Published 2005 | Version v1
Miscellaneous

3-D extension C5G7 MOX benchmark calculation using threedant code

  • 1. Hanyang Univ., Dept. of Nuclear Engineering, Seoul (Korea, Republic of)
  • 2. OECD NEA, Le Seine Saint-Germain, 92 - Issy les Moulineaux (France)

Description

It pursued the benchmark on deterministic 3-D MOX fuel assembly transport calculations without spatial homogenization (C5G7 MOX Benchmark Extension). The goal of this benchmark is to provide a more through test results for the abilities of current available 3-D methods to handle the spatial heterogeneities of reactor core. The benchmark requires solutions in the form of normalized pin powers as well as the eigenvalue for each of the control rod configurations; without rod, with A rods, and with B rods. In this work, the DANTSYS code package was applied to analyze the 3-D Extension C5G7 MOX Benchmark problems. The THREEDANT code within the DANTSYS code package, which solves the 3-D transport equation in x-y-z, and r-z-theta geometries, was employed to perform the benchmark calculations. To analyze the benchmark with the THREEDANT code, proper spatial and angular approximations were made. Several calculations were performed to investigate the effects of the different spatial approximations on the accuracy. The results from these sensitivity studies were analyzed and discussed. From the results, it is found that the 4*4 grid per pin cell is sufficiently refined so that very little benefit is obtained by increasing the mesh size. (authors)

Availability note (English)

Available from SFEN, 5 rue des Morillons, 75015 - Paris (France)

Additional details

Publishing Information

Publisher
SFEN
Imprint Place
Paris (France)
Imprint Pagination
12 p.
Report number
INIS-FR--09-1013

Conference

Title
international topical meeting on mathematics and computation, supercomputing, reactor physics and nuclear and biological applications
Acronym
M and C 2005
Dates
12-15 Sep 2005
Place
Avignon (France)

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
40084869
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
BENCHMARKS; D CODES; FUEL ASSEMBLIES; MESH GENERATION; MIXED OXIDE FUELS; NEUTRON TRANSPORT THEORY; T CODES; THREE-DIMENSIONAL CALCULATIONS; VALIDATION
Descriptors DEC
COMPUTER CODES; ENERGY SOURCES; FUELS; MATERIALS; NUCLEAR FUELS; REACTOR MATERIALS; SOLID FUELS; TESTING; TRANSPORT THEORY

Optional Information

Notes
7 refs.