Development and Validated Application of Calculation Function of High Fidelity Refueling Cycle for Pressurized Water Reactor
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摘要: 在自主开发的数值反应堆物理计算程序NECP-X基础上开发了压水堆的换料循环计算功能，并针对某M310机组首循环、第2循环和第3循环的启动物理实验，以及针对前2个循环的燃耗进行了精细建模计算。计算值与实测值的比较结果表明：首循环、第2循环和第3循环启动物理实验的临界硼浓度、控制棒价值、温度系数计算结果误差均较小，符合验收准则；不同燃耗深度下的临界硼浓度、堆芯功率分布与实测值的比较结果显示，稳定燃耗点处最大硼浓度偏差为−39ppm（1ppm=10−6），最大的组件功率误差小于4.5%，随着燃耗的加深，堆芯功率的分布逐渐展平，误差逐渐减小。计算结果表明NECP-X程序已经具备商用压水堆启动物理实验和多燃料循环的计算能力。Abstract: The refueling cycle calculation function for pressurized water reactor (PWR) is developed on the basis of the self-developed numerical nuclear reactor physics calculation code NECP-X. Startup physics experiments are conducted for the first, second and third cycles of an M310 reactor, and fine modeling calculation is carried out for the first two cycles. By comparing the calculated values with the measured values, it shows that the errors of calculation results of critical boron concentration, control rod worth and temperature coefficient in the startup physics experiments for the first, second and third cycles are relatively small, which meet the acceptance criteria. The results of comparison of the critical boron concentration and core power distribution with the measured values at different burnup levels show that the maximum boron concentration deviation at the stable burnup point is −39ppm (1ppm = 10−6), and the maximum assembly power error is less than 4.5%. With the increase of burnup level, the core power distribution flattens out and the error decreases gradually. The calculation results show that NECP-X already has the calculation function for the startup physics experiments and multi-fuel cycle of commercial PWRs.
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Key words:
- Numerical reactor /
- NECP-X /
- Multi-cycle refueling /
- Large PWR validation
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图 3 M310压水堆首循环径向功率偏差分布 %
Figure 3. M310 PWR First-cycle Radial Power Deviation Distribution
图 4 M310压水堆首循环冷却剂温度分布
Figure 4. M310 PWR First-cycle Moderator Temperature Distribution
表 1 临界硼浓度计算结果
Table 1. Critical Boron Concentration Calculation Results
工况 计算值与实测值偏差/ppm 验收准则/ppm Rin 5.96 ±50 RG1in 1.10 ARO 8.58 
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表 2 控制棒价值计算结果
Table 2. Control Rod Worth Calculation Results
控制棒组 计算值与实测值相对偏差/% 验收准则/% R 2.4 ±10 G1 3.7 G2 3.5 SB −4.0 SC 4.6
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表 3 等温温度系数计算结果
Table 3. Isothermal Temperature Coefficient Calculation Results
工况 计算值与实测值偏差/(pcm·K−1) 验收准则/(pcm·K−1) ARO −2.1 ±3.6 Rin −1.3 RG1in −2.4
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表 4 临界硼浓度和反应性温度系数计算结果
Table 4. Critical Boron Concentration and Reactivity Temperature Coefficient Calculation Results
参数 计算值与实测值偏差 ARO临界硼浓度/ppm 35 ARO等温温度系数/(pcm·K−1) −0.143
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表 5 控制棒价值计算结果
Table 5. Control Rod Worth Calculation Results
控制棒组 计算值与实测值相对偏差/% R −1.7 N2 −3.4 SA 1.6 G1 0 G2 7.2 N1 3.8 SB −3.4 SC 8.2 SD −0.6
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表 6 AO、FΔh、Fq计算结果
Table 6. AO, FΔh and Fq Calculation Results
EFPD AO计算值与实测
值的偏差/%①FΔh计算值与实测
值的偏差Fq计算值与实测
值的偏差172 −0.13 0.01 0.10 229 1.99 0.01 0.04 258 1.88 0.01 0.04 289 2.33 0.02 0.04 注：①AO值为相对值，即：（堆芯上半部分功率−下半部分功率）/总功率
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表 7 控制棒价值计算结果
Table 7. Control Rod Worth Results
控制棒组 计算值与实测值相对偏差/% 验收准则/% R 2.78 ±10 N2 −6.80 SA 0.76 G1 4.40 G2 3.17 N1 6.81 SB −1.23 SC 7.53 SD 8.30
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