Neutronic Activity for Development of the Promising Alternative Water-Cooled DEMO Concepts
Source abstract
Abstract
An emerging breeding blanket that fulfills performance criteria, meets the safety requirements, and is reliable enough to meet the plant availability is a challenging issue that assumes complex studies involving numerous neutronic analyses based on the Monte Carlo simulations with MCNP code. Two different concepts are now candidates to be implemented as a driver blanket for DEMO fusion reactor: WCLL (Water-Cooled Lithium Lead) and HCPB (Helium-Cooled Pebble Bed). The current R&D work within the EUROfusion DEMO project is concentrated on a search for the new water-cooled blanket layouts: a deep upgrade of the WCLL blanket to ensure a sufficient tritium breeding capability and an elaboration of the hybrid concept coupling technological advantages of water coolant, lead neutron multiplier, and ceramic breeder. To this end, very detailed, fully heterogeneous MCNP geometry models were developed for the newest designs of the WCLL-db (WCLL-double bundle) and WLCB (Water-cooled liquid Lead Ceramic Breeder) DEMO blankets to verify the new engineering solutions. This makes rigorous calculations possible to find an optimal breeder blanket layout. The basic response, tritium breeding ratio (TBR), was assessed for both concepts, and it appeared to be TBR = 1.16 for the WCLL-db and TBR ≤ 1.13 for the WLCB DEMOs, respectively. Several geometry layouts of the WLCB breeder blanket were investigated to reach the TBR sufficient for a sustainable tritium fuel cycle. Two promising novel solutions were suggested to enhance the tritium breeding performance of the WLCB blanket and to achieve TBR ≥ 1.16: heavy water coolant and an advanced breeder ceramic. Various nuclear safety aspects of the technologies utilized in both blanket concepts are addressed in this work to facilitate engineering decisions aimed at the consolidated blanket design for the upcoming DEMO reactor.
Source: crossref · Quality: baseline
Research context
OpenAlex topics: Nuclear reactor physics and engineering · Fusion materials and technologies · Nuclear Materials and Properties
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
Affiliations
Karlsruhe Institute of Technology (KIT), Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen, Germany
EUROFUSION Programme Management Unit, Fusion Technology Department—DEMO Central Team, Boltzmannstrasse 2, 85748 Garching, Germany
References (25)
Show source-provided references
1. An overview of the EU breeding blanket design strategy as an integral part of the DEMO design effort10.1016/j.fusengdes.2019.01.141 ↗
2. Pereslavtsev, P., Bachmann, C., and Park, J.H. (2021). DEMO tritium breeding performances with different in-vessel components configurations. Fusion Eng. Des., 166.10.1016/j.fusengdes.2021.112319 ↗
3. Arena, P., Del Nevo, A., Moro, F., Noce, S., Mozzillo, R., Imbriani, V., Giannetti, F., Edemetti, F., Froio, A., and Savoldi, L. (2021). The DEMO Water-Cooled Lead–Lithium Breeding Blanket: Design Status at the End of the Pre-Conceptual Design Phase. Appl. Sci., 11.10.3390/app112411592 ↗
4. Hernández, F.A., Pereslavtsev, P., Zhou, G., Kang, Q., D’Amico, S., Neuberger, H., Boccaccini, L.V., Kiss, B., Nádasi, G., and Maqueda, L. (2020). Consolidated design of the HCPB Breeding Blanket for the pre-Conceptual Design Phase of the EU DEMO and harmonization with the ITER HCPB TBM program. Fusion Eng. Des., 156.10.1016/j.fusengdes.2020.111614 ↗
5. Ilenia, C. (2023, June 20). Thermal-Structural Investigation of a Breeder Zone Region of the WCLL “Double Bundle”. Available online: http://idm.euro-fusion.org/?uid=2NCWRV.
6. Initial layout of DEMO buildings and configuration of the main plant systems10.1016/j.fusengdes.2018.02.101 ↗
7. Multi-functional Neutronics Calculation Methodology and Program for Nuclear Design and Radiation Safety Evaluation10.1080/15361055.2018.1475162 ↗
8. Pereslavtsev, P., Cismondi, F., and Hernandez, F. (2020). Analyses of the shielding options for HCPB DEMO blanket. Fusion Eng. Des., 156.10.1016/j.fusengdes.2020.111605 ↗
9. Fischer, U. (2023, June 20). Material Compositions for PPPT Neutronics and Activation Analyses. Available online: http://idm.euro-fusion.org/?uid=2MM3A6.
10. Werner, C.J., Bull, J.S., Solomon, C.J., Brown, F.B., McKinney, G.W., Rising, M.E., Dixon, D.A., Martz, R.L., Hughes, H.G., and Cox, L.J. (2017). MCNP User’s Manual Code, version 6.2, Los Alamos National Laboratory. Tech. Rep. LA-UR-17-29981.
11. The joint evaluated fission and fusion nuclear data library, JEFF-3.310.1140/epja/s10050-020-00141-9 ↗
12. Tokamak D-T neutron source models for different plasma physics confinement modes10.1016/j.fusengdes.2012.02.025 ↗
13. Neutronic analyses in support of the WCLL DEMO design development10.1016/j.fusengdes.2018.04.113 ↗
14. Nuclear analyses of solid breeder blanket options for DEMO: Status, challenges and outlook10.1016/j.fusengdes.2019.01.023 ↗
15. Equilibrium Evaporation Behavior of Polonium and Its Homologue Tellurium in Liquid Lead-Bismuth Eutectic10.1080/18811248.2006.9711230 ↗
16. Death by polonium-210: Lessons learned from the murder of former Soviet spy Alexander Litvinenko10.1053/j.semdp.2008.12.003 ↗
17. First principles review of options for tritium breederand neutron multiplier materials for breeding blankets in fusion reactors10.1016/j.fusengdes.2018.09.014 ↗
18. Park, J.H., and Pereslavtsev, P. (2021). Comparative activation analyses for the HCPB breeding blanket in DEMO. Fusion Eng. Des., 167.10.1016/j.fusengdes.2021.112338 ↗
19. Fleming, M., Stainer, T., and Gilbert, M. (2018). The FISPACT II User Manual, UK Atomic Energy Authority, Culham Science Center. UKAEA-R(18)001.
20. TENDL: Complete Nuclear Data Library for Innovative Nuclear Science and Technology10.1016/j.nds.2019.01.002 ↗
21. Activation and decay heat analysis of the European DEMO blanket concepts10.1016/j.fusengdes.2017.02.100 ↗
22. Tritium release behavior from neutron irradiated Li8PbO610.1016/0022-3115(90)90327-J ↗
23. Phase relations in the system Li2O-ZrO210.1016/0022-3115(89)90560-6 ↗
24. Tritium: Its generation and pathways to the environment at CANDU 6 generating stations10.1016/0029-5493(96)01157-0 ↗
25. Song, K.M., Sohn, S.H., Kang, D.W., and Chung, H.S. (2005, January 27–28). Introduction to Wolsong Tritium Removal Facility (WTRF). Proceedings of the Transactions of the Korean Nuclear Society Autumn Meeting, Busan, Republic of Korea.