Development of new reactor fuel materials: hydrogenation properties of UThZr alloys and neutron irradiation effects on their hydrides
Development of new reactor fuel materials: hydrogenation properties of UThZr alloys and neutron irradiation effects on their hydrides
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DOI：
10.1016/s0022-3115(97)00058-5
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发表时间：
1997-08
影响因子：
3.1
通讯作者：
Takuya Yamamoto;Hadi Suwamo;H. Kayano;M. Yamawaki
中科院分区：
文献类型：
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作者：
Takuya Yamamoto;Hadi Suwamo;H. Kayano;M. Yamawaki
为开发一种新型的U_Th_Zr混合氢化物燃料，研究了4种U_Th_Zr合金（U：Th：Zr = 2：1：6、1：1：4、1：2：6和1：4：10）的吸氢性能。吸氢实验表明，在773 ~ 1073 K和102 ~ 105 Pa的氢压下，所有样品的氢容量（以Th和Zr含量之和归一化）均接近或高于TRIGA燃料U-ZrH 2 − x合金的氢容量。在微观结构方面，合金由三个相组成：α-U，ZrH 2 − x和ThZr 2 H7 − x，它们彼此精细均匀地混合，可能是因为它们是由一个在高温下稳定的固溶体相形成的。在富Th合金中，α-U的直径约为1 μm，分散在ThZr 2 H7 − x和ZrH 2 − x中。这种微结构与U ZrH 2 − x燃料非常相似。在反应堆中辐照到7.4 × 1023 n/m2时，样品具有较高的相稳定性。
Hydrogen absorption properties of four UThZr alloys with compositions of 2:1:6, 1:1:4, 1:2:6 and 1:4:10 in U:Th:Zr ratio were examined for developing a new UTh mixed hydride fuel. It was revealed by hydrogen absorption measurement that for all the specimens hydrogen capacities normalized by the sum of Th and Zr contents were similar to or higher than that of the UZrH2 − xalloy, TRIGA fuel, at temperatures from 773 to 1073 K and under hydrogen pressures from 102to 105Pa. Regarding the microstructure, the alloy hydrides consisted of three phases; α-U, ZrH2 − xand ThZr2H7 − x, which are finely and homogeneously mixed with each other probably because they were formed from one solid solution phase stable at high temperatures. In the case of Th-rich alloys the α-U was about 1 μm in diameter and dispersed in the bulk of ThZr2H7 − xand ZrH2 − x. Such microstructure is quite similar to that of UZrH2 − xfuel. The hydrides irradiated to 7.4 × 1023n/m2in the reactor showed a high phase stability.