Irradiation behaviour of alloy D9 clad and wrapper in FBTR
Source abstract
Abstract
Titanium modified austenitic stainless steel 316 (Alloy D9) is the material of clad and wrapper for the 500 MWe Prototype Fast Breeder Reactor (PFBR) at Kalpakkam, India. Towards evaluating the irradiation performance of the mixed oxide (MOX) fuel design and Alloy D9 structural material, a test fuel subassembly (FSA) made of Alloy D9 wrapper with 37 MOX fuel pins of Alloy D9 cladding was irradiated in Fast Breeder Test Reactor (FBTR) to a peak burnup of 112 GWd/t. The dimensional changes, swelling and mechanical properties of alloy D9 clad and wrapper at displacement damage levels of 40-62 dpa were evaluated through post-irradiation examinations (PIE) and compared with that of AISI 316 clad/wrapper of FBTR. This study has revealed superior performance of alloy D9 compared to AISI 316 counterparts and suggests that MOX fuel subassembly of PFBR with Alloy D9 cladding and wrapper can safely attain the initial target burnup of 100 GWd/t and corresponding displacement damage of 85 dpa.
Source: expertdata · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Fusion materials and technologies
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
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