The European DEMO Helium Cooled Pebble Bed Breeding Blanket: Design Status at the Conclusion of the Pre-Concept Design Phase

Zhou, Guangming; Hernández, Francisco A.; Pereslavtsev, P.; Kiss, Béla; Retheesh, Anoop; Maqueda, Luis G.; Park, Jin Hun

doi:10.3390/en16145377

Cited by 7 publications

(6 citation statements)

References 55 publications

(79 reference statements)

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“…In their article, G. Zhou et al [1] present a description of the European DEMO HCPB breeding blanket's design and its evolution. The design activities and performance analyses are summarized, showing that the HCPB BB is a high tritium-breeding and robust blanket candidate for the European DEMO.…”

Section: Published Papers Highlightsmentioning

confidence: 99%

Editorial: Advances in Nuclear Fusion Energy and Cross-Cutting Technologies

Palermo

2024

Energies

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Section: Published Papers Highlightsmentioning

confidence: 99%

Editorial: Advances in Nuclear Fusion Energy and Cross-Cutting Technologies

Palermo

2024

Energies

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“…The HCPB blanket design [3], which incorporates a Single Module Segmentation (SMS), aligns with the dimensions of the breeder blanket space outlined in the generic DEMO model described previously. Enclosed within a U-shaped FW of 25 mm thickness is the blanket, featuring a substantial 150 mm thick back supporting wall (BSW), as illustrated in Figure 2a.…”

Section: Hcpb Breeder Blanket Layoutmentioning

confidence: 99%

“…As was mentioned above, all the MCNP geometry models of the 22.5 • DEMO toroidal segments include reflecting boundaries to simulate the tokamak symmetry. The material assignments were performed in the MCNP input decks, making use of the reference data for different DEMO blanket concepts [3][4][5]: the VV shell of 6 cm thickness was made of the SS316L(N) steel and the VV interior volume was filled with a material mixture of 60% SS316L(N) steel and 40% water (200 • C, 3.1 MPa). The ports walls were assumed to also be made of SS316L(N) steel.…”

Section: Geometry Models For Neutronic Simulationsmentioning

confidence: 99%

“…This study was conducted to account for the effects on the TBR and power production of the diverse possible cut-outs in the blankets required for the arrangement of the IVCs. The numerical simulations were carried out with fully heterogeneous geometry models of the HCPB [3], WCLL [4] and WLCB [5] blanket concepts to provide feedback for designing groups with the indication of the TBR req margins and losses of the power production due to IVCs that should be demonstrated before any blanket concept can be accepted in the DEMO project.…”

Section: Introductionmentioning

confidence: 99%

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Main Nuclear Responses of the DEMO Tokamak with Different In-Vessel Component Configurations

Park,

Pereslavtsev

2024

Applied Sciences

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Research and development of the DEMOnstration power plant (DEMO) breeder blanket (BB) has been performed in recent years based on a predefined DEMO tritium breeding ratio (TBR) requirement, which determines a loss of wall surface due to non-breeding in-vessel components (IVCs) which consume plasma-facing wall surface and do not contribute to the breeding of tritium. The integration of different IVCs, such as plasma limiters, neutral beam injectors, electron cyclotron launchers and diagnostic systems, requires cut-outs in the BB, resulting in a loss of the breeder blanket volume, TBR and power generation, respectively. The neutronic analyses presented here have the goal of providing an assessment of the TBR losses associated with each IVC. Previously performed studies on this topic were carried out with simplified, homogenized BB geometry models. To address the effect of the detailed heterogeneous structure of the BBs on the TBR losses due to the inclusion of the IVCs in the tokamak, a series of blanket geometry models were developed for integration in the latest DEMO base model. The assessment was performed for both types of BBs currently developed within the EUROfusion project, the helium-cooled pebble bed (HCPB) and water-cooled lead–lithium (WCLL) concepts, and for the water-cooled lead and ceramic breeder (WLCB) hybrid BB concept. The neutronic simulations were performed using the MCNP6.2 Monte Carlo code with the Joint Evaluated Fission and Fusion File (JEFF) 3.3 data library. For each BB concept, a 22.5° toroidal sector of the DEMO tokamak was developed to assess the TBR and nuclear power generation in the breeder blankets. For the geometry models with the breeder blanket space filled only with blankets without considering IVCs, the results of the TBR calculations were 1.173, 1.150 and 1.140 for the HCPB, WCLL and WLCB BB concepts, respectively. The TBR impact of all IVCs and the losses of the power generation were estimated as a superposition of the individual effects.

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“…In the pre-conceptual design phase of the European DEMO reactor (2014-2020) [1], a series of deterministic safety analyses of the Design basis accidents (DBAs), as well as beyond design basis accidents (BDBAs), have been investigated for the helium cooled pebble bed (HCPB) blanket concept following the design development [2]. References [3][4][5] reported the events of the loss of coolant accidents (LOCAs) in the breeding blanket (BB), in-vessel or ex-vessel for the first designs up to DEMO baseline 2015 with 18 toroidal field coils.…”

Section: Introductionmentioning

confidence: 99%

Preliminary accident analysis of the loss of vacuum in vacuum vessel for the European DEMO HCPB blanket concept

Jin,

Raskob

2024

Nucl. Fusion

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Design Basis Accidents (DBAs) are investigated continuously for the European DEMO reactor accompanying its development. One selected postulated initial event (PIE) is a loss of vacuum (LOVA) in vacuum vessel (VV) with large ingress of air induced by rupture in a VV penetration. It has been investigated for the helium cooled pebble bed blanket concept according to the DEMO baseline 2017. The associated primary heat transfer system (PHTS) and the related systems in the tokamak building, from the VV to the PHTS vault and galleries, are considered for the investigation. The LOVA is postulated to occur at a port seal of the EC (Electron Cyclotron) equatorial port plug (EPP) on the side of the closure plate with (i) a small leak of 1.0E-3 m², or (ii) a large break size of 1.0E-2 m². Air ingress from one port cell into the VV leads to the VV pressurization and the fusion power termination followed by an unmitigated plasma disruption. A loss of off-site power (LOOP) for 32 h is assumed to coincide with the disruption. An in-vessel LOCA (Loss of Coolant Accident) is considered as a consequence if the affected first wall reaches the defined temperature of 1000 °C. The radioactive inventories in the VV (tritium, W-dust) can mobilize towards the VVPSS, the affected systems in the building and the environment due to pressurization, venting and leak conditions. MELCOR 1.8.6 for fusion is applied for this deterministic safety analysis. The resulting releases of radioactivity to the environment are then provided for dose calculation using the computer systems UFOTRI and COSYMA. The transient results of the accident sequences, the detected hydrogen production, the source terms releases and the dose results will be discussed.

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The European DEMO Helium Cooled Pebble Bed Breeding Blanket: Design Status at the Conclusion of the Pre-Concept Design Phase

Cited by 7 publications

References 55 publications

Editorial: Advances in Nuclear Fusion Energy and Cross-Cutting Technologies

Editorial: Advances in Nuclear Fusion Energy and Cross-Cutting Technologies

Main Nuclear Responses of the DEMO Tokamak with Different In-Vessel Component Configurations

Preliminary accident analysis of the loss of vacuum in vacuum vessel for the European DEMO HCPB blanket concept

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