Mechanical Properties of Irradiated Type-304 and Type-316 Stainless Steel in Fast Reactors.

Abstract

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1000-MWe LMFBR ACCIDENT ANALYSIS AND SAFETY SYSTEM DESIGN STUDY. TOPICAL REPORT. EFFECTS OF IRRADIATION-INDUCED METAL SWELLING ON THE REFERENCE DESIGN.

“…With the primary goal of reducing the maximum core swelling established, the associated effect is the reduction in maximum strain, as shown in Figure 3 The increase in the stresses for the modified fuel assembly shown in [3][4][5][6][7][8][9][10][11][12][13][14][15][16][17][18][19][20][21][3][4][5][6][7][8][9][10][11][12][13][14][15][16][17][18][19][20][21][22] was a setback because of the side effects of neutron flux distribution in the rnodified core. In reducing the neutron fluence level near the core centerline, the actual neutron flux level and the flux gradients near the interface of the core and radial blanket are considerably increased.…”

“…Figure 3-32 shows the published survey by Comprelli and coworkers. 10 The combined data on the time before rupture for type 304 and 316 stainless steel were obtained from the DFR and EBR II reactors. The recent published data by PNL15 also shows good agreement with these results.…”