Generation of a plasma neutron source for Monte Carlo neutron transport calculations in the tokamak JET
Abstract
The connection between plasma physics and neutronics is crucial for the understanding of the operation and performance of modern and future tokamak devices. Neutrons are one of the primary carriers of information on the plasma state and represent the basis for various plasma diagnostic systems as well as measurements of fusion power, tritium breeding studies, evaluations of tokamak structural embrittlement and the heating of water inside the fusion device's walls. It is therefore important that the birth of neutrons in a plasma and their transport from inside the tokamak vessel to the surrounding structures is well characterized. In this paper a methodology for the modelling of the neutron emission on the tokamak JET is presented. The TRANSP code is used to simulate the total neutron production as well as 2D neutron emission profiles for a JET plasma discharge. The spectra of the fusion neutrons are computed using the DRESS code. Finally, the computational results are analysed in an effort to create a plasma neutron source generator, which is to be used for Monte Carlo neutron transport computations.
- Authors:
-
- Jožef Stefan Inst., Ljubljana (Slovenia)
- Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
- Uppsala Univ. (Sweden). Dept. of Physics and Astronomy
- Culham Centre for Fusion Energy, Abingdon, Oxon (United Kingdom)
- Publication Date:
- Research Org.:
- Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
- Sponsoring Org.:
- USDOE
- Contributing Org.:
- 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 under grant agreement No. 633053. The views and opinions expressed herein do not necessarily reflect those of the European Commission. The authors acknowledge the funding received from the Slovenian Research Agency in the scope of the project entitled Training of young researchers 1000-14-0106.
- OSTI Identifier:
- 1543447
- Grant/Contract Number:
- AC02-09CH11466
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Fusion Engineering and Design
- Additional Journal Information:
- Journal Volume: 136; Journal Issue: Part B; Journal ID: ISSN 0920-3796
- Publisher:
- Elsevier
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 70 PLASMA PHYSICS AND FUSION TECHNOLOGY
Citation Formats
Štancar, Žiga, Gorelenkova, Marina, Conroy, Sean, Eriksson, Jacob, Buchanan, James, and Snoj, Luka. Generation of a plasma neutron source for Monte Carlo neutron transport calculations in the tokamak JET. United States: N. p., 2018.
Web. doi:10.1016/j.fusengdes.2018.04.065.
Štancar, Žiga, Gorelenkova, Marina, Conroy, Sean, Eriksson, Jacob, Buchanan, James, & Snoj, Luka. Generation of a plasma neutron source for Monte Carlo neutron transport calculations in the tokamak JET. United States. https://doi.org/10.1016/j.fusengdes.2018.04.065
Štancar, Žiga, Gorelenkova, Marina, Conroy, Sean, Eriksson, Jacob, Buchanan, James, and Snoj, Luka. Mon .
"Generation of a plasma neutron source for Monte Carlo neutron transport calculations in the tokamak JET". United States. https://doi.org/10.1016/j.fusengdes.2018.04.065. https://www.osti.gov/servlets/purl/1543447.
@article{osti_1543447,
title = {Generation of a plasma neutron source for Monte Carlo neutron transport calculations in the tokamak JET},
author = {Štancar, Žiga and Gorelenkova, Marina and Conroy, Sean and Eriksson, Jacob and Buchanan, James and Snoj, Luka},
abstractNote = {The connection between plasma physics and neutronics is crucial for the understanding of the operation and performance of modern and future tokamak devices. Neutrons are one of the primary carriers of information on the plasma state and represent the basis for various plasma diagnostic systems as well as measurements of fusion power, tritium breeding studies, evaluations of tokamak structural embrittlement and the heating of water inside the fusion device's walls. It is therefore important that the birth of neutrons in a plasma and their transport from inside the tokamak vessel to the surrounding structures is well characterized. In this paper a methodology for the modelling of the neutron emission on the tokamak JET is presented. The TRANSP code is used to simulate the total neutron production as well as 2D neutron emission profiles for a JET plasma discharge. The spectra of the fusion neutrons are computed using the DRESS code. Finally, the computational results are analysed in an effort to create a plasma neutron source generator, which is to be used for Monte Carlo neutron transport computations.},
doi = {10.1016/j.fusengdes.2018.04.065},
journal = {Fusion Engineering and Design},
number = Part B,
volume = 136,
place = {United States},
year = {Mon Apr 30 00:00:00 EDT 2018},
month = {Mon Apr 30 00:00:00 EDT 2018}
}
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Figures / Tables:
Figure 1: Basic plasma parameters for JET shot 92436 – the line averaged electron density and temperature are shown in the upper panel, followed by the heating power and the neutron rate measured by ex-vessel fission chambers in the bottom. The grey area denotes the time window used for averagingmore »
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Works referenced in this record:
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Works referencing / citing this record:
Multiphysics approach to plasma neutron source modelling at the JET tokamak
journal, July 2019
- Štancar, Žiga; Gorelenkova, Marina; Conroy, Sean
- Nuclear Fusion, Vol. 59, Issue 9
Self-consistent modelling of heating synergy between NBI and ICRH in JET deuterium plasmas
journal, June 2019
- Joly, J.; Garcia, J.; Imbeaux, F.
- Plasma Physics and Controlled Fusion, Vol. 61, Issue 7
Figures / Tables found in this record:
Figures/Tables have been extracted from DOE-funded journal article accepted manuscripts.