Neutronic calculations for CANDU thorium systems using Monte Carlo techniques

Saldideh, M.; Shayesteh, Mohsen; Eshghi, Mahdi

doi:10.1088/1674-1137/38/8/088201

Cited by 2 publications

(1 citation statement)

References 6 publications

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“…Nuttin et al com par a tively an a lyzed the con ver sion per for mances of CANDU and PWR re actors loaded with a mix ture of tho rium and plu to nium by slightly mod i fy ing them [7]. Saldideh et al cal cu lated the neutronic val ues of a CANDU re ac tor fu elled with var i ous mix tures of tho rium, ura nium and plu to nium by us ing Monte Carlo tech niques [8]. They point out that with such fuel com po si tions, the in fi nite neu tron mul tipli ca tion fac tor (k ¥ ) can be above 1.04 dur ing over 8 years of burn op er a tion.…”

Section: Introductionmentioning

confidence: 99%

Analysis of fuel rejuvenation times in a fusion breeder reactor fuelled with a mixture of uranium-thorium oxides for the CANDU reactor

Bakır

Yapıcı

2017

NUCL TECH RAD PROT

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1 Tech nol ogy Fac ulty, Cumhuriyet Uni ver sity, Sivas, Tur key 2 En gi neer ing Fac ulty, Erciyes Uni ver sity, Kayseri, Tur key Sci en tific pa per http://doi.org/10.2298/NTRP1703193BThis study pres ents the de ter mi na tion of fuel re ju ve na tion times in a D-T fu sion breeder re actor fu elled with a mix ture of nat UO 2 and ThO 2 for multi-re use of nu clear fu els in CANDU-37 re ac tors. To de ter mine the ef fect of tho rium on the fuel en rich ment and re ju ve na tion times, neutronic anal y ses are per formed by in creas ing the per cent age of ThO 2 in the fuel mix ture from 10 to 35. The time-de pend ent neutronic cal cu la tions are car ried out in three stages. In the first stage, which is the fuel en rich ment or re ju ve na tion pro cess in the fu sion breeder re actor, the subcritical cal cu la tions of the fu sion breeder re ac tor fu elled with the fuel mix tures are per formed by us ing the MCNPX 2.7/CIN DER un der a fu sion neu tron wall load ing of 1 MWm -2 , cor re spond ing to neu tron flux of 4.444·10 13 cm -2 s -1 (en ergy of ev ery fu sion neu tron is 14.1 MeV). In the sec ond stage, which is the ther mal re ac tor anal y sis, the fuel rods en riched at the end of the first stage are placed in the CANDU-37 re ac tor, and the crit i cal calcu la tions of this re ac tor are per formed by us ing MCNPX 2.7 and MONTEBURNS codes sep a rately. The nu mer i cal re sults show that the neutronic val ues ob tained from both codes are very near each other. The third stage is the two-year cool ing pro cess of CANDU spent fu els. The val ues ob tained by nu mer i cal cal cu la tions show that this fu sion breeder re ac tor is self-suf fi cient in terms of tri tium and has a high per for mance in terms of en ergy mul ti pli cation as well as fuel re ju ve na tion and tho rium uti li za tion.Key words: fu sion breeder re ac tor, fis sile breed ing, fuel en rich ment, fuel re ju ve na tion, tho rium uti li za tion, CANDU re ac tor G. Bakir, et al.: Anal y sis of Fuel Re ju ve na tion Times in a Fu sion Breeder .

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Section: Introductionmentioning

confidence: 99%

Analysis of fuel rejuvenation times in a fusion breeder reactor fuelled with a mixture of uranium-thorium oxides for the CANDU reactor

Bakır

Yapıcı

2017

NUCL TECH RAD PROT

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Analysis of reusability of ThO2 and spent UO2 fuels enriched with ads in a CANDU reactor

et al. 2022

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The study presents the analysis of the reusability of ThO2 and spent UO2 fuels enriched in two different ADS reactors fuelled with Minor Actinide. The spent UO2 fuels are taken out from pressurized water reactor and CANDU spent fuels. For this analysis, the CANDU-37 reactor having a total fission thermal power of 2156 MW is considered and 14 different cases of enriched fuels taken from the previous enrichment processes are analysed by burning in this reactor. The 3-D and time-dependent critical burn up calculations are carried out by using the MCNP 2.7 code. To determine the effective burn time of each case, these calculations are performed until the values of kinf decrease to about the criticality thresh old of 1.05 for all investigated cases. The percent ages of the 239Pu and 233U fissile isotopes appear to be below weapons-grade plutonium and uranium, respectively, in all enriched fuel cases. At the end of effective burn times, the burnup values can reach the values varying in the range of 26.770 and 33.540 GWd/MTU which are a mean of 3.5-4.5 times the burnup value of the CANDU-37 reactor fed with the NatUO2 fuel. The results of this study bring out that in terms of energy production, the CANDU-37 reactor fuelled with the ThO2 and spent UO2 fuels enriched in ADS designs demonstrates higher neutronic performance than the conventional CANDU-37 reactor.

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Neutronic calculations for CANDU thorium systems using Monte Carlo techniques

Cited by 2 publications

References 6 publications

Analysis of fuel rejuvenation times in a fusion breeder reactor fuelled with a mixture of uranium-thorium oxides for the CANDU reactor

Analysis of fuel rejuvenation times in a fusion breeder reactor fuelled with a mixture of uranium-thorium oxides for the CANDU reactor

Analysis of reusability of ThO2 and spent UO2 fuels enriched with ads in a CANDU reactor

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