Shielding Design Optimization of the Helium-Cooled Pebble Bed Breeding Blanket for the EU DEMO Fusion Reactor

The helium-cooled pebble bed (HCPB) breeding blanket (BB) is one of the two driver-blanket candidates for the European DEMO fusion reactor. Recent design activities were focused, among other objectives, on the achievement of an efficient shielding system to adequately protect the vacuum vessel (VV)...

Full description

Bibliographic Details
Main Authors: Iole Palermo, Francisco A. Hernández, Pavel Pereslavtsev, David Rapisarda, Guangming Zhou
Format: Article
Language:English
Published: MDPI AG 2022-08-01
Series:Energies
Subjects:
Online Access:https://www.mdpi.com/1996-1073/15/15/5734
_version_ 1797413985254899712
author Iole Palermo
Francisco A. Hernández
Pavel Pereslavtsev
David Rapisarda
Guangming Zhou
author_facet Iole Palermo
Francisco A. Hernández
Pavel Pereslavtsev
David Rapisarda
Guangming Zhou
author_sort Iole Palermo
collection DOAJ
description The helium-cooled pebble bed (HCPB) breeding blanket (BB) is one of the two driver-blanket candidates for the European DEMO fusion reactor. Recent design activities were focused, among other objectives, on the achievement of an efficient shielding system to adequately protect the vacuum vessel (VV) and toroidal field coils (TFCs). Several shielding options have been studied in terms of architecture (e.g., in-BB shield and ex-BB shield) and materials (e.g., B<sub>4</sub>C, WC, WB, YHx, and ZrHx). In this study, the B<sub>4</sub>C material was selected as the most attractive option considering not only shielding performance but also availability, industrialization, experience, and cost factors. Subsequently, we performed a parametric study by implementing different thicknesses of a B<sub>4</sub>C external shield and reporting information of its effect on shielding performance, structural behavior, swelling and tritium breeding. Furthermore, a detailed structure for the VV was developed considering an internal layered configuration comprising steels/water with different boron contents. Corresponding shielding analyses were conducted regarding influence on neutron attenuation when implementing such a VV structure for both the baseline consolidated design of the HCPB and one of the previously developed and improved BSS configurations. The most critical responses (neutron flux and dpa) were fully established only using 10 cm B<sub>4</sub>C and an improved VV configuration.
first_indexed 2024-03-09T05:26:28Z
format Article
id doaj.art-9c018a995ebb480286fbec212aba0beb
institution Directory Open Access Journal
issn 1996-1073
language English
last_indexed 2024-03-09T05:26:28Z
publishDate 2022-08-01
publisher MDPI AG
record_format Article
series Energies
spelling doaj.art-9c018a995ebb480286fbec212aba0beb2023-12-03T12:36:43ZengMDPI AGEnergies1996-10732022-08-011515573410.3390/en15155734Shielding Design Optimization of the Helium-Cooled Pebble Bed Breeding Blanket for the EU DEMO Fusion ReactorIole Palermo0Francisco A. Hernández1Pavel Pereslavtsev2David Rapisarda3Guangming Zhou4CIEMAT, Fusion Technology Division, Avda. Complutense 40, 28040 Madrid, SpainKarlsruhe Institute of Technology (KIT), 76131 Eggenstein-Leopoldshafen, GermanyKarlsruhe Institute of Technology (KIT), 76131 Eggenstein-Leopoldshafen, GermanyCIEMAT, Fusion Technology Division, Avda. Complutense 40, 28040 Madrid, SpainKarlsruhe Institute of Technology (KIT), 76131 Eggenstein-Leopoldshafen, GermanyThe helium-cooled pebble bed (HCPB) breeding blanket (BB) is one of the two driver-blanket candidates for the European DEMO fusion reactor. Recent design activities were focused, among other objectives, on the achievement of an efficient shielding system to adequately protect the vacuum vessel (VV) and toroidal field coils (TFCs). Several shielding options have been studied in terms of architecture (e.g., in-BB shield and ex-BB shield) and materials (e.g., B<sub>4</sub>C, WC, WB, YHx, and ZrHx). In this study, the B<sub>4</sub>C material was selected as the most attractive option considering not only shielding performance but also availability, industrialization, experience, and cost factors. Subsequently, we performed a parametric study by implementing different thicknesses of a B<sub>4</sub>C external shield and reporting information of its effect on shielding performance, structural behavior, swelling and tritium breeding. Furthermore, a detailed structure for the VV was developed considering an internal layered configuration comprising steels/water with different boron contents. Corresponding shielding analyses were conducted regarding influence on neutron attenuation when implementing such a VV structure for both the baseline consolidated design of the HCPB and one of the previously developed and improved BSS configurations. The most critical responses (neutron flux and dpa) were fully established only using 10 cm B<sub>4</sub>C and an improved VV configuration.https://www.mdpi.com/1996-1073/15/15/5734shieldingboron carbideHCPB blanketDEMOneutronicsnuclear fusion
spellingShingle Iole Palermo
Francisco A. Hernández
Pavel Pereslavtsev
David Rapisarda
Guangming Zhou
Shielding Design Optimization of the Helium-Cooled Pebble Bed Breeding Blanket for the EU DEMO Fusion Reactor
Energies
shielding
boron carbide
HCPB blanket
DEMO
neutronics
nuclear fusion
title Shielding Design Optimization of the Helium-Cooled Pebble Bed Breeding Blanket for the EU DEMO Fusion Reactor
title_full Shielding Design Optimization of the Helium-Cooled Pebble Bed Breeding Blanket for the EU DEMO Fusion Reactor
title_fullStr Shielding Design Optimization of the Helium-Cooled Pebble Bed Breeding Blanket for the EU DEMO Fusion Reactor
title_full_unstemmed Shielding Design Optimization of the Helium-Cooled Pebble Bed Breeding Blanket for the EU DEMO Fusion Reactor
title_short Shielding Design Optimization of the Helium-Cooled Pebble Bed Breeding Blanket for the EU DEMO Fusion Reactor
title_sort shielding design optimization of the helium cooled pebble bed breeding blanket for the eu demo fusion reactor
topic shielding
boron carbide
HCPB blanket
DEMO
neutronics
nuclear fusion
url https://www.mdpi.com/1996-1073/15/15/5734
work_keys_str_mv AT iolepalermo shieldingdesignoptimizationoftheheliumcooledpebblebedbreedingblanketfortheeudemofusionreactor
AT franciscoahernandez shieldingdesignoptimizationoftheheliumcooledpebblebedbreedingblanketfortheeudemofusionreactor
AT pavelpereslavtsev shieldingdesignoptimizationoftheheliumcooledpebblebedbreedingblanketfortheeudemofusionreactor
AT davidrapisarda shieldingdesignoptimizationoftheheliumcooledpebblebedbreedingblanketfortheeudemofusionreactor
AT guangmingzhou shieldingdesignoptimizationoftheheliumcooledpebblebedbreedingblanketfortheeudemofusionreactor