Preliminary conceptual design and neutroncis analysis of a heat pipe cooled traveling wave reactor

Ma, Kunfeng; Hu, Pan

doi:10.1016/j.anucene.2021.108907

Cited by 13 publications

(3 citation statements)

References 32 publications

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“…The HPTWR is a heat pipe cooled reactor with 65.5 MW th , which has a total of 1,008 heat pipe fuel elements with ignition and breeding fuel regions (Ma and Hu, 2022). A central heat pipe in each fuel element is surrounded by a uranium nitride (UN) fuel pellet with cladding on both radial sides of the pellet (inner and outer claddings) (Sterbentz et al, 2018).…”

Section: Model Descriptionmentioning

confidence: 99%

“…Thus, the application of the neutron traveling wave in the heat pipe reactor can reduce the enrichment of fuel and extend the lifetime of the core. The neutron breeding traveling wave has been applied in the heat pipe cooled reactor in our previous work (Ma and Hu, 2022). Figure 1 shows the burnup strategy of the heat pipe cooled traveling wave reactor (HPTWR) power source, which consists of a reactor, shield, and heat exchanger.…”

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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“…At the end of the cycle, the temperature peak reached approximately 1784.6 K. This reduction in thermal stress enhanced the safety of the HP wall. Additionally, the study proposed a design for a 65.5 MWt HPTWR (Ma and Hu, 2022). The HPTWR design incorporated an ignition fuel with 14% enrichment and a breeding fuel with 8.5% enrichment.…”

Section: Chinese Hpcr Researchmentioning

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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Preliminary conceptual design and neutroncis analysis of a heat pipe cooled traveling wave reactor

Cited by 13 publications

References 32 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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