Assessment of RELAP5/MOD3/CANDU+ to Wolsung-1 D2O leakage event
- 1. KAERI, Taejon (Korea, Republic of)
- 2. KINS, Taejon (Korea, Republic of)
Description
In order to evaluate the integrated performance of RELAP5/MOD3/CANDU+ for CANDU operational transient analysis, we assesed the code to the D2O leakage event occurred at Wolsung-I, 600 MW(e) CANDU reactor, on Oct. 20, '94. D2O leakage event was initiated by stuck opening of liquid relief valve No.4 in primary coolant pressure and level control system. Assessment calculation was performed for the plant transients up to 1000 seconds after the initiating event. Calculation results are compared with those measured in primary heat transport system, pressure and inventory control system and boiler secondary system. Comparison with the plant trip log shows that the RELAP5/CANDU+ is able to simulate the plant transients properly, from which we can conclude that the RELAP5/CANDU+ is validated for application to CANDU operational transient analysis. CANDU specific models used in the assessment are fuel bundle heat transfer model, decay heat model and MOV(Motor Operated Valve) model
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Taejon (Korea, Republic of)
- Imprint Title
- Proceedings of the Korean Nuclear Society autumn meeting
- Imprint Pagination
- [CD-ROM]
- Journal Page Range
- [10 p.]
Conference
- Title
- 2001 autumn meeting of the Korean Nuclear Society
- Dates
- 24-26 Oct 2001
- Place
- Seoul (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 33065485
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CONTROL SYSTEMS; D CODES; FUEL ELEMENT CLUSTERS; HEAT TRANSFER; LEAKS; R CODES; RELIEF VALVES; TRANSIENTS; WOLSUNG-1 REACTOR
- Descriptors DEC
- CANDU TYPE REACTORS; COMPUTER CODES; CONTROL EQUIPMENT; ENERGY TRANSFER; EQUIPMENT; FLOW REGULATORS; FUEL ASSEMBLIES; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; NATURAL URANIUM REACTORS; PHWR TYPE REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; THERMAL REACTORS; VALVES
Optional Information
- Notes
- 8 refs, 10 figs, 3 tabs