Whole core transport calculation for PWR analysis using leakage dependent SPH
- 1. Mitsubishi Heavy Industries, Ltd., Kobe, Hyogo (Japan)
- 2. Osaka Univ., Suita, Osaka (Japan)
Description
To accurately calculate power distribution and other neutronic characteristics of PWR cores, the whole core heterogeneous transport calculation which explicitly treats individual cells will be required. The whole core calculation has been performed by using pin-by-pin SN nodal method with cell homogenized cross sections corrected by SPH factors. The cell homogenized cross sections are generated by cell heterogeneous assembly calculations at non-reflective boundary condition in order to take into account the spectrum interference effect of adjacent assemblies and reflectors. When non-reflective boundary condition is applied to the assembly calculation, the conventional SPH method does not work because the neutron leakage of heterogeneous system is not consistent with that of homogeneous system when the same albedo boundary condition is applied to both heterogeneous and homogeneous system. The new SPH method has been developed to have a consistency of the neutron leakage between cell-heterogeneous and homogeneous system and the applicability of the new SPH method is verified for the mini core calculation including UO2 and MOX assemblies. (author)
Additional details
Publishing Information
- Publisher
- Atomic Energy Society of Japan
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- The 16th pacific basin nuclear conference. Pacific partnership toward a sustainable nuclear future
- Imprint Pagination
- [2022 p.]
- Journal Page Range
- [6 p.]
Conference
- Title
- 16. pacific basin nuclear conference
- Acronym
- 16PBNC
- Dates
- 13-18 Oct 2008
- Place
- Aomori (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 40103114
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALBEDO; BOUNDARY CONDITIONS; FUEL ASSEMBLIES; HETEROGENEOUS EFFECTS; HOMOGENIZATION METHODS; MIXED OXIDE FUELS; NEUTRON LEAKAGE; NEUTRON TRANSPORT; POWER DISTRIBUTION; PWR TYPE REACTORS; REACTOR CELLS; REACTOR CORES; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; CALCULATION METHODS; CHALCOGENIDES; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; MATERIALS; NEUTRAL-PARTICLE TRANSPORT; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; POWER REACTORS; RADIATION TRANSPORT; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SOLID FUELS; THERMAL REACTORS; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- This CD-ROM can be used for WINDOWS 9x/NT/2000/ME/XP/VISTA, MACINTOSH; Acrobat Reader is included; Data in PDF format, Folder Name FullPaper, Paper ID P16P1134.pdf; 6 refs., 4 figs., 1 tab.