Destruction rate analysis of transuranic targets in sodium-cooled fast reactor (SFR) assemblies using MCNPX and SCALE 6.0

Allen, Kenneth S.; Knight, Travis W.

doi:10.1016/j.pnucene.2009.09.001

Cited by 16 publications

(5 citation statements)

References 6 publications

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“…To improve the results accuracy, the calculation steps with a smaller time are needed especially at the beginning of the simulation to build in the equilibrium concentration of major fission products. Meanwhile, increasing the magnitude of time steps as the depletion progresses is also desired to save computing time (Allen and Knight, 2010). Under the above considerations, the FHR core is depleted for almost 3 years in 16 steps.…”

Section: Neutronics Simulation Softwarementioning

confidence: 99%

Analysis of thorium and uranium based nuclear fuel options in Fluoride salt-cooled High-temperature Reactor

Xiang-Zhou

Jiang

et al. 2015

Progress in Nuclear Energy

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Section: Neutronics Simulation Softwarementioning

confidence: 99%

Analysis of thorium and uranium based nuclear fuel options in Fluoride salt-cooled High-temperature Reactor

Xiang-Zhou

Jiang

et al. 2015

Progress in Nuclear Energy

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“…The Sodium-Cooled Fast Reactor (SFR) which is one of six reactor concepts favored by the Gen-IV program has been studied and developed in many countries such as the U.S., Russia, France, U. K. and Japan [10,11]. The SFR system has sodium cooled core, a fast neutron spectrum and a closed fuel cycle for efficient managements of actinides (Np, Cm, Am…).…”

Section: Sfr Conceptmentioning

confidence: 99%

The Investigation of Burnup Characteristics Using the Serpent Monte Carlo Code for a Sodium Cooled Fast Reactor

Korkmaz

Ağar

2014

Nuclear Engineering and Technology

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“…TRU elimination was also analysed in Generation IV reactors, such as lead-cooled fast reactor [5], sodium-cooled fast reactor [24], high temperature gas-cooled reactor [25], and molten salt reactor [26,27]. Fast-spectrum reactors possess an advantage in term of high neutron energy which allows the fission of various TRU elements.…”

Section: Introduction mentioning

confidence: 99%

Transmutation of Transuranic Elements as Solid Coating in Molten Salt Reactor Fuel Channel

Dwijayanto,

Miftasani,

Harto

2023

Tri Dasa Mega

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The accumulation of spent nuclear fuel (SNF) is presently considered as a hindrance of the massive deployment of nuclear power plant, especially regarding the transuranic (TRU) elements. Eliminating TRU through transmutation is one of the most feasible alternative as a technical solution to solve the issue. This study explores the possibility of TRU transmutation using molten salt reactor (MSR) in a heterogeneous configuration, where a solid TRU is coated inside the fuel channel filled with liquid salt fuel. Such configuration is proposed to allow higher TRU loading into fluoride salt mixture without compromising the safety of the reactor. TRU coating was applied in consecutively outward radial fuel channel layers with coating thicknesses of 2.5 mm and 5 mm. Calculation was performed using MCNP6.2 radiation transport code and ENDF/B-VII.0 neutron cross section library. From the results, TRU coating with smaller thickness and positioned closer to the centre of the core exhibit higher transmutation efficiency due to exposure to higher neutron flux. Highest transmutation efficiency was achieved at 67.93% after 160 days of burnup. This shows a potential of achieving highly efficient TRU using heterogeneous configuration in MSR core.

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Destruction rate analysis of transuranic targets in sodium-cooled fast reactor (SFR) assemblies using MCNPX and SCALE 6.0

Cited by 16 publications

References 6 publications

Analysis of thorium and uranium based nuclear fuel options in Fluoride salt-cooled High-temperature Reactor

Analysis of thorium and uranium based nuclear fuel options in Fluoride salt-cooled High-temperature Reactor

The Investigation of Burnup Characteristics Using the Serpent Monte Carlo Code for a Sodium Cooled Fast Reactor

Transmutation of Transuranic Elements as Solid Coating in Molten Salt Reactor Fuel Channel

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