Rejuvenation of the LWR spent fuel in (D–T) driven hybrid reactors

Ünalan, Sebahattin

doi:10.1016/s0920-3796(97)00120-8

Cited by 19 publications

(2 citation statements)

References 20 publications

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“…In this study was used APEX fusion technology as a hybrid reactor design. The liquid wall has been used to regulate the performance of the APEX hybrid reactor, energy transfer and tritium production (Christofilos, 1989;Günay, 2015b;Abdou et al, 2001;Ünalan, 1998;Abdou, 2004;Şarer et al, 2007;Moir, 1997;Günay, 2014d). The large radius of hybrid reactor is 552 cm.…”

Section: Methodsmentioning

confidence: 99%

Calculation of Fissile Fuel Production in Some Minor Actinides Based on Thorium

Düz

ŞEKER²

2022

Euroasia Journal

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In this study, a hybrid reactor with fission fusion reaction was modeled. As a fluid in design; 10% ThC2 + 0.1-1% AmF3 + 89.9-89% Li20Sn80 and 10% ThC2 + 0.1-1% NpF4 + 89.9-89% Li20Sn80 molten salt was used. In the first liquid wall, second liquid wall and shield regions of the reactor, the fissile fuel production was calculated using the MCNPX-2.7.0. ENDF/B-VII.0 nuclear reaction cross section library was used for numerical calculations.

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Section: Methodsmentioning

confidence: 99%

Calculation of Fissile Fuel Production in Some Minor Actinides Based on Thorium

Düz

ŞEKER²

2022

Euroasia Journal

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“…Whereas the hydrogen atom and its isotopes produced by (n, p), (n, d), and (n, t) reactions can diffuse out of the first wall material with high temperatures, the helium atoms produced by (n, α) and (n, He -3) reactions will accumulate in the first wall of the hybrid reactor and produce helium gas bubbles. These reactions will limit the operational lifetime of the structural material of the reactor [14][15][16][17].…”

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confidence: 99%

Contributions of each isotope in structural material on radiation damage in a hybrid reactor

Günay

2016

EPJ Web Conf.

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In this study, the fluids were used in the liquid first-wall, blanket and shield zones of the designed hybrid reactor system. In this study, salt-heavy metal mixtures consisting of 93-85% Li 20 Sn 80 + 5% SFG-PuO 2 and 2-10% UO 2 , 93-85% Li 20 Sn 80 + 5% SFG-PuO 2 and 2-10% NpO 2 , and 93-85% Li 20 Sn 80 + 5% SFG-PuO 2 and 2-10% UCO were used as fluids. In this study, the effect on the radiation damage of spent fuel-grade (SFG)-PuO 2 , UO 2 , NpO 2 and UCO contents was investigated in the structural material of a designed fusion-fission hybrid reactor system. In the designed hybrid reactor system were investigated the effect on the radiation damage of the selected fluid according to each isotopes of structural material in the structural material for 30 full power years (FPYs). Three-dimensional analyses were performed using the most recent MCNPX-2.7.0 Monte Carlo radiation transport code and the ENDF/B-VII.0 nuclear data library.

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Investigation of neutronic performance of a peaceful nuclear explosive reactor (PACER) evaluating UF4 and ThF4 nuclides

Akansu¹,

Kahraman²

2004

Sadhana

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In this study, neutronic behaviour of a peaceful nuclear explosion reactor (PACER) producing approx 1•2 GWe power from fusion explosions is analysed considering ThF 4 and UF 4 as fissile zones. UF 4 and ThF 4 are put in to the system adjacent to the inner-side of the flibe coolant zone positions (distance between explosive region and fuel zone, DR = 50, 100, 200, 400, 500 and 700 cm). Flibe percentages are taken to be 25, 50, 75 and 100%. It is found that optimum combinations of fissile zone thickness, coolant zone position and coolant percentages are 10 cm, 200 cm and 25% flibe for UF 4 and 10 cm, 50 cm and 25% flibe for ThF 4. The behaviour of fuels mentioned above has been observed over a period of 30 years at discrete time intervals, t = 30 days. In the case of UF 4 , M values at

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Rejuvenation of the LWR spent fuel in (D–T) driven hybrid reactors

Cited by 19 publications

References 20 publications

Calculation of Fissile Fuel Production in Some Minor Actinides Based on Thorium

Calculation of Fissile Fuel Production in Some Minor Actinides Based on Thorium

Contributions of each isotope in structural material on radiation damage in a hybrid reactor

Investigation of neutronic performance of a peaceful nuclear explosive reactor (PACER) evaluating UF4 and ThF4 nuclides

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