Development and Test of a New Verification Scheme for Transient Core Simulators
Creators
- 1. Division of Subatomic and Plasma Physics, Department of Physics, Chalmers University of Technology, SE-412 96 Gothenburg, Sweden (Sweden)
Description
Transient calculations in commercial nuclear reactors are performed while typically relying on a time-dependent neutron transport solver or a low-order solver (i.e. diffusion). In order to be licensed, the codes used by the industry need to go through a process of verification and validation, with the verification carried out by comparing the results of simulations to analytical or semi-analytical solutions. Such analytical or semi-analytical solutions can only be obtained if the system to be modelled during the verification process is either fully homogeneous or piecewise homogeneous. This paper reports on the development of a different verification approach that can be applied to fully heterogeneous systems. It relies on the extraction of the point-kinetic response of the reactor (which can be estimated from the results of core simulations) and on its subsequent comparison with its expected analytical form
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 116
- Journal Page Range
- p. 1025-1026
- ISSN
- 0003-018X
Conference
- Title
- 2017 Annual Meeting of the American Nuclear Society
- Dates
- 11-15 Jun 2017
- Place
- San Francisco, CA (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 52090695
- Subject category
- S97: MATHEMATICAL METHODS AND COMPUTING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ANALYTICAL SOLUTION; COMPARATIVE EVALUATIONS; COMPUTERIZED SIMULATION; NEUTRON TRANSPORT; REACTORS; SIMULATORS; TIME DEPENDENCE; TRANSIENTS; VALIDATION; VERIFICATION
- Descriptors DEC
- ANALOG SYSTEMS; EVALUATION; FUNCTIONAL MODELS; MATHEMATICAL SOLUTIONS; NEUTRAL-PARTICLE TRANSPORT; RADIATION TRANSPORT; SIMULATION; TESTING
Optional Information
- Notes
- 4 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)