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Title: Radiation re-solution of fission gas in non-oxide nuclear fuel

Renewed interest in fast nuclear reactors is creating a need for better understanding of fission gas bubble behavior in non-oxide fuels to support very long fuel lifetimes. Collisions between fission fragments and their subsequent cascades can knock fission gas atoms out of bubbles and back into the fuel lattice. We showed that these collisions can be treated as using the so-called ‘‘homogenous’’ atom-by-atom re-solution theory and calculated using the Binary Collision Approximation code 3DOT. The calculations showed that there is a decrease in the re-solution parameter as bubble radius increases until about 50 nm, at which the re-solution parameter stays nearly constant. Furthermore, our model shows ion cascades created in the fuel result in many more implanted fission gas atoms than collisions directly with fission fragments. This calculated re-solution parameter can be used to find a re-solution rate for future bubble simulations.
Authors:
 [1] ;  [2] ;  [1]
  1. Oregon State Univ., Corvallis, OR (United States). Nuclear Engineering and Radiation Health Physics
  2. Idaho National Lab. (INL), Idaho Falls, ID (United States). Fuel Modeling and Simulation
Publication Date:
OSTI Identifier:
1177672
DOE Contract Number:
AC07-05ID14517
Resource Type:
Journal Article
Resource Relation:
Journal Name: Journal of Nuclear Materials; Journal Volume: 457; Journal Issue: C
Publisher:
Elsevier
Research Org:
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Org:
USDOE
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; NUCLEAR FUELS; Service Life; Reactor Lattices; SOLUTIONS; FISSION PRODUCTS; Uranium Carbides; Uranium Nitrides; MATHEMATICAL SOLUTIONS; BUBBLES; Ion-Atom Collisions; FISSION FRAGMENTS; APPROXIMATIONS; Number Codes; Fast Reactors; SIMULATION NON-OXIDE NUCLEAR FUEL