Evaluation of critical experimental core configurations to simulate non-uniform fuel debris

Gunji, Satoshi; Araki, Shohei; Suyama, Kenya; Izawa, Kazuhiko

Proceedings of International Conference on Physics of Reactors 2022 (PHYSOR 2022) (Internet), 10 Pages, 2022/05

The fuel debris is expected to have not only heterogeneous but also non-uniform compositions. Therefore, the calculation method used in their criticality management is required to be validated experimentally. In this study, several core configurations of a new critical assembly "STACY" of JAEA with non-uniform arrangements of uranium oxide fuel rods, concrete rods and stainless steel rods, which are components of the fuel debris, were studied. In each case, the median value of 100 sample patterns was larger than the mean effective multiplication factor. It was also confirmed that there are differences in the effective multiplication factor of more than one dollar by the pattern changing, and that the neutron spectra can change significantly by changing the local neutron moderation conditions. In particular, the effective multiplication factor became smaller when over-moderated regions with large water-to-fuel ratios were formed in the core configurations due to increases in thermal neutron absorption. Such criticality experiments with non-uniform arrangements of multiple compositions will be useful to evaluate the validity of the calculation code.

Progress of criticality control study on fuel debris by Japan Atomic Energy Agency to support Secretariat of Nuclear Regulation Authority

Tonoike, Kotaro; Watanabe, Tomoaki; Gunji, Satoshi; Yamane, Yuichi; Nagaya, Yasunobu; Umeda, Miki; Izawa, Kazuhiko; Ogawa, Kazuhiko

Proceedings of 11th International Conference on Nuclear Criticality Safety (ICNC 2019) (Internet), 9 Pages, 2019/09

Criticality control of the fuel debris in the Fukushima Daiichi Nuclear Power Station would be a risk-informed control to mitigate consequences of criticality events, instead of a deterministic control to prevent such events. The Nuclear Regulation Authority of Japan has administrated a research and development program to tackle this challenge since 2014. The Nuclear Safety Research Center of Japan Atomic Energy Agency, commissioned by the authority, is conducting activities such as computations of criticality characteristics of the fuel debris, development of a criticality analysis code, preparation of criticality experiments, and development of a criticality risk analysis method.

Study of safety aspects for pyrochemical reprocessing systems

Kakehi, Isao; Nakabayashi, Hiroki

JNC TN9400 2000-051, 237 Pages, 2000/04

JNC-TN9400-2000-051.pdf:8.14MB

In this study, we have proposed the concept of safety systems (solutions of safety problems) in pyrochemical reprocessing systems (lt consists of pyrochemical reprocessing methods and the injection casting process for the metal fuel fabrication, or vibro-packing process for the oxide fuel fabrication.) which has different concept from the existing PUREX reprocessing method and pellet fuel fabrication process. And we performed its safety evaluations. FoIlowing the present Japanese safety regulations for reprocessing facilities, we pointed out functions, design requirements and equipments relating to its safety systems and picked up subjects. For the survey of safety evaluations, we first selected anticipated events and accident events, and second by evaluated 6the correspondence of the limitation of the public exposure to the accidents above, by using two parameters, the safety design parameter (the filter performance to confine radioactive matelials) and the leak inventory of radioactivities, and last by picked up its problems. ln addition to the above evaluations we performed basic criticality analyses for its systems to utilize these results for the design and evaluation of the criticality safety management system. Thus this study specified the concept of safety systems for pyrochemical reprocessing processes and then issues in order to establish safety design policies (matters which must consider for the safety design) and guides and to advance more definite safety design.

None

PNC TN1410 97-043, 167 Pages, 1997/11

PNC-TN1410-97-043.pdf:7.22MB

no abstracts in English

Basic criticality characteristics data collection for the fuel debris retrieval

Araki, Shohei; Watanabe, Tomoaki; Gunji, Satoshi; Tonoike, Kotaro

no journal, , 

no abstracts in English