Conceptual design of reactor system for hybrid micro modular reactor (H-MMR) using potassium heat pipe

Choi, Young Jae; Lee, Seongmin; Jang, Seongdong; Son, In Woo; Kim, Yong Hee; Lee, Jeong Ik; Jeong, Yong Hoon

doi:10.1016/j.nucengdes.2020.110886

Cited by 18 publications

(3 citation statements)

References 9 publications

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“…Figure 2 shows the crosssections of the fuel element (a) and heat pipe (b). Both the operation temperatures of UN fuel and Li heat pipe in the neutroncis calculation are set to 1,600 K. The Li heat pipe can be replaced during long-term continuous reactor operation due to its high-temperature life limit (Rosenfeld et al, 2004;Choi et al, 2020). The 1,008 fuel elements are surrounded by the axial and radius reflectors to keep the criticality of the reactor.…”

Section: Model Descriptionmentioning

confidence: 99%

“…Based on the eVinci-like heat pipe cooled reactor, Hernandez et al (2019) found that the neutron leakage impact for the small-sized heat pipe reactor is the most limiting factor on the fuel cycle performance. To improve the lifetime of the reactor, the KAIST (Choi et al, 2020) proposed an 18 MW th H-MMR with UN fuel, which provides continuous operation for about 56 years in the case of 12.1% 235 U enrichment. In addition, Ehud (2008) proposed a 125 MWth HP-ENHS core, which can achieve at least 20 years of core lifetime by loading the depleted uranium and TRUs.…”

Section: Introductionmentioning

confidence: 99%

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Analysis of Th and U breeding in a heat pipe cooled traveling wave reactor

2023

Front. Energy Res.

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Introduction: Heat pipe cooled traveling wave reactor (HPTWR) is a newly proposed heat pipe reactor. The HPTWR can achieve the low enrichment of loaded fuel, small reactivity swing, and long-term continuous operation for the power supply of decentralized electricity markets. Due to the excellent breeding capability of the HPTWR, the Th fuel is also added into the breeding fuel region of the reactor to achieve the Th-U fuel cycle in this work.Methods: The Monte Carlo code RMC is used to obtain the reactivity swing, propagation of axial power peak, burnup, and productions of bred fissile nuclides for the HPTWR with Th and U fuels.Results and Discussion: The results indicate that the HPTWR with 13.6% 235U enrichment of ignition fuel and 20% 235U enrichment of breeding fuel can continuously operate for 18.1 years without refueling when the mass fraction of 232Th in heavy metals of breeding fuel region is 33%. The propagation velocity of axial power peak and total burnup for the HPTWR with Th and U fuels is about 0.5525 cm/years and 24.72 GWd/THM during the 18.1 years operation respectively. The corresponding productions of bred 239Pu, 241Pu and 233U are about 212.99 kg of 239Pu, 0.19 kg of 241Pu and 81.58 kg of 233U at the end of cycle (EOC) respectively. The obtained results in this study demonstrate that the HPTWR can achieve the Th fuel breeding in the case of the low 235U enrichment loading (≤ 20%).

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Section: Model Descriptionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Analysis of Th and U breeding in a heat pipe cooled traveling wave reactor

2023

Front. Energy Res.

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“…In Korea, a Hybrid micro modular reactor, which combined the capabilities of renewable energy and energy storage systems, had been designed utilizing potassium HP technology (Choi et al, 2020). The H-MMR offered increased flexibility and efficiency in electricity and thermal generation, capable of producing 10 MWe and 18 MWt through load following strategies.…”

Section: Hpcr Studies In Other Countriesmentioning

confidence: 99%

Review of reactor conceptual design and thermal hydraulic characteristics for heat pipe in nuclear systems

Wang,

Ren,

2023

Front. Energy Res.

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Heat pipe cooled reactors (HPCRs) have broad application prospects due to their advantages, such as high power density, compact structure, lower cost, and easy modular assembly. Numerous countries have engaged in extensive research and development of HPCR conceptual designs. The heat from the reactor is removed by high temperature heat pipes (HTHPs), which generally employ alkali metals as the working fluid, such as potassium, sodium, and lithium. Understanding the thermal-hydraulic performance of HTHPs is essential for the safe and efficient operation of a reactor. Therefore, the objective of this paper is to provide a comprehensive review of HPCR conceptual designs developed by various countries in recent years. The research progress of HTHPs on flow and heat transfer performance is reviewed, with an emphasis on both transient and steady-state characteristics. Research progress, as well as the issues that need to be focused on in future research, are discussed in detail.

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Numerical Study of Influence of 15N Enrichment on Burnup Performances for a Heat Pipe Cooled Traveling Wave Reactor

2023

Springer Proceedings in Physics

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Conceptual design of reactor system for hybrid micro modular reactor (H-MMR) using potassium heat pipe

Cited by 18 publications

References 9 publications

Analysis of Th and U breeding in a heat pipe cooled traveling wave reactor

Analysis of Th and U breeding in a heat pipe cooled traveling wave reactor

Review of reactor conceptual design and thermal hydraulic characteristics for heat pipe in nuclear systems

Numerical Study of Influence of 15N Enrichment on Burnup Performances for a Heat Pipe Cooled Traveling Wave Reactor

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