Depletion calculation of subcritical system with consideration of spontaneous fission reaction. Issue 4 (3rd April 2022)

• Record Type: Journal Article
• Authors: Riyana, Eka Sapta; Okumura, Keisuke; Sakamoto, Masahiro; Matsumura, Taichi; Terashima, Kenichi
• Is Part Of: Journal of nuclear science and technology. Volume 59:Issue 4(2022)
• Page Start: 424
• Page End: 430
• Publication Date: 2022-04-03
• Subjects: Subcritical system -- depletion calculation -- burnup -- spontaneous fission -- Monte Carlo calculation -- fission product -- fuel debris canister -- activity ratio -- criticality; Nuclear engineering -- Periodicals; Nuclear physics -- Periodicals; Nuclear energy -- Periodicals; 621.4805
• DOI: 10.1080/00223131.2021.1974970
• Languages: English
• ISSNs: 0022-3131

Abstract

ABSTRACT: Modification of the Monte Carlo depletion calculation code OpenMC was performed to enable the depletion calculation of the subcritical neutron multiplying system. With the modified code, it became possible to evaluate the quantity of short half-life fission products from spontaneous and induced fissions in the subcritical system. As a preliminary study, it was applied to the fuel debris storage canister filled with nuclear materials and spontaneous fission nuclides. It was confirmed that the code could successfully provide a quantity of short half-life fission products (FPs) over time and provide the relationship between the activity ratio of 88 Kr to 135 Xe and effective neutron multiplication factor of the canister.