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Title: Generation of a plasma neutron source for Monte Carlo neutron transport calculations in the tokamak JET

Journal Article · · Fusion Engineering and Design
 [1];  [2];  [3];  [3];  [4];  [1]
  1. Jožef Stefan Inst., Ljubljana (Slovenia)
  2. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
  3. Uppsala Univ. (Sweden). Dept. of Physics and Astronomy
  4. Culham Centre for Fusion Energy, Abingdon, Oxon (United Kingdom)

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.

Research Organization:
Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
Sponsoring Organization:
USDOE
Contributing Organization:
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.
Grant/Contract Number:
AC02-09CH11466
OSTI ID:
1543447
Journal Information:
Fusion Engineering and Design, Vol. 136, Issue Part B; ISSN 0920-3796
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 10 works
Citation information provided by
Web of Science

References (12)

The Analysis of the External Neutron Monitor Responses in a Simplified JET-Like Tokamak Using ADVANTG journal February 2017
Prediction/modelling of the neutron emission from JET discharges journal July 2002
New techniques for calculating heat and particle source rates due to neutral beam injection in axisymmetric tokamaks journal September 1981
Calculating fusion neutron energy spectra from arbitrary reactant distributions journal February 2016
The tokamak Monte Carlo fast ion module NUBEAM in the National Transport Code Collaboration library journal June 2004
Fusion yield measurements on JET and their calibration journal November 2014
Improved formulas for fusion cross-sections and thermal reactivities journal April 1992
ENDF/B-VIII.0: The 8 th Major Release of the Nuclear Reaction Data Library with CIELO-project Cross Sections, New Standards and Thermal Scattering Data journal February 2018
The ‘neutron deficit’ in the JET tokamak journal June 2017
Anomalous and classical neutral beam fast ion diffusion on JET journal March 2009
Energetic particle physics in fusion research in preparation for burning plasma experiments journal November 2014
TRANSP modelling of total and local neutron emission on MAST journal January 2015

Cited By (2)

Multiphysics approach to plasma neutron source modelling at the JET tokamak journal July 2019
Self-consistent modelling of heating synergy between NBI and ICRH in JET deuterium plasmas journal June 2019

Figures / Tables (5)


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