A new paradigm for whole core neutron transport without homogenization
Creators
- 1. Northwestern Univ., Dept. of Mechanical Engineering, Evanston, IL 60208 (United States)
- 2. Argonne National Laboratory, 9700 South Cass Avenue, Argonne, IL 60439 (United States)
Description
A new paradigm is introduced which allows the performance of whole core transport calculations without lattice homogenization. Quasi-reflected interface conditions are formulated to partially decouple periodic lattice effects from the pin-cell to pin-cell flux variation in the finite sub-element form of the variational nodal code VARIANT. With fuel-coolant homogenization eliminated, the interface variables that couple pin-cell sized nodes are divided into low-order and high-order spherical harmonic terms. Reflected interface conditions are subsequently applied to the high-order terms to remove them from the system of unknowns. Combined with an integral transport treatment within the node, the new approach dramatically reduces both the formation time and the size of the response matrices and leads to sharply reduced memory and CPU requirements. The method is applied to the two-dimensional C5-G7 problem, an OECD/NEA PWR benchmark containing MOX and UO2 fuel assemblies. Results indicate the new approach results in very little loss of accuracy relative to the corresponding full spherical harmonics expansions while reducing CPU times by well over an order of magnitude. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park (United States)
- ISBN
- 0-89448-059-6
- Imprint Pagination
- 11 p.
Conference
- Title
- Joint International Topical Meeting on Mathematics and Computations and Supercomputing in Nuclear Applications
- Acronym
- M and C + SNA 2007
- Dates
- 15-19 Apr 2007
- Place
- Monterey, CA (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 42109172
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S97: MATHEMATICAL METHODS AND COMPUTING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCURACY; BENCHMARKS; FUEL ASSEMBLIES; FUEL PINS; MIXED OXIDE FUELS; NEA; NEUTRON FLUX; NEUTRON TRANSPORT; NEUTRON TRANSPORT THEORY; NODAL EXPANSION METHOD; PWR TYPE REACTORS; REACTOR CELLS; SPHERICAL HARMONICS; TWO-DIMENSIONAL CALCULATIONS; URANIUM DIOXIDE; VARIATIONAL METHODS
- Descriptors DEC
- ACTINIDE COMPOUNDS; CALCULATION METHODS; CHALCOGENIDES; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; FUELS; FUNCTIONS; INTERNATIONAL ORGANIZATIONS; MATERIALS; NEUTRAL-PARTICLE TRANSPORT; NUCLEAR FUELS; OECD; OXIDES; OXYGEN COMPOUNDS; POWER REACTORS; RADIATION FLUX; RADIATION TRANSPORT; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SOLID FUELS; THERMAL REACTORS; TRANSPORT THEORY; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 15 refs.