Evaluation of accident tolerant FeCrAl coating for PWR cladding under normal operating conditions with coupled neutron transport and fuel performance

Michael Rose, Thomas J. Downar, Xu Wu, Tomasz Kozlowski

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

Abstract

Following the Fukushima Daiichi nuclear disaster in 2011, the emphasis for nuclear fuel R&D activities has shifted to enhancing the accident tolerance of light water reactor fuels. In a previous study, several accident tolerant fuel (ATF) designs were evaluated under normal operating conditions for pressurized water reactors with SERPENT and BISON. One of the more promising ATF designs was a fuel rod with Zircaloy cladding and a FeCrA1 coating; the current study presents Redwing results for this design. Redwing couples MPACT and BISON in order to perform coupled neutron transport and fuel performance simulations. In both the previous and current studies, a short fuel rod model, 10 pellets in length, was depleted for about 3 years. In the current study, the reactivity as a function of time for the same model was obtained from Redwing; these results show that the FeCrAl coating incurs a significant, but manageable, reactivity penalty. Several important fuel performance parameters were obtained from Redwing and compared to the BISON standalone results from the previous study: fuel/cladding gap width, fission gas released to the plenum, plenum pressure, and other parameters not shown in this paper. The fuel performance parameters show several explainable differences between Redwing and BISON standalone, and some parameters suggest improvements that Redwing makes over BISON standalone. Work is underway to develop a full-length model of an ATF rod for both BISON standalone and Redwing.

Original languageEnglish (US)
Title of host publicationMathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference, M and C+SNA+MC 2015
PublisherAmerican Nuclear Society
Pages2334-2344
Number of pages11
ISBN (Electronic)9781510808041
StatePublished - Jan 1 2015
EventMathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference, M and C+SNA+MC 2015 - Nashville, United States
Duration: Apr 19 2015Apr 23 2015

Publication series

NameMathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference, M and C+SNA+MC 2015
Volume3

Other

OtherMathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference, M and C+SNA+MC 2015
CountryUnited States
CityNashville
Period4/19/154/23/15

Fingerprint

Neutron Transport
accidents
Accidents
Coating
coatings
neutrons
evaluation
Evaluation
rods
nuclear fuels
Reactivity
reactivity
Reactor
light water reactors
pressurized water reactors
disasters
Water
penalties
pellets
fission

Keywords

  • Accident tolerant fuel
  • BISON
  • FeCrAl
  • MPACT
  • Multiphysics

ASJC Scopus subject areas

  • Mathematics(all)
  • Nuclear and High Energy Physics

Cite this

Rose, M., Downar, T. J., Wu, X., & Kozlowski, T. (2015). Evaluation of accident tolerant FeCrAl coating for PWR cladding under normal operating conditions with coupled neutron transport and fuel performance. In Mathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference, M and C+SNA+MC 2015 (pp. 2334-2344). (Mathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference, M and C+SNA+MC 2015; Vol. 3). American Nuclear Society.

Evaluation of accident tolerant FeCrAl coating for PWR cladding under normal operating conditions with coupled neutron transport and fuel performance. / Rose, Michael; Downar, Thomas J.; Wu, Xu; Kozlowski, Tomasz.

Mathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference, M and C+SNA+MC 2015. American Nuclear Society, 2015. p. 2334-2344 (Mathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference, M and C+SNA+MC 2015; Vol. 3).

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

Rose, M, Downar, TJ, Wu, X & Kozlowski, T 2015, Evaluation of accident tolerant FeCrAl coating for PWR cladding under normal operating conditions with coupled neutron transport and fuel performance. in Mathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference, M and C+SNA+MC 2015. Mathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference, M and C+SNA+MC 2015, vol. 3, American Nuclear Society, pp. 2334-2344, Mathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference, M and C+SNA+MC 2015, Nashville, United States, 4/19/15.
Rose M, Downar TJ, Wu X, Kozlowski T. Evaluation of accident tolerant FeCrAl coating for PWR cladding under normal operating conditions with coupled neutron transport and fuel performance. In Mathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference, M and C+SNA+MC 2015. American Nuclear Society. 2015. p. 2334-2344. (Mathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference, M and C+SNA+MC 2015).
Rose, Michael ; Downar, Thomas J. ; Wu, Xu ; Kozlowski, Tomasz. / Evaluation of accident tolerant FeCrAl coating for PWR cladding under normal operating conditions with coupled neutron transport and fuel performance. Mathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference, M and C+SNA+MC 2015. American Nuclear Society, 2015. pp. 2334-2344 (Mathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference, M and C+SNA+MC 2015).
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