Affiliation:
1. Faculty of Engineering, Erciyes University, Kayseri, Turkey
2. Faculty of Technology, Cumhuriyet University, Sivas, Turkey
3. Faculty of Engineering and Architecture, Batman University, Batman, Turkey
Abstract
This paper presents analyses of enrichments of uranium taken out from Canada
Deuterium Uranium and pressurized water reactors spent fuels and fissile
fuel breeding from thorium in two different helium cooled-accelerator
driven system designs, DESIGN A and DESIGN B. In the beginning, the 235U
percentages in the uranium fuels taken out from the reactors spent fuels are
0.17% and 0.91%, respectively. Both system cores are fuelled with two
different minor actinides compositions extracted from PWR-MOX spent fuels.
The DESIGN A has one transmutation zone (enrichment zone) surrounding the
fuel core and containing thorium or spent uranium fuels, while DESIGN B
has a second transmutation zone (fissile fuel breeding zone) surrounding the
first transmutation zone and containing only thorium fuel. In brief, a total
of ten cases formed by the combinations of accelerator driven system
designs, minor actinides components, and spent uranium with thorium fuels
are analysed, which are six in DESIGN A containing one transmutation zone
and four in DESIGN B containing two transmutation zones. Lead-bismuth
eutectic alloy, a liquid heavy metal, consisting of 45% lead and 55 %
bismuth is used as target material in the investigated accelerator driven
system. It is assumed that the target is bombarded with 1.2383?1017 protons
per second and that the energy of each proton is 1000 MeV. This means a
proton beam power of 20 MW. The 3-D and time-dependent neutronic analyses
are conducted by using the MCNPX 2.7 and CINDER 90 nuclear code. Both
accelerator driven system designs are operated until the values of keff rise
to 0.985 to determine the longest operation times that are the effective
burn times in all cases. Depending on the design, minor actinide
composition, and fuel type (spent UO2 and ThO2), the results obtained
at the end of cycle exhibit the effective burn times vary from 300 days to
2050 days, the fuel enrichments can reach up to 2.49-4.23% and the values
of gain reach up to 10.8-25.1.
Publisher
National Library of Serbia
Subject
Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering
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