Modeling radionuclide release of TRISO bearing fuel compacts during post-irradiation annealing tests

D. Schappel; K. Terrani; L. L. Snead; B. D. Wirth

doi:10.1016/j.nucengdes.2019.110428

Modeling radionuclide release of TRISO bearing fuel compacts during post-irradiation annealing tests

D. Schappel
, K. Terrani
, L. L. Snead
, B. D. Wirth

Materials Science and Engineering

University of Tennessee
Oak Ridge National Laboratory

Research output: Contribution to journal › Article › peer-review

12 Scopus citations

Abstract

This article presents calculated radionuclide release fractions from TRISO fuel during post-irradiation annealing and comparison with AGR-1 irradiated TRISO compacts using the BISON fuel performance code. The BISON code was found to produce good agreement in an analytical comparison and with legacy German TRISO compact irradiation data. However, the recommended IAEA fission product diffusion coefficients did not produce good agreement with the 2014 AGR-1 data (Demkowicz et al., 2015). Thus, the diffusion coefficients prefactors and activation energies were modified to obtain best agreement with the recent AGR data. Future work involves investigating the release behavior of silver from silicon carbide and implementing methods to provide predictive capability for the silver release behavior.

Original language	English
Article number	110428
Journal	Nuclear Engineering and Design
Volume	357
DOIs	https://doi.org/10.1016/j.nucengdes.2019.110428
State	Published - Feb 2020

Keywords

AGR
BISON
Diffusion
Radionuclide
Release
TRISO

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10.1016/j.nucengdes.2019.110428

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title = "Modeling radionuclide release of TRISO bearing fuel compacts during post-irradiation annealing tests",

abstract = "This article presents calculated radionuclide release fractions from TRISO fuel during post-irradiation annealing and comparison with AGR-1 irradiated TRISO compacts using the BISON fuel performance code. The BISON code was found to produce good agreement in an analytical comparison and with legacy German TRISO compact irradiation data. However, the recommended IAEA fission product diffusion coefficients did not produce good agreement with the 2014 AGR-1 data (Demkowicz et al., 2015). Thus, the diffusion coefficients prefactors and activation energies were modified to obtain best agreement with the recent AGR data. Future work involves investigating the release behavior of silver from silicon carbide and implementing methods to provide predictive capability for the silver release behavior.",

keywords = "AGR, BISON, Diffusion, Radionuclide, Release, TRISO",

author = "D. Schappel and K. Terrani and Snead, \{L. L.\} and Wirth, \{B. D.\}",

note = "Publisher Copyright: {\textcopyright} 2019",

year = "2020",

month = feb,

doi = "10.1016/j.nucengdes.2019.110428",

language = "English",

volume = "357",

journal = "Nuclear Engineering and Design",

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T1 - Modeling radionuclide release of TRISO bearing fuel compacts during post-irradiation annealing tests

AU - Schappel, D.

AU - Terrani, K.

AU - Snead, L. L.

AU - Wirth, B. D.

PY - 2020/2

Y1 - 2020/2

N2 - This article presents calculated radionuclide release fractions from TRISO fuel during post-irradiation annealing and comparison with AGR-1 irradiated TRISO compacts using the BISON fuel performance code. The BISON code was found to produce good agreement in an analytical comparison and with legacy German TRISO compact irradiation data. However, the recommended IAEA fission product diffusion coefficients did not produce good agreement with the 2014 AGR-1 data (Demkowicz et al., 2015). Thus, the diffusion coefficients prefactors and activation energies were modified to obtain best agreement with the recent AGR data. Future work involves investigating the release behavior of silver from silicon carbide and implementing methods to provide predictive capability for the silver release behavior.

AB - This article presents calculated radionuclide release fractions from TRISO fuel during post-irradiation annealing and comparison with AGR-1 irradiated TRISO compacts using the BISON fuel performance code. The BISON code was found to produce good agreement in an analytical comparison and with legacy German TRISO compact irradiation data. However, the recommended IAEA fission product diffusion coefficients did not produce good agreement with the 2014 AGR-1 data (Demkowicz et al., 2015). Thus, the diffusion coefficients prefactors and activation energies were modified to obtain best agreement with the recent AGR data. Future work involves investigating the release behavior of silver from silicon carbide and implementing methods to provide predictive capability for the silver release behavior.

KW - AGR

KW - BISON

KW - Diffusion

KW - Radionuclide

KW - Release

KW - TRISO

UR - https://www.scopus.com/pages/publications/85074771795

U2 - 10.1016/j.nucengdes.2019.110428

DO - 10.1016/j.nucengdes.2019.110428

M3 - Article

AN - SCOPUS:85074771795

SN - 0029-5493

VL - 357

JO - Nuclear Engineering and Design

JF - Nuclear Engineering and Design

M1 - 110428

ER -

Modeling radionuclide release of TRISO bearing fuel compacts during post-irradiation annealing tests

Abstract

Keywords

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