| 摘要 |
In the production of nuclear fuel cladding of a zirconium alloy containing Nb or Nb+Ta, annealing is carried out at 550-850 deg C for 1-4 h such that the log of the cumulative anneal parameter is -20 to -15 and satisfies a mathematical relationship relating it to the Nb or Nb+Ta content. Nuclear fuel cladding is produced by subjecting a zirconium alloy of composition (by wt.) 0.2-1.7% Sn, 0.18-0.6% Fe, 0.07-0.4% Cr, 0.05-1.0% Nb, optionally 0.01-0.1% Ta, balance zirconium and impurities, including <= 60 ppm N, to hot forging, solution heat treatment, hot extrusion, repeated annealing and cold rolling, and final stress relief annealing, the annealing being carried out at 550-850 deg C for 1-4 h such that the cumulative anneal parameter /=SAi (where /=SAi = /=Sti asterisk exp(-40000/Ti)) satisfies the relationships of log/=SAi = -20 to -15 and log/=SAi = -18-10XNb to -15-3.75(XNb-0.2), in which Ai = anneal parameter for the 'i'th anneal, ti = anneal duration (h) for the 'i'th anneal, Ti = the anneal temperature (K) for the 'i'th anneal and XNb = the Nb and optional Ta content (in wt.%). An Independent claim is also included for a zirconium alloy nuclear fuel cladding made by the above process.
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