Whole core analysis of molten salt breeder reactor with online fuel reprocessing

Park, Jinsu; Jeong, Yongjin; Lee, Deokjung

doi:10.1002/er.3371

Cited by 18 publications

(26 citation statements)

References 9 publications

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“…According to another MSBR research, if the same kind of reprocessing method is adopted to obtain the equilibrium core composition in the whole MSBR core design directly, the calculation time will be about 8 times longer than the single-cell method [6]. The two-cell method can represent the MSBR core model more accurately with a less computational time than the single-cell method.…”

Section: Resultsmentioning

confidence: 99%

“…The single-cell method does not differentiate the characteristics of the two zones, so the equilibrium composition obtained from the two-cell method is more accurate than the single-cell method. In Table 4, there are four factors from the whole MSBR core analysis [6]. The difference between Zone I cell of the twocell method and Zone I of the whole MSBR core is less than 5%, but the Zone II results of the two-cell method and the whole MSBR core show some difference, especially about 30% difference in the resonance escape probability.…”

Section: Four Factor Analysismentioning

confidence: 91%

“…In Figure 11, there are normalized neutron flux spectrum for the initial and equilibrium states of Zone I cell and Zone II cell. Each neutron flux spectrum of the two-cell method is quite similar with the spectrum of each zone of the whole MSBR core [6]. It implies that the two-cell method can distinguish the characteristics of Zone I and Zone II of the whole MSBR core.…”

Section: Equilibrium Core Analysismentioning

confidence: 97%

“…The MSBR adopts molten-salt fuel and bare graphite moderator. The lithium in the molten-salt fuel is used as a fully enriched 7 Li because of high thermal absorption cross section of 6 Li. The uranium in the molten-salt fuel of an initial composition is used as 233 U in this paper.…”

Section: Introductionmentioning

confidence: 99%

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Equilibrium core design methods for molten salt breeder reactor based on two-cell model

Jeong

Park

Lee

2015

Journal of Nuclear Science and Technology

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Two unit-cell-based core design methods are presented for a molten salt breeder reactor (MSBR) equilibrium core with online reprocessing and refueling: a single-cell method and a two-cell method. The single-cell method adopts a representative single unit cell which has the same fuel-to-moderator volume ratio as the average value of an MSBR core which actually consists of two zones with different ratios. The two-cell method uses two representative unit cells, one for each zone, with each zone having the appropriate fuel-tomoderator ratio. It is demonstrated that the two-cell-based method is able to catch the neutron physics of spectral interaction of the two zones with different neutron energy spectra, whereas the single-cell method cannot accurately predict the breeding ratio nor the resonance escape probability of the MSBR core. A new code system was established using MCNP6/PYTHON script language for modeling of the online reprocessing of molten fuel, and the depletion and online refueling of the MSBR core.

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Section: Resultsmentioning

confidence: 99%

Section: Four Factor Analysismentioning

confidence: 91%

Section: Equilibrium Core Analysismentioning

confidence: 97%

Section: Introductionmentioning

confidence: 99%

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Equilibrium core design methods for molten salt breeder reactor based on two-cell model

Jeong

Park

Lee

2015

Journal of Nuclear Science and Technology

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“…The SFR is one of the Generation IV reactor concepts [1][2][3][4][5]. The SFR is one of the Generation IV reactor concepts [1][2][3][4][5].…”

Section: Introductionmentioning

confidence: 99%

Design study of long-life small modular sodium-cooled fast reactor

Park

Tak

Kim

et al. 2016

Int. J. Energy Res.

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Summary This paper presents a new design for a small modular sodium‐cooled fast reactor core with an optimized lifetime and reactivity swing through the analysis of various breed‐and‐burn strategies and its neutronic analyses in terms of active core movements, isotopic mass balance, kinetic parameters, and inherent safety. The new core design aims at a power level of 260 MW with a long lifetime of 30 years without refueling and a reactivity swing smaller than 1000 pcm. Starting from five initial candidate cores with various breed‐and‐burn strategies, an optimum core was selected from a combination of the two candidates that shows a proper breeding behavior with the optimized uranium enrichment in the low‐enriched uranium region and the optimized size of the blanket region. The depletion analysis of the new core provides various reactor design parameters such as the core multiplication factor, breeding ratio, heavy metal mass change, power distribution, and summary of neutron balance. In addition, the perturbation analysis provides the reactor kinetic parameters and reactivity feedback coefficients for the inherent safety analysis of the core. The integral reactivity parameters of the quasi‐static reactivity balance analysis demonstrate that the new core is inherently safe in cases of unprotected loss of flow, unprotected loss of heat sink, and unprotected transient over power. Copyright © 2016 John Wiley & Sons, Ltd.

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Transient analysis for liquid-fuel molten salt reactor based on MOREL2.0 code

et al. 2017

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SummaryA molten salt reactor (MSR) is characterized by simultaneously using liquid fuel salt as both the nuclear fuel and coolant. The redistribution of delayed neutron precursors (DNPs) makes the transient behavior of MSRs different from traditional solid-fuel reactors. In this study, a 3D coupled neutronics/thermal hydraulics code, MOREL2.0, was employed to analyze a liquid-fuel Thorium Molten Salt Reactor (TMSR-LF) under perturbations of fuel pump start-up and coast-down and by overheating and overcooling the inlet fuel temperature. Some transient processes were simulated to provide guidance for the future design and optimization of TMSR-LFs. In response to the perturbations, reactivity was lost and gained in the pump start-up and coast-down, respectively.Overheating the inlet fuel temperature introduced negative reactivity, and TMSR-LF maintained a safety state, while overcooling the inlet fuel temperature resulted in positive reactivity. Overcooling by 70 K produced a supercritical transient condition and a rapid increase in power within a short period, which was followed by a decrease in power due to negative temperature feedback. The transient results demonstrate that the negative temperature feedback coefficients guarantee TMSR-LF inherent safety and the variation range of temperature stay within the safety margin.

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Whole core analysis of molten salt breeder reactor with online fuel reprocessing

Cited by 18 publications

References 9 publications

Equilibrium core design methods for molten salt breeder reactor based on two-cell model

Equilibrium core design methods for molten salt breeder reactor based on two-cell model

Design study of long-life small modular sodium-cooled fast reactor

Transient analysis for liquid-fuel molten salt reactor based on MOREL2.0 code

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