Anisotropic azimuthal power and temperature distribution as a driving force for hydrogen redistribution

M. G. Mankosa, C. J. Piotrowski, M. N. Avramova, A. T. Motta, K. N. Ivanov, S. Stafford, R. L. Williamson

Research output: Chapter in Book/Report/Conference proceedingConference contribution

2 Scopus citations

Abstract

The reactor environment, in which nuclear fuel operates, requires improved multi-dimensional fuel and cladding simulation and analysis to accurately describe fuel behavior. The high-fidelity fuel performance code BISON was developed at Idaho National Laboratory (INL) to address this need. BISON is a three-dimensional finite-element based fuel performance code. In the high temperature environment of a reactor, the zirconium in the cladding undergoes waterside corrosion in primary water, releasing hydrogen in the process. Some of this hydrogen is absorbed by the cladding. Once hydrogen is absorbed in the cladding, its distribution is extremely sensitive to temperature, stress and concentration gradients. Hydrogen migrates down temperature and concentration gradients and at a high enough concentration, precipitates as hydrides which can embrittle the cladding. This paper describes a development effort to validate the hydrogen distribution prediction capabilities of the BISON code. The project is divided into two primary sections: first, using a high fidelity multiphysics coupling to accurately predict temperature gradients as a function of radial, azimuthal, and axial directions (r, θ, and z), and using experimental data to validate a previously developed analytical hydrogen transport and hydride precipitation model implemented in BISON.

Original languageEnglish (US)
Title of host publicationInternational Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
PublisherAmerican Nuclear Society
Pages6229-6242
Number of pages14
ISBN (Electronic)9781510811843
StatePublished - Jan 1 2015
Event16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015 - Chicago, United States
Duration: Aug 30 2015Sep 4 2015

Publication series

NameInternational Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
Volume8

Other

Other16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015
CountryUnited States
CityChicago
Period8/30/159/4/15

All Science Journal Classification (ASJC) codes

  • Instrumentation
  • Nuclear Energy and Engineering

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