Published October 2001 | Version v1
Miscellaneous

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

Part of:
Proceedings of the Korean Nuclear Society autumn meeting

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)

Optional Information

Notes
8 refs, 10 figs, 3 tabs