Abstract
Current experimental fusion systems and conceptual designs of fusion pilot plants (FPPs) are growing in complexity and size. Several radiation metrics are crucial to the safe operation of fusion machines, including neutron flux streaming through openings and the shutdown dose rate (SDDR). Most current designs of advanced experimental fusion systems—and the most probable candidates for FPPs—are based on the tokamak concept, which is prone to neutron streaming through the myriad openings needed for diagnostic and support systems. SDDR is caused by decay gamma rays from radionuclides that become activated by neutrons during the operation of a fusion system that use deuterium-deuterium (DD), tritium-tritium, or deuterium-tritium plasma. Because computational tools have become essential for determining these radiation metrics, they must be validated against reliable and applicable experimental data. Experiments at the Joint European Torus (JET) provide a unique source of experimental data for validating computational tools and nuclear data used to determine SDDR and neutron fluxes in streaming-dominated geometries. This paper presents the comprehensive analysis of the high-performance DD JET SDDR, and streaming experiments performed using Oak Ridge National Laboratory (ORNL) fusion workflows. The computational results were compared with experimental results that consist of online SDDR measurements with ionization chambers and neutron fluence streaming measurements using thermoluminescent detectors. The ratio of calculated-to-experimental SDDR values ranges from 0.6 to 2.5, and the streaming results range from 0.5 to 8.0. Future work will include analyzing the JET 2021 DTE2 campaign alongside the integration of the Shift Monte Carlo transport code into all ORNL fusion neutronics workflows.
| Original language | English |
|---|---|
| Pages (from-to) | 284-304 |
| Number of pages | 21 |
| Journal | Fusion Science and Technology |
| Volume | 79 |
| Issue number | 3 |
| DOIs | |
| State | Published - 2023 |
Funding
This work was supported by the Fusion Energy Sciences [ERAT919]; U.S. Department of Energy [DE-AC05-00OR22725]. This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 2014–2018 and 2019–2020 under grant agreement number 633053. The views and opinions expressed herein do not necessarily reflect those of the European Commission. This material is based upon work supported by the U.S. Department of Energy (DOE), Office of Science, Office of Fusion Energy Sciences under the Collaboration to Benchmark Neutronics Simulation Computer Codes under the EURATOM-US DOE Agreement in the Field of Fusion Energy Research and Development. This manuscript has been authored by UT-Battelle, LLC, under contract DE-AC05-00OR22725 with the DOE. The authors acknowledge the support of EUROfusion Preparation of ITER Operation project leader Xavier Litaudon. The authors acknowledge Scott Mosher and Stephen Wilson for their development of ADVANTG, MSX, and NAGSS and their efforts to validate the SDDR code suite on benchmark experiments. This material is based upon work supported by the U.S. Department of Energy (DOE), Office of Science, Office of Fusion Energy Sciences under the Collaboration to Benchmark Neutronics Simulation Computer Codes under the EURATOM-US DOE Agreement in the Field of Fusion Energy Research and Development. This manuscript has been authored by UT-Battelle, LLC, under contract DE-AC05-00OR22725 with the DOE. The authors acknowledge the support of EUROfusion Preparation of ITER Operation project leader Xavier Litaudon. The authors acknowledge Scott Mosher and Stephen Wilson for their development of ADVANTG, MSX, and NAGSS and their efforts to validate the SDDR code suite on benchmark experiments. This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 2014–2018 and 2019–2020 under grant agreement number 633053. The views and opinions expressed herein do not necessarily reflect those of the European Commission.
| Funders | Funder number |
|---|---|
| Collaboration to Benchmark Neutronics Simulation Computer Codes | |
| Fusion Energy Research and Development | |
| MSX | |
| NAGSS | |
| U.S. Department of Energy | DE-AC05-00OR22725 |
| Office of Science | |
| Fusion Energy Sciences | ERAT919 |
| H2020 Euratom | 633053 |
Keywords
- ADVANTG
- JET
- MS-CADIS
- shutdown dose rate
- streaming
