Non-Destructive post-irradiation examination results of the first modern fueled experiments in TREAT

JOURNAL OF NUCLEAR MATERIALS

卷:541

Article

Schulthess, Jason¹  Woolstenhulme, Nicolas¹  Craft, Aaron¹  Kane, Joshua¹  Boulton, Nicholas¹  Chuirazzi, William¹  Winston, Alexander¹  Smolinski, Andrew¹  Jensen, Colby¹  Kamerman, David¹  Wachs, Daniel¹ 

[1] Idaho Natl Lab, 1955N Fremont Ave, Idaho Falls, ID 83415 USA

关键词: TREAT;    Fuel safety research;    Severe accident;    Light water reactor;   

DOI  :  10.1016/j.jnucmat.2020.152442

来源: Elsevier

【 摘 要 】

A series of experiments were conducted in the Transient Reactor Test (TREAT) Facility as part of commissioning for nuclear fuel safety research to be continued over the next several decades. TREAT was first constructed in the late 1950s to support research on nuclear fuel specimens under extreme nuclear-heated conditions. Following a decades-long hiatus, reactor operations were resumed at TREAT in 2017 to support the reemerging field of fuel-safety research. The first fueled tests were performed on fresh light-water reactor (LWR)-type sub length specimens (4.9% enriched UO2 in zirconium-alloy cladding) in inert gas capsules with the primary objective to demonstrate new irradiation capabilities, including calculation of energy-coupling factor, and to provide a baseline reference for interpretation of future experiments on accident tolerant fuel designs and high burnup standard fuels. In parallel, several new nondestructive post-irradiation experimental systems and processes have been developed and were successfully demonstrated using these samples. Five capsules were irradiated with energy injections and peak cladding temperatures of similar to 212 and similar to 1312 J/gUO(2) and similar to 561 similar to 2113 degrees C, respectively. These irradiations resulted in various degrees of fuel damage that were characterized using advanced non-destructive examinations. The post-irradiation examinations highlighted that, in the most-energetic transient, zirconium breakout, also referred to as 'candling,' was observed as gross cladding melting and relocation. Post-irradiation examinations also confirmed results inferred from in situ instrumentation during irradiation and are consistent with previous results from other studies. (C) 2020 Elsevier B.V. All rights reserved.

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