Riccardo Boccelli , Andrea D’Ottavio , Stefano Lorenzi , Angelica Peressotti , Maria Antonietta Perino , Marco Enrico Ricotti , Lorenzo Tutolo
{"title":"用于空间应用的200kwt高浓铀燃料热管反应堆的初步设计和中子特性","authors":"Riccardo Boccelli , Andrea D’Ottavio , Stefano Lorenzi , Angelica Peressotti , Maria Antonietta Perino , Marco Enrico Ricotti , Lorenzo Tutolo","doi":"10.1016/j.nucengdes.2025.114521","DOIUrl":null,"url":null,"abstract":"<div><div>Nuclear reactors represent a key technology for advancing space exploration and utilisation, providing a reliable, continuous, and environmentally independent energy source essential for long-duration missions beyond Earth. This capability is crucial for ensuring uninterrupted operation of spacecraft systems, sustaining lunar habitats, and supporting energy-intensive scientific experiments. Nuclear energy, particularly fission, is renowned for its high energy density and reliability, making it a key element in the design of space missions where mass minimisation is a critical requirement for feasibility and economic viability. While designs like KRUSTY have demonstrated compactness and simplicity, it is desirable to develop reactors with higher power levels, lower enrichment, and compatibility with non-proliferation concepts.</div><div>The objective of this work is to propose a preliminary design for a heat-pipe reactor conceived for both lunar surface applications and low-power electric propulsion and to conduct a comprehensive neutronic analysis. The proposed reactor combines the simplicity of a KRUSTY-type reactor with increased power to 200 kWt (40-50 kWe assuming 20%–25% conversion efficiency) and reduced enrichment (from HEU to HALEU). The preliminary design is characterised by an epithermal spectrum, a nominal operating temperature between 1000 K and 1100 K, and has a mass of 1139 kg, resulting in a specific power of 176 Wt/kg. A neutronic analysis was performed to characterise the reactor, extracting information such as power and flux distributions, feedback coefficients, reactivity control, burnup, and addressing safety aspects, demonstrating that the reactor maintains sufficient reactivity margin under certain accidental criticality condition. All the criticality calculations were performed using OpenMC Monte Carlo code.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"445 ","pages":"Article 114521"},"PeriodicalIF":2.1000,"publicationDate":"2025-10-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Preliminary design and neutronic characterisation of a 200 kWt HALEU fueled heat-pipe reactor for space applications\",\"authors\":\"Riccardo Boccelli , Andrea D’Ottavio , Stefano Lorenzi , Angelica Peressotti , Maria Antonietta Perino , Marco Enrico Ricotti , Lorenzo Tutolo\",\"doi\":\"10.1016/j.nucengdes.2025.114521\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>Nuclear reactors represent a key technology for advancing space exploration and utilisation, providing a reliable, continuous, and environmentally independent energy source essential for long-duration missions beyond Earth. This capability is crucial for ensuring uninterrupted operation of spacecraft systems, sustaining lunar habitats, and supporting energy-intensive scientific experiments. Nuclear energy, particularly fission, is renowned for its high energy density and reliability, making it a key element in the design of space missions where mass minimisation is a critical requirement for feasibility and economic viability. While designs like KRUSTY have demonstrated compactness and simplicity, it is desirable to develop reactors with higher power levels, lower enrichment, and compatibility with non-proliferation concepts.</div><div>The objective of this work is to propose a preliminary design for a heat-pipe reactor conceived for both lunar surface applications and low-power electric propulsion and to conduct a comprehensive neutronic analysis. The proposed reactor combines the simplicity of a KRUSTY-type reactor with increased power to 200 kWt (40-50 kWe assuming 20%–25% conversion efficiency) and reduced enrichment (from HEU to HALEU). The preliminary design is characterised by an epithermal spectrum, a nominal operating temperature between 1000 K and 1100 K, and has a mass of 1139 kg, resulting in a specific power of 176 Wt/kg. A neutronic analysis was performed to characterise the reactor, extracting information such as power and flux distributions, feedback coefficients, reactivity control, burnup, and addressing safety aspects, demonstrating that the reactor maintains sufficient reactivity margin under certain accidental criticality condition. All the criticality calculations were performed using OpenMC Monte Carlo code.</div></div>\",\"PeriodicalId\":19170,\"journal\":{\"name\":\"Nuclear Engineering and Design\",\"volume\":\"445 \",\"pages\":\"Article 114521\"},\"PeriodicalIF\":2.1000,\"publicationDate\":\"2025-10-11\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Nuclear Engineering and Design\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S0029549325006983\",\"RegionNum\":3,\"RegionCategory\":\"工程技术\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q1\",\"JCRName\":\"NUCLEAR SCIENCE & TECHNOLOGY\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0029549325006983","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
Preliminary design and neutronic characterisation of a 200 kWt HALEU fueled heat-pipe reactor for space applications
Nuclear reactors represent a key technology for advancing space exploration and utilisation, providing a reliable, continuous, and environmentally independent energy source essential for long-duration missions beyond Earth. This capability is crucial for ensuring uninterrupted operation of spacecraft systems, sustaining lunar habitats, and supporting energy-intensive scientific experiments. Nuclear energy, particularly fission, is renowned for its high energy density and reliability, making it a key element in the design of space missions where mass minimisation is a critical requirement for feasibility and economic viability. While designs like KRUSTY have demonstrated compactness and simplicity, it is desirable to develop reactors with higher power levels, lower enrichment, and compatibility with non-proliferation concepts.
The objective of this work is to propose a preliminary design for a heat-pipe reactor conceived for both lunar surface applications and low-power electric propulsion and to conduct a comprehensive neutronic analysis. The proposed reactor combines the simplicity of a KRUSTY-type reactor with increased power to 200 kWt (40-50 kWe assuming 20%–25% conversion efficiency) and reduced enrichment (from HEU to HALEU). The preliminary design is characterised by an epithermal spectrum, a nominal operating temperature between 1000 K and 1100 K, and has a mass of 1139 kg, resulting in a specific power of 176 Wt/kg. A neutronic analysis was performed to characterise the reactor, extracting information such as power and flux distributions, feedback coefficients, reactivity control, burnup, and addressing safety aspects, demonstrating that the reactor maintains sufficient reactivity margin under certain accidental criticality condition. All the criticality calculations were performed using OpenMC Monte Carlo code.
期刊介绍:
Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology.
Fundamentals of Reactor Design include:
• Thermal-Hydraulics and Core Physics
• Safety Analysis, Risk Assessment (PSA)
• Structural and Mechanical Engineering
• Materials Science
• Fuel Behavior and Design
• Structural Plant Design
• Engineering of Reactor Components
• Experiments
Aspects beyond fundamentals of Reactor Design covered:
• Accident Mitigation Measures
• Reactor Control Systems
• Licensing Issues
• Safeguard Engineering
• Economy of Plants
• Reprocessing / Waste Disposal
• Applications of Nuclear Energy
• Maintenance
• Decommissioning
Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.