A transport multicell method for two dimensional lattices of hexagonal cells
Description
The constant increase of stock of Plutonium originated from classical LWR facilities have aroused a renewed interest in undermoderated reactors and, with this, a change on bundle design from the usual light-moderated, X-Y pin-fuel layout to the typical, fast-reactor, hexagonal lattice. To provide a tool for routine, design calculations of pin-fuel assemblies in a ''hexagonal'', beehive-like geometry we have applied a multicell, collision-probability technique. A flat-flux expansion on axially symmetric zones has been used, together with a uniform double P1 expansion for the boundary angular fluxes, to construct an interface-current method for the calculation of two-dimensional hexagonal cells. Collision and escape probabilities are computed in a volume-preserving, cylindrical cell model, while one of three separate PSS models is used for the calculation of the transmission probabilities. When only one zone has been cylinderized then use of the heterogeneous PSS model is equivalent to an exact calculation in the actual two-dimensional cell geometry (without cylinderization). Comparison between the different approximations and a Monte Carlo calculation are presented for a typical undermoderated assembly
Availability note (English)
MF available from INIS under the Report Number.Files
16085792.pdf
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Additional details
Additional titles
- Augmented title (English)
- Undermoderated reactors
Publishing Information
- Imprint Pagination
- 15 p.
- Report number
- CEA-CONF--7862
Conference
- Title
- International meeting on advances in nuclear engineering and computational methods.
- Dates
- 9-11 Apr 1985.
- Place
- Knoxville, TN (USA).
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 16085792
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPARATIVE EVALUATIONS; COMPUTER CALCULATIONS; EPITHERMAL REACTORS; HEXAGONAL CONFIGURATION; MONTE CARLO METHOD; NEUTRON FLUX; NEUTRON TRANSPORT; ONE-GROUP THEORY; REACTOR CELLS; TWO-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- CONFIGURATION; NEUTRAL-PARTICLE TRANSPORT; RADIATION FLUX; RADIATION TRANSPORT; REACTORS; TRANSPORT THEORY
Optional Information
- Notes
- Formalism implemented in the FORTRAN module MODHEX; 7 refs.