Abstract
The Oak Ridge National Laboratory (ORNL) Health Physics Research Reactor (HPRR) was a research reactor designed and built at ORNL in 1961. The critical assembly used a highly enriched uranium and molybdenum alloy as the fuel, and could be operated in steady-state or burst modes. The HPRR has recently been the object of an investigation to create a criticality benchmark. Such benchmarks are very important, as they are used primarily to show the accuracy of newly developed modeling codes and to help experimental validation and reactor licensing. The evaluated experiments considered in this paper were carried out between 1974 and 1986 from various HPRR activities such as steady-state subcritical, steady-state critical, and burst prompt super-critical operations of the reactor for dosimetry, irradiation, or training purposes. By using the HPRR experimental logbook information and the as-built drawings of the critical assembly, a highly detailed model of the HPRR was created with SCALE 6.2.4/KENO-VI, and a first version of a critical benchmark of the HPRR was developed following the International Criticality Safety Benchmark Evaluation Project (ICSBEP) guidelines for thorough description and uncertainty/sensitivity quantification. Unfortunately, in most of the evaluated experiments, the obtained difference between calculated and experimental keff is around 1,000 pcm, corresponding to a relative error of approximately 1%, beyond the quality standards of the ICSBEP recommending a relative error below 0.1%. Moreover, the derived experimental uncertainty is high, around 4% relative, mainly due to the U-Mo fuel density uncertainty, but also from numerous other factors. For these reasons, the creation of a valuable critical benchmark from HPRR operation data is thus far compromised. In this paper, the different steps of the experiments' evaluation are summarized, and the reasons for the experimental/calculation discrepancies and potential ways to solve them are explored. This paper also aims to remind us always to exercise considerable care when performing experimental work, and to record all the data possible for potential future uses.
| Original language | English |
|---|---|
| Title of host publication | Proceedings of the Nuclear Criticality Safety Division Topical Meeting, NCSD 2022 - Embedded with the 2022 ANS Annual Meeting |
| Publisher | American Nuclear Society |
| Pages | 725-734 |
| Number of pages | 10 |
| ISBN (Electronic) | 9780894487859 |
| DOIs | |
| State | Published - 2022 |
| Event | 2022 Nuclear Criticality Safety Division Topical Meeting, NCSD 2022 - Anaheim, United States Duration: Jun 12 2022 → Jun 16 2022 |
Publication series
| Name | Proceedings of the Nuclear Criticality Safety Division Topical Meeting, NCSD 2022 - Embedded with the 2022 ANS Annual Meeting |
|---|
Conference
| Conference | 2022 Nuclear Criticality Safety Division Topical Meeting, NCSD 2022 |
|---|---|
| Country/Territory | United States |
| City | Anaheim |
| Period | 06/12/22 → 06/16/22 |
Funding
This material is based upon work supported by the US Department of Energy/National Nuclear Security Administration Nuclear Criticality Safety Program (DOE/NNSA NCSP).
Keywords
- HPRR
- ICSBEP
- U-Mo
- critical benchmark
- fast neutron
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