Preliminary analysis of randomized configuration patterns in modified STACY core
Creators
- 1. Secretariat of the Nuclear Regulation Authority, Regulatory Standard and Research Department, Tokyo (Japan)
- 2. Japan Atomic Energy Agency, Nuclear Safety Research Center, Fuel Cycle Safety Research Division, Tokai, Ibaraki (Japan)
Description
In collaboration with the Japan Atomic Energy Agency (JAEA), the Nuclear Regulation Authority (NRA) has taken an experimental approach to determining the criticality of pseudo-fuel debris since 2014. In addition, JAEA continues to modify the STAtic experiment Critical facility (STACY) and prepares for critical experiments that simulate pseudo-fuel debris. In a critical experiment plan using the modified STACY, randomized core configuration patterns composed of fuel and structure rods, etc. were proposed Various rod patterns were considered in the critical experiments; however, the experimental patterns should be narrowed down as reasonable. For this reason, to evaluate the impact of rod patterns on the criticality characteristic etc., hundreds of randomized configuration patterns with two types of spacer grid plates (1.27 and 1.50 cm pitches) assembled in the modified STACY core were generated using the Fisher-Yates shuffling algorithm, the criticality characteristics of which were then evaluated using Tools for Sensitivity and Uncertainty Analysis Methodology Implementation in three dimensional systems (TSUNAMI-3D). In addition, pseudo-fuel debris models that consider the volume ratio of pseudo-fuel debris to moderation (Vm/Vf) were built and the sensitivity coefficient-based similarity index (G) between the patterns and pseudo-fuel debris models were then calculated using TSUNAMI-Indices and Parameters (TSUNAMI-IP). As a result, the impact of the rod patterns on reactivities was within 500 pcm. Especially G values in Vm/Vf > 2 exceeded 0.80 for all the patterns with the 1.50 cm-spacer grid plate. The impact of rod patterns to G values in the pseudo-fuel debris models was extremely small. (author)
Files
Additional details
Identifiers
Publishing Information
- Imprint Title
- Proceedings of the 12th international conference on nuclear criticality safety (ICNC2023)
- Imprint Pagination
- 48 p.
- Journal Page Range
- 9 p.
- Report number
- JAEA-Conf--2024-001
Conference
- Title
- 12. international conference on nuclear criticality safety
- Acronym
- ICNC2023
- Dates
- 1-6 Oct 2023
- Place
- Sendai, Miyagi (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 56006633
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONTAINMENT SHELLS; CORIUM; CRITICALITY; DATA COVARIANCES; FISSION PRODUCTS; FUEL RODS; MELTDOWN; REACTOR CORES; REACTOR VESSELS; STACY REACTOR; T CODES
- Descriptors DEC
- ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; COMPUTER CODES; CONTAINERS; CONTAINMENT; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FUEL ELEMENTS; ISOTOPES; MATERIALS; PLUTONIUM REACTORS; RADIOACTIVE MATERIALS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SEVERE ACCIDENTS; ZERO POWER REACTORS
Optional Information
- Notes
- 10 refs., 7 figs., 2 tabs.; Also available as CD-ROM Data in PDF format, Folder Name: S1_-Poster, Paper ID: of5_-0_-101_-0_-0000003.pdf