分类： 物理学 >> 核物理学 提交时间： 2025-06-05
Qiu, Mr. Zhichao
zhuang, Dr. kun
Wang, Mr. Xiaoyu
Gao, Mr. Yong
Cao, Mr. Yun
Liu, Mr. Daping
Chen, Dr. Jingen (Nuclear energy)
Wang, Sipeng
摘要： As the key technology of space exploration, space power has always been a research interest of international researchers. A lot of research work has been carried out around the world for the space nuclear reactor using heat pipe, liquid metal and gas cooling method. With the development of molten salt reactor of IV generation reactor system, molten salt dissolving fissile material and acting as a coolant at the same time has become a new cooling scheme, which provides new ideas for the design of space nuclear reactor. In this study, a novel reactor Liquid-Solid Dual-Fuel Space Nuclear Reactor (LSSNR) was preliminarily proposed combining the molten salt fuel and cross-shaped spiral solid fuel for the design goals of 30-year lifetime and active core weight less than 200 kg. Monte Carlo neutron transport code OpenMC based on ENDF/B-VII.1 library was employed for neutronics design in aspect of fuel type, cladding material, reflector material and spectral shift absorber. Then, the thickness of control drum absorber was optimized to meet the requirement of the sufficient shutdown margin, lower solid fuel enrichment, and 30 EFPY operation lifetime. Finally , UC solid fuel with U-235 enrichment of 80.98 wt.% and B4C thickness of 0.75 cm were adopted in LSSNR, and BeO was adopted as reflector and matrix material of control drum. A spectral shift absorber Gd2O3 was used to avoid the sub-critical LSSNR returning to criticality at a launch accident. The keff with control drum rotating innermost position is 0. 954949, and the keff reaches 1.00592 after 30 EFPY operation. The total mass of the active core is 160.65 kg. In addition, the thermal-hydraulic feasibility of LSSNR using cross-shaped spiral fuel was analyzed based on a 4/61 reactor core model. The structure of cross-shaped spiral fuel achieves enhanced heat transfer by generating turbulence, leads to a uniform temperature distribution of the coolant flow field, and reduces local temperature peaks. Based on LSSNR scheme, some neutronic characteristics were analyzed. Results demonstrate that the LSSNR has strongly negative reactivity coefficients due to the thermal expansion of liquid fuel, and the fission gas-induced pressure meets safety requirements. After 100 years of the end of core life, the total radioactivity of reactor core is reduced by 99% and is 7.1305 Ci.
分类： 物理学 >> 核物理学 提交时间： 2025-04-16
摘要： The 2019 edition of the International Reactor Physics Evaluation Project (IRPhEP) Handbook incorporated the Molten Salt Reactor Experiment (MSRE) benchmark, providing keff (effective multiplication factor) values derived from first criticality experiments and control rod worth calculations for multiple nuclear data libraries including ENDF/B-VII.1. This benchmark constitutes the first comprehensive reference case for molten salt reactor physics, having been extensively utilized to assess the consistency and accuracy of Monte Carlo codes and nuclear data libraries in molten salt reactor modeling. Since 2011, the Thorium Molten Salt Reactor (TMSR) nuclear energy system has been under development at the Shanghai Institute of Applied Physics, Chinese Academy of Sciences to facilitate thorium resource utilization. In support of this initiative, the China Nuclear Data Center developed specialized CENDL-TMSR-V1 libraries tailored for thorium-uranium fuel cycles. Nevertheless, the verification status of Chinese nuclear libraries CENDL-3.2 and CENDL-TMSR-V1 in molten salt reactor applications remains unexplored. In this work, a high-fidelity MSRE model was developed using OpenMC, with comparative analyses conducted across four evaluated nuclear data libraries: ENDF/B-VII.1, ENDF/B-VIII.0, CENDL-3.2, and CENDL-TMSR-V1. A systematic evaluation of neutronic parameters was performed, encompassing reactivity coefficients, control rod differential worth, zero-power flux distribution, and 500-day burn-up calculations. Key findings reveal that: The relative deviations in keff between all libraries and IRPhEP benchmark values remain below 300 pcm (0.3% Δk/k). The maximum relative discrepancy in power distribution predictions between CENDL-series libraries and ENDF/B-VII.1 is <2%. The keff deviations during burn-up calculations are maintained within 0.2%/. This study validates the applicability of CENDL-series libraries for molten salt reactor neutronic simulations.
分类： 其他 提交时间： 2025-04-22
摘要： 硼中子俘获治疗（Boron Neutron Capture Therapy, BNCT）是一种结合放射治疗与化学药物治疗的靶向癌症治疗技术，其治疗计划系统（Treatment Planning System, TPS）的性能会影响治疗计划的制定从而影响治疗效果。本研究基于MeVisLab医学影像处理平台，开发了一套模块化的BNCT治疗计划系统，旨在实现治疗计划制定过程的自动化、精确化和可视化。该系统集成了医学影像处理、剂量计算、剂量可视化等基础功能模块，能够高效处理CT、MRI等医学影像数据，并基于蒙特卡罗模拟程序OpenMC进行中子剂量分布计算。借助于OpenMC的高效粒子输运模拟能力，系统能够精确计算粒子与肿瘤组织中的硼-10核反应产生的剂量分布，确保剂量计算的准确性。同时，系统采用了模块化设计方式，这使得算法扩展和用户定制化操作更为灵活，并提供了直观的三维可视化界面，便于医生进行治疗方案的设计与优化。本系统的设计与实现为BNCT的精准治疗提供了可靠的技术支持。
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