2018 Annual Meeting

Presentation information

Oral presentation

III. Fission Energy Engineering » 301-1 Reactor Physics, Utilization of Nuclear Data, Criticality Safety

[2F06-09] Criticality Safety

Tue. Mar 27, 2018 10:50 AM - 11:55 AM Room F (U2-211 -U2 Building)

Chair: Yasushi Nauchi (CRIEPI)

10:50 AM - 11:05 AM

[2F06] Impact of the uncertainty of the PIE analysis on the criticality analysis

*Kenichi Tada1, Kenya Suyama1 (1. JAEA)

Keywords:SWAT4.0, MVP, ORIGEN2, BWR, post irradiation examination, 2F2DN23, Fuel Debris, Criticality analysis

To investigate the appricability of the burnup calculation code SWAT4.0, we calculated the post irradiation examination which is 8x8 BWR fuel assembly and loaded in Fukushima Daini Nuclear Power Plant unit 2. In this study, we investigate the impact of the difference of the number density of nuclide on the criticality analysis for the fuel debris. The calculation was carried out by the infinite pin-cell geometry and calculation results indicates that the impact of the difference of the number density of nuclide on the k-effective is less than 3\%dk/k. Since we adopt the upper subcriticality limit of 0.95 in usual criticality safety evaluation, this result indicates that SWAT4.0 has adequate prediction accuracy of the isotopic composition to be adopted in the burnup credit analysis of the fuel debris from the Fukushima Daiichi Nuclear Power Plant.