Abstract
This paper presents the comparison of 252Cf production in HEU and LEU cores. The proposed LEU design provides a higher mass of 252Cf due to its longer cycle length and higher total flux in the Cm target, which results from the power uprate to 95 MWth. Moreover, different versions of ENDF/B nuclear data libraries have been applied to determine the 252Cf production rate in HFIR. The findings showed that the production rate of 252Cf varies by ~19% based on the selection of the library. Although the most recent libraries showed an overestimation result relative to ENDF/B-VII.0, this work provides a sound basis for the need to validate the cross sections of the nuclides involved in the production of 252Cf using actual experimental data. This work also demonstrated the application of ORIGEN to characterize the most important isotopes and reactions in the 252Cf production chain that can serve as useful information to improve the production efficiency. Future work will simulate as-irradiated campaigns with as-built composition data and as-run operating histories to compare calculated results to the actual 252Cf produced with the current HEU core.
Original language | English |
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Pages (from-to) | 704706 |
Number of pages | 1 |
Journal | Transactions of the American Nuclear Society |
Volume | 128 |
DOIs | |
State | Published - 2023 |
Event | 2023 Transactions of the American Nuclear Society Annual Meeting and Technology Expo, ANS 2023 - Indianapolis, United States Duration: Jun 11 2023 → Jun 14 2023 |
Funding
This material is based upon work supported and funded by the U.S. Department of Energy National Nuclear Security Administration’s Office of Material Management dan Minimization. This research was performed on the High Flux Isotope Reactor, a US DOE Office of Science User Facility operated by ORNL under contract DE-AC05-00OR22725. This material is based upon work supported and funded by the U.S. Department of Energy National Nuclear Security Administration's Office of Material Management and Minimization. This research was performed on the High Flux Isotope Reactor, a US DOE Office of Science User Facility operated by ORNL under contract DE-AC05-00OR22725. 1 Notice: This manuscript has been authored by UT-Battelle, LLC under Contract No. DE-AC05-00OR22725 with the U.S. Department of Energy. The United States Government retains and the publisher, by accepting the article for publication, acknowledges that the United States Government retains a non-exclusive, paid-up, irrevocable, world-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for United States Government purposes. The Department of Energy will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (http://energy.gov/downloads/doe-public-access-plan).
Funders | Funder number |
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U.S. Department of Energy National Nuclear Security Administration’s Office of Material Management dan Minimization | |
U.S. Department of Energy | |
Office of Science | |
National Nuclear Security Administration | |
Oak Ridge National Laboratory | DE-AC05-00OR22725 |