Sensitivity and uncertainty analysis for coolant void reactivity in a Candu fuel lattice cell model
Creators
- 1. Nuclear Eng. Dept., Seoul National University, 1 Gwanak-ro, Gwanak-gu, Seoul 08826 (Korea, Republic of)
Description
This paper proposes the Monte Carlo (MC) second-order perturbation methodology to estimate the uncertainty for the reactivity worth and presents the uncertainty for Coolant Void Reactivity (CVR) of the Candu fuel lattice cell problem. The Eigenvalue Perturbation Based Method (EPBM) which utilizes the first-order perturbation technique is presented as well. They are applied to predict the cross-section sensitivity of the reactivity change due to the density perturbation. The prediction accuracy of estimated sensitivities is evaluated by comparing with the ones estimated by direct subtraction method. The results show both EPBM and second-order perturbation method agree well with the reference. With those sensitivities, the uncertainty analysis is performed for the Candu fuel lattice cell problem with the 44- energy group ENDF/B-VII.1 covariance data. (authors)
Additional details
Publishing Information
- Publisher
- Korean Nuclear Society - KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Pagination
- 6 p.
Conference
- Title
- International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering 2017
- Acronym
- M and C 2017
- Dates
- 16-20 Apr 2017
- Place
- Jeju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- France
- INIS RN
- 53074376
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CANDU TYPE REACTORS; COOLANTS; CROSS SECTIONS; DENSITY; EIGENVALUES; MONTE CARLO METHOD; NUCLEAR DATA COLLECTIONS; NUCLEAR FUELS; PERTURBATION THEORY; REACTIVITY WORTHS; SENSITIVITY; VOIDS
- Descriptors DEC
- CALCULATION METHODS; ENERGY SOURCES; FUELS; HEAVY WATER MODERATED REACTORS; MATERIALS; PHYSICAL PROPERTIES; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS
Optional Information
- Notes
- 6 refs.; Available from the INIS Liaison Officer for France, see the INIS website for current contact and E-mail addresses