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Report No.

Calculation of criticality condition data for single-unit homogeneous uranium materials in six chemical forms

Okuno, Hiroshi  ; Yoshiyama, Hiroshi; Miyoshi, Yoshinori

Single-unit criticality condition data were calculated for homogeneous uranium materials in six chemical forms for revision of the Data Collection section that was attached as the appendix to the Nuclear Criticality Safety Handbook. The calculated criticality condition data were the estimated critical and the estimated lower-limit critical masses and volumes of spheres, diameters of infinitely-long cylinders and infinite slab thicknesses for uranium materials in six chemical forms encountered in criticality safety evaluation of nuclear fuel cycle facilities. The calculation was made with a continuous-energy Monte Carlo criticality calculation code MVP and the Japanese Evaluated Nuclear Data Library JENDL-3.2. The values and precision of the present calculations were discussed in comparison with the literature and the previous results.



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Category:Nuclear Science & Technology



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