The Development of CYGRO-F for Fuel Rod Behavior Analysis-Reference-Cited by-同舟云学术

The Development of CYGRO-F for Fuel Rod Behavior Analysis

Published:1972-10 Issue:1 Volume:16 Page:156-170
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Harbourne B. L.¹,Beck M. S.¹,Foster J. P.¹,Biancheria A.¹

Affiliation:

1. Westinghouse Electric Corporation, Advanced Reactor Division, Madison, Pennsylvania 15663

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/NT72-A31183

Reference20 articles.

1. V. Z. JANKUS and R. W. WEEKS, “LIFE-I, A Fortran-IV Computer Code for the Prediction of Fast Reactor Fuel Element Behavior,” ANL-7736, Argonne National Laboratory (1970).

2. R. A. LASKIEWICZ, G. R. MELDS, S. K. EVANS, and P. E. BOHABOY, “Thermal Conductivity of Uranium-Plutonium Oxide,” GEAP-13733, General Electric Company (1971).

3. R. L. GIBBY, “The Effect of Stoichiometry of the Thermal Diffusivity and Conductivity of (U.75,Pu.25)O2,” BNWL-927, Pacific Northwest Laboratories (1969).

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