Published May 2000 | Version v1
Miscellaneous

Improvement of RELAP5/MOD3.2.2 flow regime and development of fuel heat transfer model for thermal hydraulic safety analysis of CANDU plant

  • 1. KAERI, Taejon (Korea, Republic of)
  • 2. Korea Institute of Nuclear Safety, Taejon (Korea, Republic of)

Description

Thermal-hydraulic models of RELAP5/MOD3, current auditing tool for LWR licensing, have been improved to develop an auditing code for CANDU. It was attempted to extend the auditing area to CANDU LOCA event by improving RELAP5/MOD3/CANDU version, which had been already developed from RELAP5/MOD3.2.2 in order to audit non-LOCA events in CANDU plant. Major improving areas are flow regime model and heatup model of fuel elements. Horizontal flow regime map was improved by modifying the horizontal stratification criteria in CANDU fuel channel. Improved regime map was verified through the assessment of AECL experiment. Fuel heatup model was also developed by considering the fuel element elevations in CANDU channel if horizontal stratification occurs. Different thermal hydraulic conditions are applied for each fuel element in the estimation the heat transfer coefficient. RELAP5/MOD3/CANDU+ version have been developed by the application of models. The developed code extends the model capabilities of exiting RELAP5/MOD3/CANDU version which was based on RELAP5/MOD3.2.2 gamma version, and the code can be used for more realistic estimations of thermal hydraulic behavior in CANDU channel during a LOCA

Part of:
Proceedings of the KNS spring meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Taejon (Korea, Republic of)
Imprint Title
Proceedings of the KNS spring meeting
Imprint Pagination
[CDROM]
Journal Page Range
[12 p.]

Conference

Title
2000 spring meeting of the KNS
Dates
26-27 May 2000
Place
Kori (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
34027607
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CANDU TYPE REACTORS; FUEL ELEMENTS; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; R CODES; SAFETY ANALYSIS; THERMAL ANALYSIS
Descriptors DEC
ACCIDENTS; COMPUTER CODES; ENERGY TRANSFER; FLUID MECHANICS; HEAVY WATER MODERATED REACTORS; MECHANICS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS

Optional Information

Notes
6 refs, 10 figs, 1 tab