Quantification of ATF concept assessment factors using multiphysics simulations
Creators
- 1. Department of Nuclear Engineering, Texas A and M University, 3133 TAMU, College Station, TX 77843 (United States)
- 2. Fuels Modeling and Simulation, Idaho National Laboratory, 2525 N. Fremont Ave., Idaho Falls, ID 83415 (United States)
Description
In pursuit of a quantitative method of comparing accident tolerant fuel concepts to traditional fuel behaviors, a method of applying failure probabilities in an existing fuel assessment framework is proposed. To demonstrate this process, an example case is undertaken by utilizing coupled multiphysics codes to investigate uranium silicide and uranium oxide fuel behaviors during a postulated reactivity insertion accident. An upper limit on each fuel system's surface cladding temperature is used to classify pass and fail cases on perturbed simulations. Sensitivity analysis reduces the dimensionality of the problem and a global geometric classification method predicts the limit surface separating pass and fail cases in the hyperspace made up of sensitive input variables. Numerically integrating this surface yields the probability of failure of the fuel concepts. Results demonstrate the method's viability as a fuel evaluation technique, but ongoing work will allow for quantification of proposed concept assessment factors. (authors)
Additional details
Publishing Information
- Publisher
- Korean Nuclear Society - KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Pagination
- 8 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
- 53074590
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCIDENT-TOLERANT NUCLEAR FUELS; CLADDING; CLASSIFICATION; COMPUTERIZED SIMULATION; FUEL SYSTEMS; GEOMETRY; REACTIVITY INSERTIONS; SENSITIVITY ANALYSIS; SURFACES; URANIUM OXIDES; URANIUM SILICIDES
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; DEPOSITION; ENERGY SOURCES; FUELS; MATERIALS; MATHEMATICS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; REACTOR MATERIALS; SILICIDES; SILICON COMPOUNDS; SIMULATION; SURFACE COATING; URANIUM COMPOUNDS
Optional Information
- Notes
- 11 refs.; Available from the INIS Liaison Officer for France, see the INIS website for current contact and E-mail addresses