Analysis and Research of Release Behavior on Fission Product of Dispersion Fuel
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摘要: 为了获得弥散型燃料裂变产物向一回路冷却剂的释放特性，开展了弥散型燃料裂变产物释放行为研究，开发了适用于弥散型燃料的裂变产物源项计算程序，并对裂变产物源项进行了影响分析。结果表明：沾污铀和起泡破损后裂变产物的核素谱存在一定差异；裂变产物的释放与起泡当量直径的平方成正比；对于弥散型燃料而言，起泡破损中通过反冲释放的占比较低；相同破口条件下的弥散型和陶瓷型燃料中裂变产物的释放存在量级的差别。本文开发的程序能够用于分析弥散型燃料的裂变产物源项，为后续相关研究工程设计奠定基础。Abstract: In order to obtain the release characteristics of fission products from dispersion fuel to coolant in the primary loop, the release behavior of fission products from dispersion fuel has been studied, a fission product source term calculation code for dispersion fuel is developed, and the influence of fission product source term is analyzed. The results indicate that the nuclide spectra of fission products after uranium contamination and blistering damage are different; and the release of fission products is proportional to the square of the blister equivalent diameter; and for the dispersion fuel, the proportion of release through recoil in blistering damage is fairly low; and there is a difference in the order of magnitude of fission product release between the dispersion fuel and the ceramic fuel under the same fracture condition. The code developed in this paper can be used to analyze the fission product source term of dispersion fuel, and lay the foundation for the engineering design of follow-up projects.
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Key words:
- Dispersion fuel /
- Fission product source term /
- Blistering damage
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图 1 射出概率求解示意图
r—裂变产物的最大出射距离；$ \beta $—裂变产物的最大出射角；$ \theta $—裂变产物最大出射角的余角
Figure 1. Schematic Diagram of Solving the Injection Probability
图 3 沾污铀和起泡破损引起的裂变产物源项核素谱分布
Figure 3. Nuclide Spectrum Distribution of Fission Product Source Term Caused by Uranium Contamination and Blistering Damage
图 4 不同类型燃料破损后的裂变产物源项分布
Figure 4. Fission Product Spurce Terms Distribution after Damage of Different Fuel Types
表 1 不同起泡当量直径下释放到一回路冷却剂中的裂变产物源项
Table 1. Fission Product Source Terms Released into Coolant in Primary Loop under Different Equivalent Diameters of Blistering Damage
核素名称 放射性比活度/(MBq·t−1) 0.1 mm 0.5 mm 1 mm 5 mm 85Krm 9.2×10−5 2.3×10−3 9.2×10−3 2.3×10−1 85Kr 2.0×10−5 5.1×10−4 2.0×10−3 5.1×10−2 87Kr 9.3×10−5 2.3×10−3 9.3×10−3 2.3×10−1 88Kr 2.0×10−4 4.9×10−3 2.0×10−2 4.9×10−1 133Xem 5.6×10−5 1.4×10−3 5.6×10−3 1.4×10−1 133Xe 2.6×10−3 6.5×10−2 2.6×10−1 6.5 135Xe 8.3×10−4 2.1×10−2 8.3×10−2 2.1 138Xe 9.2×10−5 2.3×10−3 9.2×10−3 2.3×10−1 131I 5.9×10−5 1.5×10−3 5.9×10−3 1.5×10−1 132I 1.9×10−4 4.7×10−3 1.9×10−2 4.7×10−1 133I 2.5×10−4 6.2×10−3 2.5×10−2 6.2×10−1 134I 2.0×10−5 5.1×10−4 2.0×10−3 5.1×10−2 135I 1.5×10−4 3.7×10−3 1.5×10−2 3.7×10−1 134Cs 4.0×10−8 9.9×10−7 4.0×10−6 9.9×10−5 136Cs 5.8×10−7 1.5×10−5 5.8×10−5 1.5×10−3 137Cs 2.4×10−6 6.0×10−5 2.4×10−4 6.0×10−3 138Cs 9.3×10−5 2.3×10−3 9.3×10−3 2.3×10−1 
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表 2 裂变产物源项的反冲释放占比
Table 2. Proportion of Release through Recoil in Fission Product Source Terms
核素名称 裂变产物比活度/（MBq·t−1） 反冲占比/% 不考虑反冲作用 考虑反冲作用 85Krm 1.6 1.8 13.00 85Kr 8.4×10−1 8.5×10−1 1.20 87Kr 3.3 3.8 13.30 88Kr 4.4 5.1 13.10 133Xem 2.5×10−1 2.8×10−1 11.00 133Xe 1.0×101 1.1×101 9.80 135Xe 7.5 8.6 12.60 138Xe 9.0 1.1×101 14.90 131I 2.3×10−1 2.5×10−1 9.40 132I 2.2 2.5 12.80 133I 1.9 2.2 12.40 134I 8.3×10−1 9.6×10−1 13.10 135I 2.0 2.3 12.90 134Cs 1.2×10−3 1.2×10−3 0 136Cs 3.0×10−3 3.1×10−3 5.20 137Cs 1.8×10−2 1.8×10−2 2.40 138Cs 9.0 1.1×101 14.90
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