본문 바로가기
KERD
논문KCI 등재

Preliminary neutronics design and analysis of lithium heat pipe cooled space reactor with low-enriched uranium

3

조회

0

다운로드

0

인용

0

참고문헌

키워드

주제분류원자력공학

초록

The space nuclear reactor cooled by heat pipes has become the preferred choice for future space missions and deep space exploration missions. The use of low-enriched uranium (LEU) is promoted to achieve the goal of nuclear non-proliferation worldwide. In this study, a lithium heat pipe cooled space reactor with LEU (HP-LEU) was proposed based on Heat Pipes-Segmented Thermoelectric Module Converters (HP-STMCs), with the addition of moderators. The HP-LEU employs yttrium hydride (YH2) as the moderator and 19.9 % enriched uranium nitride (UN) as the fuel. The neutronics analysis has been performed on the HP-LEU reactor and the results have showed that the HP-LEU has a lifetime of more than 12 years. Two control systems have been applied in the reactor and have demonstrated the capacity to independently regulate and shut down the reactor. The total temperature reactivity coefficients are consistently negative, indicating that the HP-LEU reactor is inherently safe during operation. During normal operation, the temperatures of the materials are all acceptable. This study can serve as a reference for lithium heat pipe cooled space reactors with LEU.

Abstract

The space nuclear reactor cooled by heat pipes has become the preferred choice for future space missions and deep space exploration missions. The use of low-enriched uranium (LEU) is promoted to achieve the goal of nuclear non-proliferation worldwide. In this study, a lithium heat pipe cooled space reactor with LEU (HP-LEU) was proposed based on Heat Pipes-Segmented Thermoelectric Module Converters (HP-STMCs), with the addition of moderators. The HP-LEU employs yttrium hydride (YH2) as the moderator and 19.9 % enriched uranium nitride (UN) as the fuel. The neutronics analysis has been performed on the HP-LEU reactor and the results have showed that the HP-LEU has a lifetime of more than 12 years. Two control systems have been applied in the reactor and have demonstrated the capacity to independently regulate and shut down the reactor. The total temperature reactivity coefficients are consistently negative, indicating that the HP-LEU reactor is inherently safe during operation. During normal operation, the temperatures of the materials are all acceptable. This study can serve as a reference for lithium heat pipe cooled space reactors with LEU.

참고문헌 (26)

  1. "NASA technology roadmaps-TA3, space power and energy Storage, NASA technical report" (2015)[URL]
  2. The Role of Nuclear Power and Nuclear Propulsion in the Peaceful Exploration of Space, "Stanculescu", IAEA, ~ (2005)
  3. B. H. Yan, "The technology of micro heat pipe cooled reactor : a review", Ann. Nucl. Energy, 135, pp.106948~ (2020)[DOI]
  4. M. A. Gibson, "NASA’s Kilopower Reactor Development and the Path to Higher Power Missions", 2017 IEEE aerospace conference. IEEE, pp.1~14 (2017)
  5. M. S. El-Genk, "“SAIRS”-Scalable amtec integrated reactor space power system", Prog. Nucl. Energy, 45(1), pp.25~69 (2004)[DOI]
  6. M. S. El-Genk, "Space nuclear reactor power system concepts with static and dynamic energy conversion", Energy Convers. Manag, 49(3), pp.402~411 (2008)[DOI]
  7. M. S. El-Genk, "Space reactor power systems with no single point failures", Nucl. Eng. Des, 238(9), pp.2245~2255 (2008)[DOI]
  8. M. S. El-Genk, "Conceptual design of HP-STMCs space reactor power system for 110 kWe", AIP Conference Proceedings. American Institute of Physics, 699(1), pp.658~672 (2004)
  9. J. M. Tournier, "Reactor lithium heat pipes for HP-STMCs space reactor power system", AIP conference proceedings. American Institute of Physics, 699(1), pp.781~792 (2004)
  10. J. C. King, "A methodology for the neutronics design of space nuclear reactors", AIP Conference Proceedings. American Institute of Physics, 699(1), pp.319~329 (2004)
  11. Y. H. Fan, "Conceptual design and feasibility analysis of a heat pipe cooled cermet fuel space nuclear reactor for mars surface application", Prog. Nucl. Energy, 171, pp.105156~ (2024)[DOI]
  12. C. Chen, "Neutronics analysis of a 200 kWe space nuclear reactor with an integrated honeycomb core design", Nucl. Eng. Technol, 54(12), pp.4743~4750 (2022)[DOI]
  13. W. W. Zhang, "Conceptual design and analysis of a megawatt power level heat pipe cooled space reactor power system", Ann. Nucl. Energy, 144, pp.107576~ (2020)[DOI]
  14. B. Lal, "Trade-offs between space nuclear systems fueled with highly enriched uranium and low-enriched uranium", Nucl. Technol, 207(6), pp.836~843 (2021)[DOI]
  15. H. C. Lee, "A neutronic feasibility study on a small LEU fueled reactor for space applications", Ann. Nucl. Energy, 77, pp.35~46 (2015)[DOI]
  16. S. H. Choi, "Conceptual core design and neutronics analysis for a space heat pipe reactor using a low enriched uranium fuel", Nucl. Eng. Des, 387, pp.111603~ (2022)[DOI]
  17. Z. H. Wang, "Advance in and prospect of moderator materials for space nuclear reactors", Int. J. Energy Res, 45(8), pp.11493~11509 (2021)[DOI]
  18. K. Wang, "RMC–A Monte Carlo code for reactor core analysis", Ann. Nucl. Energy, 82, pp.121~129 (2015)[DOI]
  19. L. Zheng, "Criticality benchmarking of ENDF", B-VIII. 0 and JEFF-3. 3 neutron data libraries with RMC code, 2020, pp.52(9), 1917~1925
  20. S. C. Liu, "Development of on-the-fly temperature-dependent cross-sections treatment in RMC code", Ann. Nucl. Energy, 94, pp.144~149 (2016)[DOI]
  21. S. C. Liu, "On-the-fly treatment of temperature dependent cross sections in the unresolved resonance region in RMC code", Ann. Nucl. Energy, 111, pp.234~241 (2018)[DOI]
  22. D. A. Brown, "ENDF", B-VIII. 0: the 8th major release of the nuclear reaction data library with CIELO-project cross sections, new standards and thermal scattering data, 2018, pp.148, 1~142
  23. L. M. Alawneh, "Conceptual design of a 3 MWth yttrium hydride moderated heat pipe cooled micro reactor", Nucl. Eng. Des, 397, pp.111931~ (2022)[DOI]
  24. B. Szpunar, "Thermal conductivity of uranium nitride and carbide", International Journal of Nuclear Energy (2014)[DOI]
  25. B. J. Ade, "Reactor physics considerations for use of yttrium hydride moderator", Nucl. Sci. Eng, 196(12), pp.1539~1558 (2022)[DOI]
  26. "Moderator Considerations for Space Nuclear Power and Propulsion Systems, Nuclear and Emerging Technologies for Space 2021" (2021)[URL]

관련 논문AI추천

이 간행물의 다른 논문 (49건)