skip to main content

SciTech ConnectSciTech Connect

Title: High Temperature Fuel Cladding Chemical Interactions Between TRIGA Fuels and 304 Stainless Steel

High-temperature fuel-cladding chemical interactions (FCCI) between TRIGA (Training, Research, Isotopes, General Atomics) fuel elements and the 304 stainless steel (304SS) are of interest to develop an understanding of the fuel behavior during transient reactor scenarios. TRIGA fuels are composed of uranium (U) particles dispersed in a zirconium-hydride (Zr-H) matrix. In reactor, the fuel is encased in 304-stainless-steel (304SS) or Incoloy 800 clad tubes. At high temperatures, the fuel can readily interact with the cladding, resulting in FCCI. A number of FCCI can take place in this system. Interactions can be expected between the cladding and the Zr-H matrix, and/or between the cladding and the U-particles. Other interactions may be expected between the Zr-H matrix and the U-particles. Furthermore, the fuel contains erbium-oxide (Er-O) additions. Interactions can also be expected between the Er-O, the cladding, the Zr-H and the U-particles. The overall result is that very complex interactions may take place as a result of fuel and cladding exposures to high temperatures. This report discusses the characterization of the baseline fuel microstructure in the as-received state (prior to exposure to high temperature), characterization of the fuel after annealing at 950C for 24 hours and the results from diffusion couple experiments carriesmore » out at 1000C for 5 and 24 hours. Characterization was carried out via scanning electron microscopy (SEM) and transmission electron microscopy (TEM) with sample preparation via focused ion beam in situ-liftout-technique.« less
Authors:
 [1] ;  [1] ;  [2] ;  [1] ;  [1] ;  [1]
  1. Idaho National Lab. (INL), Idaho Falls, ID (United States)
  2. Boise State Univ., ID (United States)
Publication Date:
OSTI Identifier:
1259949
Report Number(s):
INL/EXT--15-36708
TRN: US1601536
DOE Contract Number:
AC07-05ID14517
Resource Type:
Technical Report
Research Org:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org:
USDOE National Nuclear Security Administration (NNSA)
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 22 GENERAL STUDIES OF NUCLEAR REACTORS; FUEL-CLADDING INTERACTIONS; STAINLESS STEEL-304; TRIGA TYPE REACTORS; TEMPERATURE RANGE 1000-4000 K; NUCLEAR FUELS; INCOLOY 800; CHEMICAL REACTIONS; URANIUM; ERBIUM OXIDES; ZIRCONIUM HYDRIDES; MATRIX MATERIALS; FUEL ELEMENTS; ANNEALING; FUEL CANS; DIFFUSION; MICROSTRUCTURE; TRANSIENTS 304 Stainless Steel; 304SS; FCCI; Fuel Cladding Chemical Interactions; Interactions; TRIGA