Published 1996
| Version v1
Miscellaneous
Modelling of CANDU NPP reactor regulating system using CATHENA
- 1. Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)
- 2. AECL, Chalk River (Canada)
Description
A CATHENA model for the reactor regulating system is developed and tested independently. A CATHENA plant model is created by combining this model with the reference CATHENA model which has been developed to analyze a loss-of-coolant accident(LOCA) for the Wolsong 2 generating station. This model is intended to provide a trip coverage analysis capability. The CATHENA reactor regulating system model includes the demand power routine, the light water zone control absorbers, mechanical control absorbers and adjusters. The CATHENA model is tested for steady state at 103% full power. A postulated accident transient (small LOCA) was also tested. The results show that the control routines in CATHENA were set up properly
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Taejon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS spring meeting
- Imprint Pagination
- 3566 p.
- Journal Page Range
- p. 1579-1585
Conference
- Title
- 1996 spring meeting of the KNS
- Dates
- 31 May - 1 Jun 1996
- Place
- Cheju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 37120287
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- C CODES; CANDU TYPE REACTORS; COMPUTERIZED SIMULATION; LOSS OF COOLANT; TRANSIENTS; WOLSUNG-2 REACTOR
- Descriptors DEC
- ACCIDENTS; CANDU TYPE REACTORS; COMPUTER CODES; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; NATURAL URANIUM REACTORS; PHWR TYPE REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTORS; SIMULATION; THERMAL REACTORS
Optional Information
- Notes
- 9 refs, 10 figs, 1 tab