2021 Fall Meeting

Presentation information

Oral presentation

V. Nuclear Fuel Cycle and Nuclear Materials » 501-2 Nuclear Fuel and the Irradiation Behavior

[2D05-08] Accident Tolerant Fuel

Thu. Sep 9, 2021 10:45 AM - 12:00 PM Room D

chair: Fumihiro Nakamori (CRIEPI)

11:30 AM - 11:45 AM

[2D08] Development of coated zirconium alloy fuel cladding as an accident tolerant fuel for PWR

(2)Manufacturing test

*Yuji Okada1, Daiki Sato1, Nozomu Murakami2 (1. MNF, 2. MHI)

Keywords:Light water reactor, Accident tolerant, Fuel cladding, Coating, Manufacturing, Mechanical property

We are developing Cr-coated cladding as an accident tolerant fuel cladding. In this paper, sputtering method was applied to fabricate Cr-coated zirconium alloy cladding tube samples, and subjected to mechanical tensile tests in order to make sure robustness of coating layer against to deformation, and effect of coating layer on mechanical properties of cladding tubes.
Robustness of chromium layer on cladding outer surface was verified according to visual appearance of samples after mechanical tensile test, or no defects such as cracking or spalling on the samples. In addition, mechanical properties of Cr-coated cladding tube samples were comparable to normal cludding tubes, thus thin chromium coating doesn’t degrade mechanical properties of cladding tubes.