Simplified Evaluation Models for Total Fission Number in a Criticality Accident-Reference-Cited by-同舟云学术

Simplified Evaluation Models for Total Fission Number in a Criticality Accident

Published:1995-01 Issue:1 Volume:109 Page:142-152
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Nomura Yasushi¹,Okuno Hiroshi¹

Affiliation:

1. Japan Atomic Energy Research Institute, Department of Fuel Cycle Safety Research Tokai Research Establishment, Tokaimura, Nakagun, Ibaraki-ken, 319-11, Japan

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT95-A35074

Reference9 articles.

1. W. R. STRATTON and D. R. SMITH, “A Review of Criticality Accidents,” DOE/NCT-04, U.S. Department of Energy (Mar. 1989).

2. P. LECORCHE et al. “A Review of the Experiments Performed to Determine the Radiological Consequences of a Criticality Accident,” Y-CDC-12, Union Carbide Corporation (1973).

3. R. K. MACCARDELL, D. I. HERBORN, and J. E. HOUGHTALING, “Reactivity Accident Test Results and Analyses for the SPERT III E-Core—A Small, Oxide-Fueled, Pressurized-Water Reactor,” IDO-17281, U.S. Atomic Energy Commission (Mar. 1969).

4. D. L. HETRIC, “Dynamics of Nuclear Reactors,” University of Chicago Press, Chicago (1971).

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