Abstract
The IPEN/MB-01 research reactor, located in São Paulo, Brazil, has successfully operated for about 30 years using fuel rods of UO2 enriched to 4.3 wt %235U. For the past three decades, this reactor has served as the basis for several benchmark experiments published in the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and the International Reactor Physics Evaluation Project. The integral experiment handbooks produced by these projects are frequently used by the nuclear community for nuclear data validation. The IPEN/MB-01 reactor was recently upgraded to replace rod-type fuels with plate-type fuels. The new IPEN/MB-01 core has a 4 × 5 configuration and 19 fuel elements consisting of U3Si2-Al enriched to 19.75 wt %235U. Temperature-dependent benchmark experiments were performed with the new IPEN/MB-01 research reactor configuration in the range of 293-353 K. This paper reports the results of calculations using thermal scattering evaluations for H2O and D2O in the ENDF/B-VIII.0 and ENDF/B-VIII.1 libraries in critical experiments performed with the new IPEN/MB-01 setup.
| Original language | English |
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| Title of host publication | Proceedings of the Nuclear Criticality Safety Division 2025 Conference, NCSD 2025 |
| Publisher | American Nuclear Society |
| Pages | 222-230 |
| Number of pages | 9 |
| ISBN (Electronic) | 9780894482274 |
| DOIs | |
| State | Published - 2025 |
| Event | 2025 Nuclear Criticality Safety Division Conference, NCSD 2025 - Austin, United States Duration: Sep 14 2025 → Sep 18 2025 |
Publication series
| Name | Proceedings of the Nuclear Criticality Safety Division 2025 Conference, NCSD 2025 |
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Conference
| Conference | 2025 Nuclear Criticality Safety Division Conference, NCSD 2025 |
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| Country/Territory | United States |
| City | Austin |
| Period | 09/14/25 → 09/18/25 |
Funding
This manuscript has been authored by UT-Battelle, LLC under contract DE-AC05-00OR22725 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes. DOE 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). This material is based upon work supported by the US Department of Energy and the US Nuclear Regulatory Commission. Disclaimer: This work was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.
Keywords
- heavy and light water
- reactor
- thermal scattering law