Experimental results of conductive inserts to reduce nuclear fuel temperature during nuclear volumetric heating-Reference-Cited by-同舟云学术

Experimental results of conductive inserts to reduce nuclear fuel temperature during nuclear volumetric heating

Published:2023-02 Issue: Volume:574 Page:154176
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Schulthess Jason L.^ORCID,Spencer Benjamin W.^ORCID,Petersen Philip G.,Woolstenhulme Nicolas E.^ORCID,Ban David,Frazer David,Sudderth Laura,Hamilton Sarah^ORCID,Jewell James K.,Mariani Robert D.

Funder

US Department of Energy

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference14 articles.

1. “Conductive inserts to reduce nuclear fuel temperature”;Medvedev;J. Nucl. Mater.,2020

2. “Dry in-pile fracture Test (DRIFT) for separate-effects validation of ceramic fuel fracture models”;Spencer;J. Nucl. Mater.,2022

3. Post-transient examination of performance of uranium silicide fuel and silicon-carbide composite cladding under reactivity-initiated accident conditions;Schulthess;J. Nucl. Mater.,2022

4. Transient testing of uranium silicide fuel in zircaloy and silicon carbide cladding;Kamerman;Ann. Nucl. Energy,2021

5. Schulthess, J., Woolstenhulme, N., Craft, A., Kane, J., Boulton, N., Chuirazzi, W., Winston, A., Smolinski, A., Jensen, C., Kamerman, D., Wachs, D., “Non-Destructive post-irradiation examination results of the first modern fueled experiments in TREAT”, 541 (2020) 152442. doi:10.1016/j.jnucmat.2020.152442.

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