Feedwater System Models of the Kuosheng Plant Analyzer

Shih-Jen Wang, Chun-Sheng Chien, Shih-Hsiin Chang, Suh-Chyn Jeng

Nuclear Technology / Volume 106 / Number 3 / June 1994 / Pages 397-406

Technical Paper / Reactor Control / dx.doi.org/10.13182/NT94-A34969