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Report No.

Integral test of JENDL-3.3 based on shielding benchmarks

Japanese Nuclear Data Comitteee, Shielding Integral Test Working Group (FY2006-2010)

Integral tests of neutron and photon production data in cross-section libraries based on the Japanese Evaluated Nuclear Data Library, Version 3.3 (JENDL-3.3) have been performed by using shielding benchmarks. An evaluation scheme for shielding benchmark analysis established in the Japanese Nuclear Data Committee (JNDC) was applied to the integral test for 28 materials in 22 medium-heavy nuclei and the compounds such as Lithium, Oxygen, LiF, TEFLON:(CF$$_{2}$$)n, Sodium, Aluminum, Li$$_{2}$$AlO$$_{3}$$, LiAlO$$_{2}$$, Silicon, SiC, Titanium, Li$$_{2}$$TiO$$_{3}$$, Vanadium, Chromium, Manganese, Iron, Cobalt, Nickel, SS304, Copper, Arsenic, Selenium, Zirconium, Li$$_{2}$$ZrO$$_{3}$$, Niobium, Molybdenum, Tungsten and Mercury. Calculations were made by using a continuous-energy Monte Carlo code MCNP and multi-group discrete ordinates codes ANISN, DORT and TORT. Calculations with JENDL-3.2, ENDF/B-VI, EFF-2, FENDL-1 and FENDL-2 were also made for comparison. The results of JENDL-3.3 were generally satisfactory and the cross-section libraries generated with JENDL-3.3 were validated to shielding applications for fission and fusion reactors.



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