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首页> 外文会议>Thirteenth International Symposium on Zirconium in the Nuclear Industry; Jun 10-14, 2001; Annecy, France >Alternative Zr Alloys with Irradiation Resistant Precipitates for High Burnup BWR Application
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Alternative Zr Alloys with Irradiation Resistant Precipitates for High Burnup BWR Application

机译：具有抗辐射沉淀的替代Zr合金，可用于高燃耗BWR应用

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摘要

In the core of BWRs, the second-phase particles (SPP) of Zircaloy-2 and Zir-caloy-4, the Zr(FeCr)_2 and the Zr_2(FeNi) phase, release Fe and dissolve. The degree of dissolution depends on initial size and fluence. These SPP, however, are important for the corrosion behavior of Zircaloy. Zircaloy shows an increase of corrosion at a certain burnup, depending on the initial SPP size and fast neutron fluence. Only Zr alloys with irradiation resistant SPP avoid this type of increased corrosion completely. Two types of irradiation resistant materials were considered. One is a Zr-Sn-Fe alloy containing the Zr_3Fe phase, which is irradiation resistant under BWR conditions. The other material is a Zr-Sn-Nb alloy containing the irradiation resistant β-Nb phase. In-BWR tests have shown that a Sn content of >0.8% is mandatory to minimize the nodular corrosion. Two prototypes of irradiation resistant alloys, Zrl.3Sn0.25-0.3 Fe and Zr1Sn2-3Nb, were irradiated in a BWR for 1372 days to a fast fluence of 9 X 10~(21) n/cm~2 (E > 1 MeV). These irradiation tests showed that Zrl.3Sn0.25-0.3 Fe has a little lower resistance against nodular corrosion than optimized LTP (Low Temperature Process) Zircaloy-2/4 and revealed that ZrlSn2-3Nb is superior to LTP Zircaloy-2/4 with respect to nodular and shadow corrosion resistance. The BWR corrosion resistance of ZrlSn2-3Nb depends on heat treatment. The lowest corrosion was observed with material fabricated completely in the α-range, but also material manufactured in the lower (α+β)-range exhibits low corrosion. Material fabricated in the upper (α+β)-range showed a somewhat higher corrosion, a corrosion behavior similar to LTP Zircaloy-2/4. As far as final annealing is concerned, a long time annealing at 540℃ is superior to a standard recrystallization treatment (e.g., at 580℃), which still leads to a corrosion behavior that is better than stress relieved ZrlSn2-3Nb. ZrlSn2-3Nb is resistant to shadow corrosion, when fabricated completely in the a-range. In other conditions, it shows a similar shadow corrosion behavior as Zircaloy-4.
机译：在BWR的核心中，Zircaloy-2和Zir-caloy-4的第二相颗粒（SPP），Zr（FeCr）_2和Zr_2（FeNi）相释放出Fe并溶解。溶解程度取决于初始大小和通量。但是，这些SPP对于Zircaloy的腐蚀行为很重要。 Zircaloy在一定的燃耗下显示出腐蚀的增加，这取决于初始SPP大小和快速中子注量。只有具有抗辐射SPP的Zr合金才能完全避免这种类型的腐蚀。考虑了两种类型的耐辐射材料。一种是含有Zr_3Fe相的Zr-Sn-Fe合金，该合金在BWR条件下具有耐辐照性。另一种材料是含有抗辐射β-Nb相的Zr-Sn-Nb合金。 In-BWR测试表明，必须使Sn含量> 0.8％，才能最大程度地减少结核腐蚀。在BWR中将两个抗辐射合金原型Zrl.3Sn0.25-0.3 Fe和Zr1Sn2-3Nb辐照1372天，以9 X 10〜（21）n / cm〜2的快速通量（E> 1 MeV ）。这些辐照测试表明，Zrl.3Sn0.25-0.3 Fe的抗结核腐蚀性能比优化的LTP（低温工艺）Zircaloy-2 / 4略低，并显示ZrlSn2-3Nb优于LTP Zircaloy-2 / 4，关于结节和阴影腐蚀的抵抗力。 ZrlSn2-3Nb的BWR耐腐蚀性取决于热处理。完全在α范围内制造的材料观察到最低的腐蚀，但在较低（α+β）范围内制造的材料也显示出低腐蚀。在较高的（α+β）范围内制造的材料显示出更高的腐蚀度，其腐蚀行为类似于LTP Zircaloy-2 / 4。就最终退火而言，在540℃下长时间的退火优于标准的再结晶处理（例如在580℃下），这仍导致其腐蚀行为优于消除应力的ZrlSn2-3Nb。当完全在a范围内制造时，ZrlSn2-3Nb可以抵抗阴影腐蚀。在其他条件下，它表现出与Zircaloy-4类似的阴影腐蚀行为。

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