Published 2001 | Version v1
Book Metadata-only

Analysis of the thermal behavior of DUPIC fuel

Creators

  • 1. Korea Atomic Energy Research Institute, Yusong-ku, Taejon City (Korea, Republic of)

Description

In order to evaluate the thermal behavior of DUPIC fuel, the irradiation test of simulated DUPIC fuel was accomplished at the HANARO research reactor, and the post-irradiation analysis of irradiated pellets was performed at IMEF in KAERI. To find out the temperature distribution of DUPIC fuel pellets, the FEMAXI-IV code that can analyze the performance of a fuel rod was selected and the thermal conductivity model suitable for characteristics of DUPIC fuel was proposed. Considering HANARO operation conditions, the heat transfer routine was also revised. The temperature profile calculated with FEMAXI-IV was compared with the result of post-irradiation analysis. This comparative study shows that the estimate of FEMAXI-IV agreed moderately well with the result of post-irradiation examination. (author)

Part of:
CANDU fuel for the future

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
ISBN
0-919784-70-4
Imprint Title
CANDU fuel for the future
Imprint Pagination
2 v.
Journal Page Range
(v.1) p. 237-247

Conference

Title
7. International CANDU fuel conference proceedings
Dates
23-27 Sep 2001
Place
Kingston, Ontario (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
34078583
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ATOMIC ENERGY OF CANADA LTD; CANDU TYPE REACTORS; COMPUTER CODES; FUEL CYCLE; FUEL RODS; HANARO REACTOR; KAERI; NATURAL URANIUM; PWR TYPE REACTORS; REPROCESSING; SPENT FUEL ELEMENTS; TEMPERATURE DISTRIBUTION; THERMAL CONDUCTIVITY
Descriptors DEC
ACTINIDES; CANADIAN ORGANIZATIONS; ELEMENTS; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; HEAVY WATER MODERATED REACTORS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; KOREAN ORGANIZATIONS; MATERIALS TESTING REACTORS; METALS; NATIONAL ORGANIZATIONS; PHYSICAL PROPERTIES; POOL TYPE REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SEPARATION PROCESSES; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS; THERMODYNAMIC PROPERTIES; URANIUM; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
12 refs., 7 figs.