Computational analysis of neutronic effects of ThO2 rods loaded in CANDU 6 fuel assemblies

Mirvakili, Seyed Mohammad; Gholamzadeh, Zohreh; Feghhi, S.A.H.

doi:10.1007/s41365-016-0101-y

Cited by 5 publications

(3 citation statements)

References 13 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The tri tium breed ing ra tio (TBR), which is one of the main pa ram e ters of fu sion breeder re ac tors, can be ob tained from the fol low ing re ac tions 6 Li n He T where R f is the num ber of fis sion re ac tions per fu sion neu tron, 6 Li(n,g) -the tri tium breed ing re ac tion from 6 Li (see eq. 1a) and 7 Li(n,g) -the tri tium breed ing re action from 7 Li (see eq.…”

Section: Case Of Only Nat Uo 2 Fuelmentioning

confidence: 99%

“…The nu mer ical re sults show that ura nium de mand can be re duced ap prox i mately by 27 % by plac ing the tho rium-plu tonium MOX fu els in the in ner fuel rods. Mirvakili et al, an a lyzed the neutronic ef fects of ThO 2 by plac ing it in 6 of the 37 fuel rods in fuel bun dles of the CANDU 6 reac tor [6]. Neutronic cal cu la tions are per formed by using MCNPX 2.6 and CINDER90.…”

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

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

View full text Add to dashboard Cite

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 .

show abstract

Section: Case Of Only Nat Uo 2 Fuelmentioning

confidence: 99%

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

View full text Add to dashboard Cite

show abstract

“…Thorium dioxide is a robust nuclear fuel candidate for generation IV reactors because of its low generation of minor actinides, excellent radiation resistance and chemical stability. [1][2][3][4] During the reactor operation, production of noble gases may affect the mechanical and thermal properties of nuclear fuels. [5,6] One of these noble gases is helium, and most of the helium is generated by alpha decay during fuel burnup.…”

Section: Introductionmentioning

confidence: 99%

First-principles study of helium clustering at initial stage in ThO ₂

Shao¹,

Han²,

Zhang³

et al. 2017

Chinese Phys. B

View full text Add to dashboard Cite

The clustering behavior of helium atoms in thorium dioxide has been investigated by first-principles calculations. The results show that He atoms tend to form a cluster around an octahedral interstitial site (OIS). As the concentration of He atoms in ThO 2 increases, the strain induced by the He atoms increases and the octahedral interstitial site is not large enough to accommodate a large cluster, such as a He hexamer. We considered three different Schottky defect (SD) configurations (SD 1 , SD 2 , and SD 3 ). When He atoms are located in the SD sites, the strain induced by the He atoms is released and the incorporation and binding energies decrease. The He trimer is the most stable cluster in SD 1 . Large He clusters, such as a He hexamer, are also stable in the SDs.

show abstract

Ensuring the possibility of using thorium as a fuel in a pressurized water reactor (PWR)

2021

View full text Add to dashboard Cite

Computational analysis of neutronic effects of ThO2 rods loaded in CANDU 6 fuel assemblies

Cited by 5 publications

References 13 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

First-principles study of helium clustering at initial stage in ThO ₂

Ensuring the possibility of using thorium as a fuel in a pressurized water reactor (PWR)

Contact Info

Product

Resources

About

Computational analysis of neutronic effects of ThO2 rods loaded in CANDU 6 fuel assemblies

Cited by 5 publications

References 13 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

First-principles study of helium clustering at initial stage in ThO 2

Ensuring the possibility of using thorium as a fuel in a pressurized water reactor (PWR)

Contact Info

Product

Resources

About

First-principles study of helium clustering at initial stage in ThO ₂