Abstract To establish the exclusive role of hydrogen on burst behaviour of Zircaloy-4 during loss-of-coolant accident transients, an extensive single-rod burst tests were conducted on both unirradiated as-received and hydrogenated Zircaloy-4 cladding tubes at different heating rates and internal overpressures. The visual observations of cladding tubes during bursting as well as post-burst are presented in detail to understand the effect of hydrogen concentration, heating rate, and internal pressure. Impact of hydrogen on burst parameters—burst stress, burst strain, burst temperature—during loss-of-coolant accident transients are compared and discussed. Rupture at multiple locations for hydrogenated cladding at lower internal pressure and higher heating rate is reported for the very first time. A novel burst criterion accounting hydrogen concentration in nuclear fuel cladding is proposed.

中文翻译：

---

在冷却剂丢失事故中氢气对 Zircaloy-4 核燃料包壳破裂行为的影响：多位置失效的新观察

摘要 为了确定氢气对 Zircaloy-4 在冷却剂丢失事故瞬变过程中的爆裂行为的唯一作用，在不同加热速率下对未经辐照的原样和氢化 Zircaloy-4 包壳管进行了广泛的单棒爆裂试验。和内部超压。详细介绍了包层管在爆裂和爆裂后的视觉观察，以了解氢浓度、加热速率和内部压力的影响。比较和讨论了在冷却剂损失事故瞬变期间氢气对爆裂参数（爆裂应力、爆裂应变、爆裂温度）的影响。首次报道了在较低内部压力和较高加热速率下氢化包层在多个位置的破裂。