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Title: Report on fundamental modeling of irradiation-induced swelling and creep in FeCrAl alloys

Abstract

In order to improve the accident tolerance of light water reactor (LWR) fuel, alternative cladding materials have been proposed to replace zirconium (Zr)-based alloys. Of these materials, there is a particular focus on iron-chromium-aluminum (FeCrAl) alloys due to much slower oxidation kinetics in high-temperature steam than Zr-alloys. This should decrease the energy release due to oxidation and allow the cladding to remain integral longer in the presence of high temperature steam, making accident mitigation more likely. As a continuation of the development for these alloys, the material response must be demonstrated to provide suitable radiation stability, in order to ensure that there will not be significant dimensional changes (e.g., swelling), as well as quantifying the radiation hardening and radiation creep behavior. In this report, we describe the use of cluster dynamics modeling to evaluate the defect physics and damage accumulation behavior of FeCrAl alloys subjected to neutron irradiation, with a particular focus on irradiation-induced swelling and defect fluxes to dislocations that are required to model irradiation creep behavior.

Authors:
 [1];  [2];  [1];  [1]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  2. Univ. of Tennessee, Knoxville, TN (United States)
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1337855
Report Number(s):
ORNL/TM-2016/569
AF5810000; NEAF278; TRN: US1701425
DOE Contract Number:  
AC05-00OR22725
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; CREEP; SWELLING; IRON BASE ALLOYS; CHROMIUM ALLOYS; ALUMINIUM ALLOYS; TERNARY ALLOY SYSTEMS; TEMPERATURE RANGE 0400-1000 K; FUEL CANS; WATER MODERATED REACTORS; PHYSICAL RADIATION EFFECTS; NEUTRONS; DISLOCATIONS; RADIATION HARDENING; COMPUTERIZED SIMULATION; WATER COOLED REACTORS; STABILITY; ACCIDENT-TOLERANT NUCLEAR FUELS

Citation Formats

Kohnert, Aaron A., Dasgupta, Dwaipayan, Wirth, Brian, and Linton, Kory D. Report on fundamental modeling of irradiation-induced swelling and creep in FeCrAl alloys. United States: N. p., 2016. Web. doi:10.2172/1337855.
Kohnert, Aaron A., Dasgupta, Dwaipayan, Wirth, Brian, & Linton, Kory D. Report on fundamental modeling of irradiation-induced swelling and creep in FeCrAl alloys. United States. doi:10.2172/1337855.
Kohnert, Aaron A., Dasgupta, Dwaipayan, Wirth, Brian, and Linton, Kory D. Fri . "Report on fundamental modeling of irradiation-induced swelling and creep in FeCrAl alloys". United States. doi:10.2172/1337855. https://www.osti.gov/servlets/purl/1337855.
@article{osti_1337855,
title = {Report on fundamental modeling of irradiation-induced swelling and creep in FeCrAl alloys},
author = {Kohnert, Aaron A. and Dasgupta, Dwaipayan and Wirth, Brian and Linton, Kory D.},
abstractNote = {In order to improve the accident tolerance of light water reactor (LWR) fuel, alternative cladding materials have been proposed to replace zirconium (Zr)-based alloys. Of these materials, there is a particular focus on iron-chromium-aluminum (FeCrAl) alloys due to much slower oxidation kinetics in high-temperature steam than Zr-alloys. This should decrease the energy release due to oxidation and allow the cladding to remain integral longer in the presence of high temperature steam, making accident mitigation more likely. As a continuation of the development for these alloys, the material response must be demonstrated to provide suitable radiation stability, in order to ensure that there will not be significant dimensional changes (e.g., swelling), as well as quantifying the radiation hardening and radiation creep behavior. In this report, we describe the use of cluster dynamics modeling to evaluate the defect physics and damage accumulation behavior of FeCrAl alloys subjected to neutron irradiation, with a particular focus on irradiation-induced swelling and defect fluxes to dislocations that are required to model irradiation creep behavior.},
doi = {10.2172/1337855},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Sep 23 00:00:00 EDT 2016},
month = {Fri Sep 23 00:00:00 EDT 2016}
}

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