Preliminary Study on Conceptual Design of Lead-based Fully Ceramic Microencapsulated Dispersion Fuel Core
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摘要: 为了充分利用全陶瓷微封装弥散燃料(FCM)的耐事故特性,进一步提高铅基反应堆的安全性,将FCM应用于铅基冷却剂反应堆中,给出了铅基FCM堆芯的初步概念设计,并与传统铅基UO2燃料堆芯在燃料装量、燃料利用率、能谱及反应性等方面进行了对比分析。对比结果表明,FCM对堆芯能谱有少量的慢化效果,同时需采用高富集度UO2燃料核芯以保证堆芯235U装量满足能量输出需求,采用FCM堆芯235U装量较UO2堆芯有相应降低,燃料利用率进一步提高。最后对铅基FCM堆芯布置进行功率展平优化,通过径向FCM相体积分区对堆芯功率进行了展平。计算结果显示,堆芯功率峰因子(FQ)由2.43降低至1.93,堆芯核焓升因子(FDH)由1.79降低至1.33。
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关键词:
- 铅基反应堆 /
- 全陶瓷微封装弥散燃料(FCM) /
- 初步概念设计 /
- 功率展平 /
- 相体积分区
Abstract: In order to make full use of the accident resistance characteristics of fully ceramic microencapsulated (FCM) dispersion fuel and further improve the safety of lead-based reactor, FCM fuel is applied to lead-based coolant reactor, and the preliminary conceptual design of lead-based FCM core is presented, and the fuel loading, fuel utilization, energy spectrum and reactivity of the FCM core are compared with the traditional lead-based UO2 fuel core. The comparison results show that FCM has a little moderating effect on core energy spectrum, and high enrichment UO2 fuel core is needed to ensure that the core 235U loading meets the energy output requirements. The 235U loading of the core using FCM is lower than that of UO2 core, and the fuel utilization rate is further improved. Finally, the power flattening optimization of lead-based FCM core layout is carried out, and the core power is flattened by radial FCM phase volume partition. The calculation results show that the core power peak factor (FQ) is reduced from 2.43 to 1.93, and the core nuclear enthalpy rise factor (FDH) is reduced from 1.79 to 1.33. -
表 1 FCM TRISO 参数
Table 1. Parameters of FCM TRISO
结构参数 尺寸
/μm密度
/(g·cm−3)成分 UO2核芯直径 800 >10.4 U、O原子比1:2 UN核芯直径 13.6(95%孔隙率) U、N原子比1:1 疏松PyC层 50 <1.1 C IPyC层 35 1.9 C SiC层 35 ≥3.18 Si、C原子比1:1 OPyC层 20 1.9 C 总直径 1080 注:PyC—热解碳;IPyC—内部热解碳层;OPyC—外部热解碳层 表 2 SLBR-50-FCM堆芯主要设计参数
Table 2. Main Design Parameters of SLBR-50-FCM Core
参数名 参数值 参数名 参数值 堆芯热功率/MW 50 燃料芯体直径/mm 8.0 堆芯寿期/EFPD 2000 气隙厚度/mm 0.1 燃料有效温度/K 900 包壳厚度/mm 0.6 冷却剂温度/K 700 包壳外直径/mm 9.4 TRISO颗粒相体积/% 42 燃料棒中心距/mm 10.9 235U富集度/% 90 组件中心距/mm 93.5 U装量/kg 659 组件盒内对边距/mm 88.0 235U装量/kg 593 组件盒内外边距/mm 92.0 控制棒吸收体材料 B4C 组件盒厚度/mm 2.0 反射层材料 BeO 组件内燃料棒数目/个 61 包壳材料 不锈钢 堆芯活性区高度/mm 950 冷却剂 铅基 反射层外接圆直径/mm 820 燃料组件数目/个 144 控制棒组件数目/个 18 反射层组件数目/个 48 注:EFPD—有效满功率天 表 3 SLBR-50-FCM与SLBR-50堆芯主要设计参数对比
Table 3. Comparison of Main Design Parameters between SLBR-50-FCM and SLBR-50 Cores
参数 SLBR-50 SLBR-50-FCM 堆芯热功率/MW 50 50 堆芯寿期/EFPD 2000 2000 堆芯寿期初U装量/kg 3862 659 堆芯寿期初235U装量/kg 770 593 堆芯寿期初全提棒keff 1.03720 1.16057 堆芯寿期末全提棒keff 1.00319 1.01734 堆芯全寿期最大FQ 2.06 2.43 堆芯全寿期最大FDH 1.53 1.79 注:keff —堆芯有效增殖因子;FQ—堆芯功率峰因子;FDH—堆芯核焓升因子 表 4 SLBR-50-FCM堆芯优化前后主要设计参数对比
Table 4. Comparison of Main Design Parameters before and after Optimization of SLBR-50-FCM Core
参数名 参数值 优化前 优化后 堆芯热功率/MW 50 50 堆芯寿期/EFPD 2000 2000 堆芯寿期初U装量/kg 659 658 堆芯寿期初235U装量/kg 593 592 堆芯寿期初全提棒kinf 1.16057 1.16020 堆芯寿期末全提棒kinf 1.01734 1.01319 堆芯全寿期最大FQ 2.43 1.93 堆芯全寿期最大FDH 1.79 1.33 -
[1] POWERS J J. Fully ceramic microencapsulated (FCM) replacement fuel for LWRs: ORNL/TM-2013/173[R]. Oak Ridge: Oak Ridge National Laboratory, 2013. [2] TERRANI K A, SNEAD L L, GEHIN J C. Microencapsulated fuel technology for commercial light water and advanced reactor application[J]. Journal of Nuclear Materials, 2012, 427(1-3): 209-224. doi: 10.1016/j.jnucmat.2012.05.021 [3] LI W, CHEN P, LIU Z, et al. Preliminary analysis of ATF concept design by NPIC[C]//Technical Meeting on Accident Tolerant Fuel Concepts for Light Water Reactors. Vienna: IAEA, 2014. [4] LIANG C, JI W, A neutronic feasibility study of the AP1000 design loaded with fully ceramic micro-encapsulated fuel[C]//2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering. Sun Valley: American Nuclear Society, 2013. [5] DAI X, CAO X R, YU S H, et al. Conceptual core design of an innovative small PWR utilizing fully ceramic microencapsulated fuel[J]. Progress in Nuclear Energy, 2014, 75: 63-71. doi: 10.1016/j.pnucene.2014.04.010 [6] ZRODNIKOV A V, CHITAIKIN V I, TOSHINSKII G I, et al. Nuclear power plants based on reactor modules with SVBR-75/100[J]. Atomic Energy, 2001, 91(6): 957-966. doi: 10.1023/A:1014862701400 [7] ZRODNIKOV A V, TOSHINSKY G I, KOMLEV O G, et al. Innovative nuclear technology based on modular multi-purpose lead-bismuth cooled fast reactors[J]. Progress in Nuclear Energy, 2008, 50(2-6): 170-178. doi: 10.1016/j.pnucene.2007.10.025 [8] ZHAO C, LOU L, PENG X J, et al. Application of the spectral-shift effect in the small lead-based reactor SLBR-50[J]. Frontiers in Energy Research, 2021, 9: 756106. doi: 10.3389/fenrg.2021.756106