Published July 2020
| Version v1
Report
Development and Implementation in the FRAPCON Code of Accident Tolerant Fuel Models for Coated Zircaloy Cladding and Metallic Microcell UO2 Pellet
Creators
- 1. Korea Atomic Energy Research Institute - KAERI, 111, Daedeok-daero 989 beon-gil, Yuseong-gu, Daejeon, 34057 (Korea, Republic of)
Description
KAERI has been developed the chrome-alloy coated cladding and metallic microcell UO2 pellet as the near term technology of the Accident Tolerant Fuel. The mechanical behaviour of metallic microcell UO2 pellet was estimated with finite element analysis tool. For the multi-layered cladding, the FRACAS-CT module was implemented into the fuel performance code, FRAPCON. And the fuel performance under the normal operation condition with the enhanced material properties of the metallic microcell pellet and the chrome-alloy coated cladding was estimated. (author)
Additional details
Identifiers
Publishing Information
- ISBN
- 978-92-0-114120-0
- Imprint Title
- Analysis of Options and Experimental Examination of Fuels for Water Cooled Reactors with Increased Accident Tolerance (ACTOF). Final Report of a Coordinated Research Project. Supplementary Files. Country Reports from Participants
- Imprint Pagination
- 292 p.
- Journal Page Range
- p. 210-222
- ISSN
- 1011-4289
- Report number
- IAEA-TECDOC--1921(Supplementary Files)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51083374
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S36: MATERIALS SCIENCE;
- Descriptors DEI
- ACCIDENT-TOLERANT NUCLEAR FUELS; CHROMIUM ALLOYS; CLADDING; COATINGS; COMPUTER CODES; FINITE ELEMENT METHOD; FUEL PELLETS; KAERI; PERFORMANCE; STEADY-STATE CONDITIONS; URANIUM DIOXIDE; ZIRCALOY
- Descriptors DEC
- ACTINIDE COMPOUNDS; ALLOYS; CALCULATION METHODS; CHALCOGENIDES; DEPOSITION; ENERGY SOURCES; FUELS; KOREAN ORGANIZATIONS; MATERIALS; MATHEMATICAL SOLUTIONS; NATIONAL ORGANIZATIONS; NUCLEAR FUELS; NUMERICAL SOLUTION; OXIDES; OXYGEN COMPOUNDS; PELLETS; REACTOR MATERIALS; SURFACE COATING; TRANSITION ELEMENT ALLOYS; URANIUM COMPOUNDS; URANIUM OXIDES; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Notes
- 10 refs., 20 figs., 1 tab.