TY - JOUR
T1 - A standard capsule design for structural material testing in the Advanced Test Reactor
AU - Anderson, K. S.
AU - Hale, D. D.
AU - Schulthess, J. L.
AU - Arrowood, M. M.
N1 - Funding Information:
This work was supported through the U.S. Department of Energy Advanced Fuels Campaign under DOE Idaho Operations Office Contract DE-AC07-05ID14517. Accordingly, the U.S. Government retains and the publisher, by accepting the article for publication, acknowledges that the U.S. Government retains a nonexclusive, paid-up, irrevocable, world-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for U.S. Government purposes.
Funding Information:
This work was supported through the U.S. Department of Energy Advanced Fuels Campaign under DOE Idaho Operations Office Contract DE-AC07-05ID14517. Accordingly, the U.S. Government retains and the publisher, by accepting the article for publication, acknowledges that the U.S. Government retains a nonexclusive, paid-up, irrevocable, world-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for U.S. Government purposes. This work was also supported through Idaho National Laboratory's Laboratory Directed Research and Development program through project 20A44-046FP. This information was prepared as an account of work sponsored by an agency of the U.S. Government. Neither the U.S. Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. References herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the U.S. Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the U.S. Government or any agency thereof.
Funding Information:
This work was also supported through Idaho National Laboratory’s Laboratory Directed Research and Development program through project 20A44-046FP.
Publisher Copyright:
© 2023 Elsevier B.V.
PY - 2023/12/1
Y1 - 2023/12/1
N2 - Nuclear materials testing is commonly completed in various material test and research reactors throughout the world, including the Advanced Test Reactor (ATR), but the current capsule design, analysis, and fabrication process can take years to complete. To decrease the costs and time associated with materials testing, a standard capsule has been designed which houses various specimen geometries and allows irradiation in virtually any ATR test position. The standard capsule features locking end caps which connect and lock together to form the capsule stack, eliminating the need for a basket and maximizing the quantity of specimens which are contained within the capsule. A customizable internal gas gap provides thermal resistance between the specimens and reactor coolant, making specimen temperatures from approximately 370 to 1000 K achievable. The flexibility of the capsule design allows experimenters to choose irradiation positions based off desired neutron flux, with typical fluences per cycle ranging from 8.8x1019 to 2.3x1021 n/cm2, depending on experiment position. This paper presents and discusses the standard capsule design and analysis.
AB - Nuclear materials testing is commonly completed in various material test and research reactors throughout the world, including the Advanced Test Reactor (ATR), but the current capsule design, analysis, and fabrication process can take years to complete. To decrease the costs and time associated with materials testing, a standard capsule has been designed which houses various specimen geometries and allows irradiation in virtually any ATR test position. The standard capsule features locking end caps which connect and lock together to form the capsule stack, eliminating the need for a basket and maximizing the quantity of specimens which are contained within the capsule. A customizable internal gas gap provides thermal resistance between the specimens and reactor coolant, making specimen temperatures from approximately 370 to 1000 K achievable. The flexibility of the capsule design allows experimenters to choose irradiation positions based off desired neutron flux, with typical fluences per cycle ranging from 8.8x1019 to 2.3x1021 n/cm2, depending on experiment position. This paper presents and discusses the standard capsule design and analysis.
KW - Advanced Test Reactor
KW - Multi-principle-element-alloys
KW - Neutron irradiation testing
KW - Standard capsule
UR - https://www.scopus.com/pages/publications/85173503535
UR - https://www.mendeley.com/catalogue/434ac76a-6e99-3c02-9da3-1c84e01da5e4/
U2 - 10.1016/j.nucengdes.2023.112630
DO - 10.1016/j.nucengdes.2023.112630
M3 - Article
AN - SCOPUS:85173503535
SN - 0029-5493
VL - 414
JO - Nuclear Engineering and Design
JF - Nuclear Engineering and Design
M1 - 112630
ER -