Elevated temperature irradiation hardening in austenitic stainless steel

IRRADIATION EFFECTS ON REACTOR STRUCTURAL MATERIALS. Quarterly Progress Report, May--July 1968.

“…Samples were taken from five positions along the thimble, as indicated in Figure 3. 3. The observed microstructures in the high-flux region were similar to those reported(5,6) earlier for Type 304L SS cladding.…”

“…The actual values are listed in Table 3 the vacancy supersaturation term for and aus t enitic stainless steel under EBR-I I cond i t ion s will emphas i ze the imp ortance of th e t erm . The ste ady -sta t e v acancy c on ce n tration due t o the ne utro n i r r ad iati on must firs t be ca lculat ed, which involve s solution of t he equa t ion conce nt ra t ion of va cancies, conc en tra ti on of interstiti als , ins tan taneous flux ~ 3 x 101 5 n/cm 2 for EBR-II, displacement c r oss se c tion ;;;-3 x 10 -22 , vacan cy dif fusio n c oe ffic ient for y iron ~ e -32 ,2 50 /RT, interstitial dif f usion coefficient, r = sink spacing, 3 number of a t oms/em .…”

“…(2) The an a lysis of this is shown i n Tabl e 5 . 3 . They each had a gage l eng th of 1.1 2 5 i n .…”

“…The nature of the stress-strain curves as a function of temperature is shown in Figure 5. 3. Below 200 oK, the deformation is unstable and necking and fracture occur soon after yield.…”

“…thick A533 -B, Class 1 electroslag weldment for this investigation are given in Table 9. 3. A photograph of the weld joint cross section revealing the size of the fusion zone is shown in Figure 9.2 .…”