Preliminary Conceptual Design of Ultra-high Flux Fast Neutron Test Reactor Core
-
摘要: 针对先进核能系统发展需要,提出了超高通量堆的堆芯概念设计。本文采用板型燃料、正方形燃料组件设计,设置宽流道保证堆芯冷却剂占有较高的体积份额。堆芯采用52 盒燃料组件,设置8盒控制棒组件和较厚的反射层。通过堆芯概念设计方案评价,结果表明堆芯循环长度可达100EFPD(等效满功率天),所提出的超高通量堆的最大中子注量率可达到1.08×1016 cm−2·s−1。Abstract: To meet the development need of advanced nuclear systems, an ultra-high flux reactor (UFR) core design concept is proposed in this paper. In this concept, plate-type fuel and square fuel assembly design is adopted, and a wide flow channel is provided to ensure a high volume share of the core coolant. The core is provided with 52 boxes of fuel assemblies, 8 boxes of control rod assemblies and a thick reflective layer. The results show that the cycle length of the core can reach 100 equivalent full power days (EFPD) by the core conceptual design scheme evaluation. The maximum neutron fluence rate of the proposed ultra-high flux reactor can reach 1.0×1016 cm−2·s−1.
-
表 1 堆芯主要设计参数
Table 1. Main Design Parameters of Reactor Core
参数名 参数值 堆芯热功率/MW 200 235U富集度/% 49 燃料组件数目 52 控制棒组件数目 8 径向反射层外径/cm 300 包壳厚度/cm 0.03 芯体厚度/cm 0.09 相邻板间隙/cm 0.28 对边距/cm 8.17 -
[1] GOLUOGLU S, DODDS H L. Improved neutronics model of the high flux isotope reactor[J]. Nuclear Technology, 1995, 112(1): 142-153. doi: 10.13182/NT95-A15859 [2] FEINBERG S M, KONOBEEVSKII S T, DOLLEZHAL’ N A, et al. The 50 mw research reactor SM[J]. Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology, 1962, 16(11-12): 533-542. doi: 10.1016/0368-3230(62)90168-4 [3] SEREBROV A P. High flux reactor PIK and the associated research program[J]. Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 1989, 284(1): 212-215. [4] DEHART M D, KARRIEM Z, POPE M A, et al. Fuel element design and analysis for potential LEU conversion of the Advanced Test Reactor[J]. Progress in Nuclear Energy, 2018, 104: 117-135. doi: 10.1016/j.pnucene.2017.09.007 [5] SHATILLA Y. A pressure-tube advanced burner test reactor concept[J]. Nuclear Engineering and Design, 2008, 238(1): 102-108. doi: 10.1016/j.nucengdes.2007.07.003 [6] 邓才玉,邱立青,王振东,等. HFETR堆芯及φ63辐照孔道γ释热研究[J]. 核动力工程,2007, 28(6): 97-100. doi: 10.3969/j.issn.0258-0926.2007.06.023 [7] ELISEEV V A, KOROBEYNIKOVA L V, MASLOV P A, et al. ON feasibility of using nitride and metallic fuel in the MBIR reactor core[J]. Nuclear Energy and Technology, 2016, 2(3): 179-182. doi: 10.1016/j.nucet.2016.07.009 [8] HEIDET F, ROGLANS-RIBAS J. Core design activities of the versatile test reactor – conceptual phase[J]. EPJ Web of Conferences, 2021, 247: 01010.