Published 2016 | Version v1
Miscellaneous Metadata-only

First principles studies of thermal conductivity of nuclear fuel materials

Creators

  • 1. Univ. of Saskatchewan, Dept. of Physics and Engineering Physics, Saskatoon, SK (Canada)
  • 2. Univ. of Saskatchewan, Dept. of Mechanical Engineering, Saskatoon, SK (Canada)

Description

The recent nuclear accident in Fukushima clearly illustrates the risks associated with the present design of reactors based on pure uranium oxide fuel and justifies research towards Accident Tolerant Fuel (ATF). ATF's are fuels with enhanced thermal conductivity, which can withstand the loss of coolant for a long time by allowing faster dissipation of heat, thus lowering the centerline temperature and preventing the melting of the fuel. The objective of this study is to analyze the thermal properties of urania and thoria fuel composites in order to improve thermal conductivity and propose safer fuel for present and future nuclear reactors. (author)

Part of:
CANDU fuel : evolution towards optimal performance. 13th international conference on CANDU fuel

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
ISBN
978-1-926773-24-7
Imprint Title
CANDU fuel : evolution towards optimal performance. 13th international conference on CANDU fuel
Imprint Pagination
66.6 Megabytes
Journal Page Range
[12 p.]

Conference

Title
13. International conference on CANDU fuel
Dates
15-18 Aug 2016
Place
Kingston, Ontario (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
50005361
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COOLING; HEAT TRANSFER; NUCLEAR FUELS; THERMAL CONDUCTIVITY; THORIUM; URANIUM DIOXIDE
Descriptors DEC
ACTINIDE COMPOUNDS; ACTINIDES; CHALCOGENIDES; ELEMENTS; ENERGY SOURCES; ENERGY TRANSFER; FUELS; MATERIALS; METALS; OXIDES; OXYGEN COMPOUNDS; PHYSICAL PROPERTIES; REACTOR MATERIALS; THERMODYNAMIC PROPERTIES; URANIUM COMPOUNDS; URANIUM OXIDES

Optional Information

Notes
29 refs., 1 tab., 6 figs.