Passive compact molten salt reactor (PCMSR), modular thermal breeder reactor with totally passive safety system

Harto, Andang Widi

doi:10.1063/1.4725441

Cited by 5 publications

(7 citation statements)

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“…Another thermal breeder MSR design is the Passive Compact Molten Salt Reactor (PCMSR). It is currently being developed in Universitas Gadjah Mada, Indonesia [17][18][19], and designed to possess a passive safety system with a compact modular design. it differs from other thermal breeder MSR designs in terms of integral module concept, higher operating temperature, and thermal efficiency, among others [17].…”

Section: Introduction mentioning

confidence: 99%

“…It is currently being developed in Universitas Gadjah Mada, Indonesia [17][18][19], and designed to possess a passive safety system with a compact modular design. it differs from other thermal breeder MSR designs in terms of integral module concept, higher operating temperature, and thermal efficiency, among others [17]. PCMSR refers more to a whole reactor module rather than the core design; thus, PCMSR can use one fluid or two fluid-core.…”

Section: Introduction mentioning

confidence: 99%

“…A design study has previously been performed for one fluid PCMSR using deterministic code SRAC2006 [17]. The result implied that the core design can achieve thermal breeding with a negative temperature coefficient of reactivity.…”

Section: Introduction mentioning

confidence: 99%

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Model Comparison of Passive Compact-Molten Salt Reactor Neutronic Design Using MCNP6 and Serpent-2

et al. 2021

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Passive Compact Molten Salt Reactor (PCMSR) is a thermal breeder molten salt reactor (MSR) developed in Universitas Gadjah Mada, Indonesia, run in thorium fuel cycle. Its design was initially developed using deterministic code SRAC2006 but has never been compared with other codes. This paper attempts to compare PCMSR neutronic design using Monte Carlo codes MCNP6 and Serpent-2 with ENDF B/VII.0 continuous neutron cross-section library. The reactor was run in a pure thorium fuel cycle with lithium fluoride as its carrier salt. The analyzed parameters were effective multiplication factor (k eff ), temperature coefficient of reactivity (TCR), void coefficient of reactivity (VCR), and conversion ratio (CR). The result shows that there are several important discrepancies between the original calculation and this research. The Monte Carlo calculations implied that PCMSR core was able to be critical using lower fissile concentration than previously designed, but failed to reach CR above unity. While the TCR value was found to be negative, the VCR value was positive up until the 10 % void fraction. The PCMSR core suffered from ineffective neutron moderation and high neutron leakage. These findings imply that the previous PCMSR neutronic design is inaccurate. For PCMSR to be able to operate as a thermal breeder MSR, geometrical modifications must be performed to improve neutron moderation and reduce neutron leakage.

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Section: Introduction mentioning

confidence: 99%

Section: Introduction mentioning

confidence: 99%

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Model Comparison of Passive Compact-Molten Salt Reactor Neutronic Design Using MCNP6 and Serpent-2

et al. 2021

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“…The scattering law should take two parts into consideration: solid and liquid type law. Then the neutron scattering from liquids could be represented by using a solid type spectrum of rotational and vibrational modes combined with a diffusion term, corresponding to S s (α,β) and S t (α,β), see Equation (4). The expression S s (α,β) in Equation (5) could be calculated by inputting frequency spectrum ρ s (β) and relevant weight w s ; S t (α,β) in Equation (8) is given by Egelstaff-Schofield effective width mode [12], which could be computed by input the self-diffusion coefficient c and translational weight w t , respectively.…”

Section: General Description For Thermal Neutron Scattering Of Liquidmentioning

confidence: 99%

“…After the Fukushima accident, 1 nuclear safety widely entered the public domain once more, and nuclear policy was impacted greatly all over the world, which brought unexpected attention to MSR. Molten salt reactor, the unique liquid fuel reactor in generation IV nuclear energy systems, has intrinsic safety [3,4]. It is also the best candidate for thorium utilization [5] and online processing [6].…”

Section: Introductionmentioning

confidence: 99%

The investigation of thermal neutron scattering data for molten salt Flibe

Mei

Xiang-Zhou

Jiang

et al. 2013

Journal of Nuclear Science and Technology

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Based on the dynamics of Flibe (2LiF-BeF 2 ), the thermal neutron scattering library (TSL) is generated by NJOY in this paper. We worked on the TSL data through the microscopic analysis. With the increas of temperature and translational weight of liquid Flibe, the inelastic scattering cross section decreases and the average energy of secondary neutron increases. Using TSL of Flibe, the critical calculation for molten salt reactor is also conducted by MCNP. Result shows the k eff is influenced by thermal neutron scattering obviously (about 0.8%). It is suggested that thermal neutron data should be taken into account in molten salt reactor.

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149Sm evolution behavior in a small modular molten salt reactor

Chen

et al. 2018

Annals of Nuclear Energy

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Passive compact molten salt reactor (PCMSR), modular thermal breeder reactor with totally passive safety system

Cited by 5 publications

References 0 publications

Model Comparison of Passive Compact-Molten Salt Reactor Neutronic Design Using MCNP6 and Serpent-2

Model Comparison of Passive Compact-Molten Salt Reactor Neutronic Design Using MCNP6 and Serpent-2

The investigation of thermal neutron scattering data for molten salt Flibe

149Sm evolution behavior in a small modular molten salt reactor

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