2016 Fall Meeting

Presentation information

Print

Oral Presentation

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

[1L13-18] Burnup Analysis

Wed. Sep 7, 2016 4:05 PM - 5:40 PM Room L (Kumume City Plaza - Assembly Room 2)

Chair: Go Chiba (Hokkaido Univ.)

5:05 PM - 5:20 PM

[1L17] Analysis of measured isotopic compositions of fuels irradiated in light water reactors by CASMO5

(2)MOX fuel

*tomohiro sakai1, Toru Yamamoto1, Daiki Iwahashi1 (1.S/NRA/R)

Keywords:JENDL-4.0, CASMO5, PWR, BWR, MOX fuel, Burnup calculation, Measured isotopic composition

As a part of uncertainty evaluation of the assembly nuclear calculation code od CASMO5 coupled with a JENDL-4.0 base library, burnup calculations on PWR and BWR fuels irradiated in the foreign light water reactors were performed and the calculated isotopic composition were compared with those measured to evaluate the uncertainty in the calculated isotopic compositions.