Research Progress and Development Trend of Accident Tolerant Fuel UN Pellets
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摘要: UN芯块是一种高铀密度、高热导芯块，是一种潜在耐事故燃料芯块。本文从制备工艺和物理性能、环境相容性、辐照性能、芯块-包壳相互作用以及经济性和安全性5个方面对UN芯块研究进展进行了总结。研究结果表明在压水堆中使用UN芯块对提升反应堆安全性利大于弊，总体上有利于促进堆芯事故工况下的安全性，具有降低芯块运行温度、减少事故下储能释放的显著特点，需要解决的主要问题是抗水腐蚀性能差和15N富集成本高，对于提升抗水腐蚀和抗氧化性能的可能解决方案包括掺杂或添加抗氧化成分，高成本问题需要降低15N富集成本。本综述较为全面地总结了UN芯块整体研究进展和发展趋势，对于理解其作为抗耐事故燃料芯块的可行性和存在问题提供参考。Abstract: UN pellet has high uranium density and high thermal conductivity, and is a kind of potential accident tolerant fuel pellet. In this paper, the research progress of UN pellets is summarized from five aspects: preparation process and physical properties, environmental compatibility, irradiation properties, pellet-cladding interaction, economy and safety. The research results show that the advantages of using UN pellets in PWR outweigh the disadvantages, and it is generally beneficial to promote the safety of the reactor under accident conditions. It has the remarkable characteristics of reducing the operating temperature of pellets and reducing the release of energy storage in accidents. The main problems to be solved are poor water corrosion resistance and high cost of 15N enrichment. The possible solutions to improve water corrosion resistance and oxidation resistance include doping or adding antioxidant components, and the high cost problem needs to reduce the cost of 15N enrichment. This review comprehensively summarizes the overall research progress and development trend of UN pellets, and provides reference for understanding its feasibility and existing problems as accident tolerant fuel pellets.
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Key words:
- NU /
- Accident tolerant fuel /
- Research progress
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图 1 碳热还原氮化法制备的UN粉末的扫描电子显微镜（SEM）图片
Figure 1. SEM Images of UN Powder Prepared by Carbothermal Reduction Nitridation Method
图 2 氢化氮化法制备UN粉体的SEM图片
Figure 2. SEM Images of UN Powder Prepared by Hydride-nitridation Method
图 3 UN芯块腐蚀质量损失与温度的关系(UN-UO2芯块作为对比）
Figure 3. Relationship between Corrosion Mass Loss of UN Pellets and Temperature (UN-UO2 Pellet as Comparison)
图 4 低密度（相对密度<84%）和高密度（相对密度>94%）UN芯块的体积肿胀率
Figure 4. Volume Swelling Rates of UN Pellet for Low (Relative Density<84%) and High (Relative Density>94%) Densities
图 5 1923 K时几种燃料芯块自由辐照肿胀率对比图
V燃料芯块—燃料芯块的辐照肿胀；$V_{致密{\mathrm{UO}}_2芯块} $—致密UO2的辐照肿胀
Figure 5. Comparison of Swelling Rates of Several Fuel Pellets under Free Irradiation at 1923 K
图 6 相对密度为85%的UN芯块热蠕变速率和辐照蠕变速率与温度关系（20 MPa气压下，裂变速率为1013 n/（cm3·s））
Figure 6. Thermal and Irradiation Creep Rates of UN Pellets with 85% Relative Density Depending on Temperatures (fission rate is 1013n/(cm3·s) at 20 MPa)
图 7 1923 K下几种高温燃料芯块蠕变速率（σ=5 MPa）的对比图
ε燃料芯块—芯块的蠕变速率；$ \varepsilon _{致密{\mathrm{UO}}_2芯块} $—致密UO2芯块的蠕变速率
Figure 7. Comparison of Creep Rate of Several High-Temperature Fuel Pellets at 1923 K (σ=5 MPa)
图 8 (U, Pu)N燃料元件辐照破裂后的截面图（燃耗为123 MW·d/kg(U, Pu)，最大中心温度为1090℃）
Figure 8. Cross Section of the Ruptured Irradiated (U, Pu)N Fuel Element (Burnup is 123 MW·d/kg(U, Pu), maximum central temperature is 1090℃)
表 1 UN芯块基本物理性能
Table 1. Basic Physical Properties of UN Pellet
参数 属性 热导率/[W·(m·K)−1] $ k = 1.864{e^{ - 2.14P}}{T^{0.361}} $；P的适用范围0~0.2，T的适用范围298~1923 K 热膨胀系数/K−1 $ \alpha = 7.096 \times {10^{ - 6}} + 1.409 \times {10^{ - 9}}T $，T的适用范围298~2523 K 杨氏模量/MPa $ E = 0.258{D^{3.002}}(1 - 2.375 \times {10^{ - 5}}T) $；D的适用范围70~100，T的适用范围298~1473 K 泊松比 $ \upsilon = 1.26 \times {10^{ - 3}}{D^{1.174}} $，D的适用范围70~100 分解温度/K >1800（真空）； >2100（Ar） 熔点/K 3120 比热容/[J·(kg·K)−1] 190（298 K）；260（2000 K） 拉伸强度/MPa 148（测试温度不详） 弯曲强度/MPa 74（293 K）；136（1473 K） 注：k—热导率；P—气孔率；T—温度；α—热膨胀系数；E—杨氏模量；D—理论密度百分数；$ \upsilon $—泊松比 
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表 2 轻水堆燃料芯块与包壳在正常运行、功率跃升、冷却剂丧失事故、全厂断电事故和反应性引入事故时芯块的理想属性
Table 2. Desirable Properties of LWR Fuel Pellets under Normal Operation, Power Ramps, Loss-of-coolant Accident, Station Blackout and Reactivity Insertion Accident
芯块性能 对不同运行工况的影响 正常运行 功率跃升 冷却剂丧失事故 全厂断电事故 反应性引入事故 熔点 ↑ ↑ ↑ ↑ ↑ 热导率 ↑ ↑ ↑ — — 比热容 — — ↑ ↑ ↓ 热膨胀系数 — ↓ — — ↓ 蠕变速率 — ↑ — — — 强度 — ↓ — — ↓ 辐照肿胀 ↓ ↓ ↓ ↓ ↓ 注: ↑表示需要提高的性能；↓表示该性能需要降低；—表示该项性能对该事故工况下不敏感
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