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Title: Design and Thermal Analysis for Irradiation of Absorber Material Specimens in the High Flux Isotope Reactor

Abstract

This report provides a summary of the irradiation vehicle design and thermal analysis of absorber material specimens planned for irradiation in the flux trap of the High Flux Isotope Reactor (HFIR). Four different absorber materials will be inserted in the same capsule: hafnium carbide without additive (HfC), hafnium carbide with molybdenum silicide additive (HfC + MoSi 2), samarium hafnate (Sm 2HfO 5), and europium hafnate (Eu 2HfO 5). The capsule design,with target temperatures of 300°C,will accommodate twelve specimens. Two capsules are planned to be built and irradiated to two different neutron fluence levels.

Authors:
ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1];  [1];  [1];  [2]
  1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
  2. AREVA Inc. (United States)
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1484111
Report Number(s):
ORNL/SPR-2018/1038
DOE Contract Number:  
AC05-00OR22725
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English

Citation Formats

Cetiner, Nesrin Ozgan, Petrie, Christian M., Burns, Joseph R., Le Coq, Annabelle G., Linton, Kory D., and Stevens, Jacqueline. Design and Thermal Analysis for Irradiation of Absorber Material Specimens in the High Flux Isotope Reactor. United States: N. p., 2018. Web. doi:10.2172/1484111.
Cetiner, Nesrin Ozgan, Petrie, Christian M., Burns, Joseph R., Le Coq, Annabelle G., Linton, Kory D., & Stevens, Jacqueline. Design and Thermal Analysis for Irradiation of Absorber Material Specimens in the High Flux Isotope Reactor. United States. doi:10.2172/1484111.
Cetiner, Nesrin Ozgan, Petrie, Christian M., Burns, Joseph R., Le Coq, Annabelle G., Linton, Kory D., and Stevens, Jacqueline. Thu . "Design and Thermal Analysis for Irradiation of Absorber Material Specimens in the High Flux Isotope Reactor". United States. doi:10.2172/1484111. https://www.osti.gov/servlets/purl/1484111.
@article{osti_1484111,
title = {Design and Thermal Analysis for Irradiation of Absorber Material Specimens in the High Flux Isotope Reactor},
author = {Cetiner, Nesrin Ozgan and Petrie, Christian M. and Burns, Joseph R. and Le Coq, Annabelle G. and Linton, Kory D. and Stevens, Jacqueline},
abstractNote = {This report provides a summary of the irradiation vehicle design and thermal analysis of absorber material specimens planned for irradiation in the flux trap of the High Flux Isotope Reactor (HFIR). Four different absorber materials will be inserted in the same capsule: hafnium carbide without additive (HfC), hafnium carbide with molybdenum silicide additive (HfC + MoSi2), samarium hafnate (Sm2HfO5), and europium hafnate (Eu2HfO5). The capsule design,with target temperatures of 300°C,will accommodate twelve specimens. Two capsules are planned to be built and irradiated to two different neutron fluence levels.},
doi = {10.2172/1484111},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2018},
month = {11}
}

Technical Report:

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