Exact-to-precision generalized perturbation for neutron transport calculation
Creators
- 1. North Carolina State University, 911 Oval Dr., Centennial Campus, Raleigh, NC 27606 (United States)
Description
This manuscript extends the exact-to-precision generalized perturbation theory (EPGPT), introduced previously, to neutron transport calculation whereby previous developments focused on neutron diffusion calculation only. The EPGPT collectively denotes new developments in generalized perturbation theory (GPT) that place premium on computational efficiency and defendable accuracy in order to render GPT a standard analysis tool in routine design and safety reactor calculations. EPGPT constructs a surrogate model with quantifiable accuracy which can replace the original neutron transport model for subsequent engineering analysis, e.g. functionalization of the homogenized few-group cross sections in terms of various core conditions, sensitivity analysis and uncertainty quantification. This is achieved by reducing the effective dimensionality of the state variable (i.e. neutron angular flux) by projection onto an active subspace. Confining the state variations to the active subspace allows one to construct a small number of what is referred to as the 'active' responses which are solely dependent on the physics model rather than on the responses of interest, the number of input parameters, or the number of points in the state phase space. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park (United States)
- ISBN
- 978-0-89448-700-2
- Imprint Title
- Proceedings of the 2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering - M and C 2013
- Imprint Pagination
- 3016 p.
- Journal Page Range
- p. 828-841
Conference
- Title
- 2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering
- Acronym
- M and C 2013
- Dates
- 5-9 May 2013
- Place
- Sun Valley, ID (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 45033717
- Subject category
- S97: MATHEMATICAL METHODS AND COMPUTING;
- Resource subtype / Literary indicator
- Conference
- Quality check status
- Yes
- Descriptors DEI
- ACCURACY; CROSS SECTIONS; DESIGN; DISTURBANCES; EFFICIENCY; ENGINEERING; NEUTRON DIFFUSION EQUATION; NEUTRON FLUX; NEUTRON TRANSPORT; NEUTRONS; NUCLEAR PHYSICS; PERTURBATION THEORY; PHASE SPACE; REACTOR SAFETY; SENSITIVITY ANALYSIS; TRANSPORT THEORY;
- Descriptors DEC
- BARYONS; DIFFERENTIAL EQUATIONS; DIFFUSION EQUATIONS; ELEMENTARY PARTICLES; EQUATIONS; FERMIONS; HADRONS; MATHEMATICAL SPACE; NEUTRAL-PARTICLE TRANSPORT; NUCLEONS; PARTIAL DIFFERENTIAL EQUATIONS; PHYSICS; RADIATION FLUX; RADIATION TRANSPORT; SAFETY; SPACE;
Optional Information
- Lead record
- cgjt4-fyf07
- Notes
- 30 refs.