Published April 2018 | Version v1
Book Metadata-only

Neutronic analysis of pressurized water reactor with SiC cladding fuel

Creators

  • 1. School of Electric Power, South China University of Technology, Guangzhou, Guangdong (China)

Description

According to the material characteristic of SiC. This paper proposed two kinds of SiC cladding fuel. Lattice calculated code 'DRAGON' and core calculated code 'DONJON' were adopted for physics calculation. Some analysis were carried out by comparing SiC cladding and zircaloy. Such as neutron spectrum, fuel and moderator temperature coefficient of reactivity and burn up calculation. What's more, in core physics calculation, reactivity power distribution for SiC cladding fuel in the axial and radial were explored. Results demonstrate that SiC types of assembly have broadly agreement neutron performance with the conventional cladding fuel. Meanwhile, SiC cladding fuel gain better performance in these respects of enrichment and neutron spectrum, which confirmed the acceptability of SiC cladding in the way of neutron physics. (authors)

Part of:
Progress report on nuclear science and technology in China (Vol.5). Proceedings of academic annual meeting of China Nuclear Society in 2017, No.3--Nuclear Energy & Power sub-volume

Additional details

Publishing Information

Publisher
China Atomic Energy Press
Imprint Place
Beijing (China)
ISBN
978-7-5022-8776-4
Imprint Title
Progress report on nuclear science and technology in China (Vol.5). Proceedings of academic annual meeting of China Nuclear Society in 2017, No.3--Nuclear Energy & Power sub-volume
Imprint Pagination
602 p.
Journal Page Range
p. 222-227

Conference

Title
2017 academic annual meeting of China Nuclear Society
Dates
16-18 Oct 2017
Place
Weihai (China)

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
53102076
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPARATIVE EVALUATIONS; FUEL CANS; NEUTRON PHYSICS; NEUTRON SPECTRA; PERFORMANCE; POWER DISTRIBUTION; PWR TYPE REACTORS; SILICON CARBIDES; TEMPERATURE COEFFICIENT; ZIRCALOY
Descriptors DEC
ALLOYS; CARBIDES; CARBON COMPOUNDS; ENRICHED URANIUM REACTORS; EVALUATION; PHYSICS; POWER REACTORS; REACTIVITY COEFFICIENTS; REACTORS; SILICON COMPOUNDS; SPECTRA; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS

Optional Information

Notes
6 figs., 5 tabs., 10 refs.