Core degradation modeling of CANDU severe accident code, CAISER
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
For the perspective of a regulation body, it is difficult to review the AMP report with the separate severe accident code with high accuracy. Although the MAAP-ISAAC code is developed in Korea based on MAAP code, through the recent deputy for the ownership of ISAAC code, the ownership of MAAP-ISAAC code is decided to belong to EPRI, which developed MAAP code, because the MAAPISAAC code was considered as one of the derivatives of MAAP code From the above mentioned background, the necessity for the development of CANDU severe accident code with high accuracy is raised. Hence, KAERI started the project to develop the detailed CANDU severe accident code from last year with 5 years plan. In this paper, the node system of a fuel channel and calandria tank, the main core degradation mechanism is described. From the necessity for the CANDU severe accident code having high accuracy to evaluate the allowable criterion on AMP, the detailed severe accident simulation code for CANDU reactor, CAISER has been developing in KAERI. The fuel channel module considers the water level change in a fuel channel, the melt & relocation process in a fuel channel, and the local thermal failure of a fuel channel by using 3- dimensional Cartesian coordinate node system.
Additional details
Identifiers
- URL
- https://www.kns.org;
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS 2018 Spring Meeting
- Imprint Pagination
- vp.
- Journal Page Range
- [4 p.]
Conference
- Title
- 2018 Spring Meeting of the KNS
- Dates
- 16-18 May 2018
- Place
- Jeju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 50059493
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ACCURACY; CANDU TYPE REACTORS; FISSION PRODUCT RELEASE; FUEL CHANNELS; M CODES; PROBABILITY; REACTOR ACCIDENTS; SAFETY ANALYSIS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS
Optional Information
- Notes
- 2 refs, 5 figs