BWR (boiling water reactor) lattice analysis using true geometry as compared to CPM-2

Conference · Wed Nov 01 00:00:00 EST 1989 · Transactions of the American Nuclear Society; (United States)

OSTI ID:5376864

Knott, D; Baratta, A ^[1]

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1. Pennsylvania State Univ., University Park (USA)

Conventional lattice physics codes perform the two-dimensional transport calculation using an approximated geometry, whereby all pin cells are homogenized following the spectral calculations. To better calculate the true flux within the gadolinia cells, the two-dimensional transport calculation is performed in the true geometry of the lattice using KRAM, a two-dimensional characteristics solution of the transport equation. Normal fuel cells are modeled using three regions (cylindrical fuel and clad regions within a square moderator region), while fuel regions containing gad are subdivided into many annular subregions, thereby better approximating the self-shielding effect of the gad. The characteristics method breaks the system being analyzed into regions of constant flux, as in collision probability methods, and it is, therefore, desirable to minimize the size of these regions. To this end, then, each pin cell is further subdivided diagonally into quadrants.

• OSTI ID: 5376864
• Report Number(s): CONF-891103-; CODEN: TANSA; TRN: 91-024511
• Journal Information: Transactions of the American Nuclear Society; (United States), Vol. 60; Conference: Winter meeting of the American Nuclear Society (ANS) and nuclear power and technology exhibit, San Francisco, CA (United States), 26-30 Nov 1989; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
REACTOR PHYSICS
REACTOR LATTICES
GEOMETRY
C CODES
ALGORITHMS
BURNABLE POISONS
COMPARATIVE EVALUATIONS
EIGENVALUES
EPRI
FUEL PINS
GADOLINIUM OXIDES
HOMOGENIZATION METHODS
K CODES
M CODES
NEUTRON FLUX
NEUTRON TRANSPORT
REACTOR CELLS
REACTOR CORES
SELF-SHIELDING
TWO-DIMENSIONAL CALCULATIONS
CHALCOGENIDES
COMPUTER CODES
EVALUATION
FUEL ELEMENTS
GADOLINIUM COMPOUNDS
MATERIALS
MATHEMATICAL LOGIC
MATHEMATICS
NEUTRAL-PARTICLE TRANSPORT
NEUTRON ABSORBERS
NUCLEAR POISONS
OXIDES
OXYGEN COMPOUNDS
PHYSICS
RADIATION FLUX
RADIATION TRANSPORT
RARE EARTH COMPOUNDS
REACTOR COMPONENTS
REACTOR MATERIALS
REACTORS
SHIELDING
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled