Review of structural materials for high temperature nuclear reactors cooled by lead and its alloys
Bidaye, A.C.; Sharma, I.G.; Dulera, I.V., E-mail: acbidaye@barc.gov.in
Proceedings of the international conference on advances in nuclear materials processing, performance and phenomena and satellite conference on materials behaviour- far from equilibrium: book of abstracts. V.12006
Proceedings of the international conference on advances in nuclear materials processing, performance and phenomena and satellite conference on materials behaviour- far from equilibrium: book of abstracts. V.12006
AbstractAbstract
[en] The compact high temperature reactor (CHTR) is being developed to serve as a compact power pack in remote areas not connected to the electrical grid. It is a mainly 233U-thorium fuelled, lead-bismuth cooled and beryllium oxide moderated reactor. This reactor is being designed to operate at 1000 °C to generate about 100 kWTh power, with a core life of 15 years and will incorporate several advanced passive safety features. The reactor also facilitate demonstration of technologies for high temperature process heat applications such as hydrogen production from water
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Bhabha Atomic Research Centre, Mumbai (India); 179 p; 2006; p. 168; ANM 2006: international conference on advances in nuclear materials processing, performance and phenomena; Mumbai (India); 12-16 Dec 2006; MBFE 2006: satellite conference on materials behaviour- far from equilibrium; Mumbai (India); 12-16 Dec 2006; This record replaces 50063263
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Book
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Conference
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Descriptors (DEI)
Descriptors (DEC)
ACTINIDE NUCLEI, ALLOYS, ALPHA DECAY RADIOISOTOPES, ENRICHED URANIUM REACTORS, EVEN-ODD NUCLEI, EXPERIMENTAL REACTORS, GAS COOLED REACTORS, GRAPHITE MODERATED REACTORS, HEAVY ION DECAY RADIOISOTOPES, HEAVY NUCLEI, HELIUM COOLED REACTORS, HTGR TYPE REACTORS, ISOTOPES, NEON 24 DECAY RADIOISOTOPES, NUCLEI, RADIOISOTOPES, REACTOR COMPONENTS, REACTORS, RESEARCH AND TEST REACTORS, SPONTANEOUS FISSION RADIOISOTOPES, URANIUM ISOTOPES, YEARS LIVING RADIOISOTOPES
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