Published May 1974 | Version v1
Report

Preliminary studies on UO2-cladding compatibility

  • 1. Power Reactor and Nuclear Fuel Development Corp., Tokyo (Japan)

Description

Chemical reaction between cladding material and the fuel containing fission products is important, because it limits the life of fuel elements. Simulated examination has been made on the compatibility between stainless steel and UO2 containing Cs, I or Te as fission products (Cs2O, I2O5 and Te, respectively). Fuel and a stainless steel test piece were placed in a sealed stainless steel capsule; which was then heated at 7000C for 1,000 hr. (1) The depth of reacted zone was large for I2O5, as compared with the other two. (2) Chromium was segregated in the region corroded by I2O5 or Cs2O, in both test piece and capsule. (3) The porous reacted zone in the inner surface of the capsule showed the existence of reaction products. (4) The strength of the test piece decreased with the progress of corrosion. (Mori, K.)

Additional details

Publishing Information

Imprint Title
Semi-annual progress report of Power Reactor and Nuclear Fuel Development Corporation, Tokai Works
Imprint Pagination
p. 51-56.
Report number
PNCT--831-74-01