Accuracy of a predictor-corrector quasi-static method for space-time reactor dynamics
Creators
- 1. Politecnico di Torino, Torino (Italy)
- 2. Universite Libre de Bruxelles, Brussels (Belgium)
Description
The quasi-static method is a standard tool for the space-time solution of neutron transport problems in multiplying media. Its basic principle lies in a factorization of the angular flux into the product of two functions, 'amplitude' and 'shape', where the amplitude depends only on time (and contains the major part of the time-dependence) while the shape function depends on all variables, time included. The shape equation is solved on a long time scale, while the amplitude is determined on a short time scale. The factorization is made unique by proper normalization conditions for the shape function. Most implementations replace the basic equation (transport or diffusion) by the set of coupled amplitude and shape equations derived from the factorization, the so-called 'Improved Quasi-Static Method' (IQM). In this paper we describe an alternate approach already known for some time, called here 'Predictor-Corrector Quasi-Static Method' (PCQM), and we discuss its efficiency for both solid- and liquid fuel systems. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park (United States)
- ISBN
- 0-89448-697-7
- Imprint Pagination
- 10 p.
Conference
- Title
- American Nuclear Society's Topical Meeting on Reactor Physics - Advances in Nuclear Analysis and Simulation
- Acronym
- PHYSOR-2006
- Dates
- 10-14 Sep 2006
- Place
- Vancouver, BC (Canada)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 43129893
- Subject category
- S97: MATHEMATICAL METHODS AND COMPUTING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCURACY; FACTORIZATION; FISSIONABLE MATERIALS; LIQUID FUELS; MATHEMATICAL SOLUTIONS; NEUTRON DIFFUSION EQUATION; NEUTRON TRANSPORT; REACTOR KINETICS; SPACE DEPENDENCE; TIME DEPENDENCE
- Descriptors DEC
- DIFFERENTIAL EQUATIONS; DIFFUSION EQUATIONS; EQUATIONS; FUELS; KINETICS; MATERIALS; NEUTRAL-PARTICLE TRANSPORT; PARTIAL DIFFERENTIAL EQUATIONS; RADIATION TRANSPORT
Optional Information
- Notes
- 5 refs.