Published 1994 | Version v1
Miscellaneous

Simulation of CANFLEX thermal hydraulics during a SBLOCA in a CANDU reactor

  • 1. Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

Description

Thermalhydraulic behavior of an advanced CANDU fuel, CANFLEX (CANdu FLEXible), has been described with CATHENA(Canadian Algorithm for THermal-hydraulic Network Analysis). A CATHENA CANFLEX circuit and channel simulation for a 2.5 % RIH (Reactor Inlet Header) LOCA case has been made to assess the relative safety of CANFLEX over the reference fuel. A key design improvement of CANFLEX is a flatter radial power shape over the reference fuel. The operational margin can be increased by decreasing the outer fuel center temperature to 278 .deg. C, which is from 1443 .deg. C to 1165 .deg. C. However, the inner fuel center temperature increased to 154 .deg. C due to the flatter radial power profile. A better safety margin with CANFLEX may be obtained in the outer sheath temperature without experiencing a fuel heatup. The other transients indicated that CANFLEX relative safety can be achieved for this 2.5 % RIH LOCA scenario in a typical CANDU 600 plant

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
988 p.
Journal Page Range
p. 623-630

Conference

Title
1994 spring meeting of the KNS
Dates
27-28 May 1994
Place
Pohang (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
38022780
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CANDU TYPE REACTORS; COMPUTERIZED SIMULATION; DESIGN; LOSS OF COOLANT; SAFETY; THERMAL HYDRAULICS; TRANSIENTS
Descriptors DEC
ACCIDENTS; FLUID MECHANICS; HEAVY WATER MODERATED REACTORS; HYDRAULICS; MECHANICS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTORS; SIMULATION; THERMAL REACTORS

Optional Information

Notes
5 refs, 9 figs, 2 tabs