Published September 1998 | Version v1
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Xenon load analysis for CANDU 6 with DUPIC fuel

Creators

Description

Xenon load for a CANDU 6 reactor with DUPIC fuel has been studies. Xenon property constants were generated by WIMS-AECL code and the xenon load was calculated by RFSP code with a 3-dimensional full core model. Validation calculation has shown that the xenon load with the xenon constants from WIMS-AECL code is predicted within 2% compared to that with the xenon constants from POWDERPUFS-V code. The xenon load has been calculated for various reactor power level changes and reactor shutdown conditions. Calculation results have shown that the xenon load of CANDU 6 loaded with the DUPIC fuel is much lower than that loaded with standard 37-element natural uranium fuel. The calculated xenon load will be used to assess the function of reactivity control devices for DUPIC core. (author). 6 tabs., 5 figs

Availability note (English)

Available from INIS in electronic form

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Additional details

Publishing Information

Imprint Pagination
41 p.
Report number
KAERI/TR--1132/98

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
30053454
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
CANDU TYPE REACTORS; COMPARATIVE EVALUATIONS; FISSION PRODUCTS; NUCLEAR FUELS; PWR TYPE REACTORS; R CODES; REACTIVITY; REACTOR CORES; SPENT FUELS; W CODES; XENON
Descriptors DEC
COMPUTER CODES; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EVALUATION; FUELS; HEAVY WATER MODERATED REACTORS; ISOTOPES; MATERIALS; NONMETALS; NUCLEAR FUELS; POWER REACTORS; PRESSURE TUBE REACTORS; RADIOACTIVE MATERIALS; RARE GASES; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS