Complete Degradation of Be2C at Conditions Expected in Molten Salt Environments

Anne A. Campbell; Ercan Cakmak; Blake Henry; Katherine (Katie) R. Johnson; Diego Muzquiz; Yuri Osetskiy; Erica Paxton; Stephen Raiman; Adam Willoughby; Eva Zarkadoula; David Holcomb

doi:10.2172/2462862

Complete Degradation of Be₂C at Conditions Expected in Molten Salt Environments

Anne A. Campbell, Ercan Cakmak, Blake Henry, Katherine (Katie) R. Johnson, Diego Muzquiz, Yuri Osetskiy, Erica Paxton, Stephen Raiman, Adam Willoughby, Eva Zarkadoula, David Holcomb

Research output: Book/Report › Commissioned report

Abstract

This technical report is in submission of completion of the Level 3 milestone number M3AT24OR1101032, titled “Complete Degradation of Be₂C at conditions expected in molten salt environments,” for the AT-24OR110103 “Beryllium Carbide as moderator for MSRs—ORNL” WBS number 2.04.11.01 within the larger Advanced Reactor Technologies program at Oak Ridge National Laboratory. This effort is an initial study of the viability of Be₂C as a future neutron moderator for molten salt reactors and other high-temperature reactors. The research was awarded funding in September 2022, and this Level 2 milestone presents the work that completed by the end of July 2023. This work is a collaboration between Oak Ridge National Laboratory and the University of Michigan. This report discusses the status of this effort and planned work before the final reporting.

Original language	English
Place of Publication	United States
DOIs	https://doi.org/10.2172/2462862
State	Published - Sep 2024

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10.2172/2462862

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title = "Complete Degradation of Be2C at Conditions Expected in Molten Salt Environments",

abstract = "This technical report is in submission of completion of the Level 3 milestone number M3AT24OR1101032, titled “Complete Degradation of Be2C at conditions expected in molten salt environments,” for the AT-24OR110103 “Beryllium Carbide as moderator for MSRs—ORNL” WBS number 2.04.11.01 within the larger Advanced Reactor Technologies program at Oak Ridge National Laboratory. This effort is an initial study of the viability of Be2C as a future neutron moderator for molten salt reactors and other high-temperature reactors. The research was awarded funding in September 2022, and this Level 2 milestone presents the work that completed by the end of July 2023. This work is a collaboration between Oak Ridge National Laboratory and the University of Michigan. This report discusses the status of this effort and planned work before the final reporting.",

author = "Campbell, {Anne A.} and Ercan Cakmak and Blake Henry and Johnson, {Katherine (Katie) R.} and Diego Muzquiz and Yuri Osetskiy and Erica Paxton and Stephen Raiman and Adam Willoughby and Eva Zarkadoula and David Holcomb",

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doi = "10.2172/2462862",

language = "English",

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TY - BOOK

T1 - Complete Degradation of Be2C at Conditions Expected in Molten Salt Environments

AU - Campbell, Anne A.

AU - Cakmak, Ercan

AU - Henry, Blake

AU - Johnson, Katherine (Katie) R.

AU - Muzquiz, Diego

AU - Osetskiy, Yuri

AU - Paxton, Erica

AU - Raiman, Stephen

AU - Willoughby, Adam

AU - Zarkadoula, Eva

AU - Holcomb, David

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N2 - This technical report is in submission of completion of the Level 3 milestone number M3AT24OR1101032, titled “Complete Degradation of Be2C at conditions expected in molten salt environments,” for the AT-24OR110103 “Beryllium Carbide as moderator for MSRs—ORNL” WBS number 2.04.11.01 within the larger Advanced Reactor Technologies program at Oak Ridge National Laboratory. This effort is an initial study of the viability of Be2C as a future neutron moderator for molten salt reactors and other high-temperature reactors. The research was awarded funding in September 2022, and this Level 2 milestone presents the work that completed by the end of July 2023. This work is a collaboration between Oak Ridge National Laboratory and the University of Michigan. This report discusses the status of this effort and planned work before the final reporting.

AB - This technical report is in submission of completion of the Level 3 milestone number M3AT24OR1101032, titled “Complete Degradation of Be2C at conditions expected in molten salt environments,” for the AT-24OR110103 “Beryllium Carbide as moderator for MSRs—ORNL” WBS number 2.04.11.01 within the larger Advanced Reactor Technologies program at Oak Ridge National Laboratory. This effort is an initial study of the viability of Be2C as a future neutron moderator for molten salt reactors and other high-temperature reactors. The research was awarded funding in September 2022, and this Level 2 milestone presents the work that completed by the end of July 2023. This work is a collaboration between Oak Ridge National Laboratory and the University of Michigan. This report discusses the status of this effort and planned work before the final reporting.

U2 - 10.2172/2462862

DO - 10.2172/2462862

M3 - Commissioned report

BT - Complete Degradation of Be2C at Conditions Expected in Molten Salt Environments

CY - United States

ER -

Complete Degradation of Be2C at Conditions Expected in Molten Salt Environments

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Complete Degradation of Be₂C at Conditions Expected in Molten Salt Environments