Development of Core Technology of PHWR Safety Enhancement and Evaluation
Description
By developing CANDU technologies for detailed evaluation and treatment of aging, core physics/severe accident(SA), moderator issues in order to fortify safety in Wolsong plants: Development of aging evaluation model for Wolsong pressure tube (PT) as a key technology to PHWR safety margin enhancement. Establishment of evaluation and management system for recent issues in PHWR core physics and SA that would be equivalent to the PWR system. 3-dimensional PHWR moderator circulation experiment for code validation The following concrete results are obtained from this research. - Development of diameter prediction model for the irradiated PT - Development of localized analysis system for PHWR core and evaluation of positive reactivity in Wolsong LOCA - Development of world-class ISAAC engine, simulator and construction of evaluation DB for domestic critical issues from Fukushima post actions - Development of SAMG decision-supporting system (SAMEX-CANDU) for using accident management and prediction under ultimate accidents - Construction of the PHWR moderator circulation test (MCT) facility, steady state experiment and CFD validation analysis The following two main effects are expected from this research. - (1) PT aging evaluation technology could increase the level of safety margin, (2) PT core physics and SA evaluation technology could be a basis for enhancing safety and ultimate accident managing capability, and (3) both help to clear PHWR safety issues including those of continued operation in Wolsong - The optimal SAM decision-support technology (which is world-leading technology in PHWR) could be an effective advisory tool for emergency preparedness and TSC staff's decision under severe accidents of Wolsong NPP (for example, AtomCARE) - The MCT results can be used to develop a domestic CFD code which can replace MODTURCCLAS which was used for the safety analyses of Wolsong Unit 1 refurbishment and 37M fuel safety analysis for moderator circulation.
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49108289.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 158 p.
- Report number
- KAERI/RR--4190/2016
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 49108289
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- AGING; CANDU TYPE REACTORS; DECISION MAKING; FORECASTING; PHWR TYPE REACTORS; PRESSURE TUBES; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR CORES; SAFETY; SAFETY ANALYSIS
- Descriptors DEC
- ACCIDENTS; ENRICHED URANIUM REACTORS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; TUBES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 11 tabs