Abstract
The paper presents results from neutron flux calculations in the divertor cassette body in cases of Helium Cooled Pebble Bed, and Water-Cooled Lithium Lead concepts are used as a breeding blanket. The same divertor model configuration and specified DEMO neutron source were used for both cases studied. MCNP6 code was used for neutron transport calculations and employing the FENDL-3.1 nuclear data library. |In addition, this paper presents the neutron-induced dose rate calculations performed with support by ADVANTG (AutomateD VAriaNce reducTion Generator) tool and MCNP code, which were used for the variance reduction and particle transport accordingly. The application of such a coupled computational method led to the dose rate and neutron flux maps production, which was obtained for the divertor of the DEMO reactor.
This is a preview of subscription content, log in via an institution to check access.
Similar content being viewed by others
Data Availability
The datasets generated during and/or analysed during the current study are available from the corresponding author on reasonable request.
References
U. Fischer et al., Methodological approach for DEMO neutronics in the European PPPT programme: tools, data and analyses. Fusion Eng. Des. 123, 26–31 (2017)
C.J .Werner, "MCNP Users Manual—Code Version 6.2", 2017 LA-UR-17–29981
X S.W. Mosher et al., ADVANTG—An Automated Variance Reduction Parameter Generator, (2015) ORNL/TM-2013/416 Rev. 1, Oak Ridge National Laboratory, Oak Ridge, TN
F. Brown, B. Kiedrowski, J. Bull, M. Gonzales, N. Gibson, "Verification of MCNP5–1.60",(2010)., LA-UR-10–05611
Y. Qiu, U. Fischer Global Flux Calculation for IFMIF-DONES Test Cell Using Advanced Variance Reduction Technique, Fusion Sci Technol, (2018) pp. 406–411
W. Yican, Fusion neutronics (China, Springer Nature Singapore, 2017), ISBN 978–981–10–5468–6
J.K. Shultis, R.E. Faw, An MCNP Primer (Kansas State University, Manhattan, 2011)
T. Booth, Sample problem for variance reduction in MCNP. (1985) LA-10363-MS
A. Colangeli et al., Neutronics related integration studies of EU-DEMO pellet injection system. Fusion Eng. Des. (2020). https://doi.org/10.1016/j.fusengdes.2020.111753
V. Hernandez-Davila et al., Determination of neutron fluence-to-dose conversion coefficients by means of artificial neural networks. Appl. Radiat. Isotopes (2013). https://doi.org/10.1016/j.apradiso.2013.04.014ICRP
Conversion Coefficients for Radiological Protection Quantities for External Radiation Exposures. ICRP Publication 116, Ann. ICRP 40 (2–5)
G. Mazzone et al., Eurofusion-DEMO Divertor—Cassette design and integration. Fusion Eng. Des. (2020). https://doi.org/10.1016/j.fusengdes.2020.111656.F
F. Hernández et al., A new HCPB breeding blanket for the EU DEMO: evolution, rationale and preliminary performances. Fusion Eng. Des. 124, 882–886 (2017). https://doi.org/10.1016/j.fusengdes.2017.02.00
A. Tassone et al., Recent progress in the WCLL breeding blanket design for the DEMO fusion reactor. IEEE T Plasma Sci. (2017). https://doi.org/10.1109/TPS.2017.2786046
R. Forrest et al., INDC(NDS)-0628 (IAEA, Vienna, 2012)
Author information
Authors and Affiliations
Corresponding author
Additional information
Publisher's Note
Springer Nature remains neutral with regard to jurisdictional claims in published maps and institutional affiliations.
Rights and permissions
About this article
Cite this article
Breidokaite, S., Stankunas, G. Neutron Flux in EU DEMO Divertor Cassette Body Using HCPB and WCLL Breeding Blanket Models. J Fusion Energ 41, 14 (2022). https://doi.org/10.1007/s10894-022-00327-7
Accepted:
Published:
DOI: https://doi.org/10.1007/s10894-022-00327-7