Parametric neutronic analysis of HCLL blanket for DEMO fusion reactor utilizing vacuum vessel ITER FDR design

Jordanova, J.; Fischer, U.; Pereslavtsev, P.; Poitevin, Y.; Puma, A. Li; Arhangelova, Nina

doi:10.1016/j.fusengdes.2006.02.001

Cited by 12 publications

(3 citation statements)

References 1 publication

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“…Figure 5 shows the variation of TBR with 6 Li atom fraction within the lithium lead. Increasing 6 Li enrichment shows an increase in TBR as confirmed by previous studies [29]. Figure 5 shows the variation of TBR with the poloidal height of the lithium lead regions within the breeder zone of the blanket.…”

Section: Neutronics Simulationssupporting

confidence: 84%

Multiphysics analysis with CAD-based parametric breeding blanket creation for rapid design iteration

et al. 2019

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Breeding blankets are designed to ensure tritium self-sufficiency in deuterium–tritium fusion power plants. In addition to this, breeder blankets play a vital role in shielding key components of the reactor, and provide the main source of heat which will ultimately be used to generate electricity. Blanket design is critical to the success of fusion reactors and integral to the design process. Neutronic simulations of breeder blankets are regularly performed to ascertain the performance of a particular design. An iterative process of design improvements and parametric studies are required to optimize the design and meet performance targets. Within the EU DEMO program the breeding blanket design cycle is repeated for each new baseline design. One of the key steps is to create three-dimensional models suitable primarily for use in neutronics, but could be used in other computer-aided design (CAD)-based physics and engineering analyses. This article presents a novel blanket design tool which automates the process of producing heterogeneous 3D CAD-based geometries of the helium-cooled pebble bed, water-cooled lithium lead, helium-cooled lithium lead and dual-coolant lithium lead blanket types. The paper shows a method of integrating neutronics, thermal analysis and mechanical analysis with parametric CAD to facilitate the design process. The blanket design tool described in this paper provides parametric geometry for use in neutronics and engineering simulations. This paper explains the methodology of the design tool and demonstrates use of the design tool by generating all four EU blanket designs using the EU DEMO baseline. Neutronics and heat transfer simulations using the models have been carried out. The approach described has the potential to considerably speed up the design cycle and greatly facilitate the integration of multiphysics studies.

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Section: Neutronics Simulationssupporting

confidence: 84%

Multiphysics analysis with CAD-based parametric breeding blanket creation for rapid design iteration

et al. 2019

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“…Assuming a tritium breeding ratio (TBR) of 1.1, achievable according to [34], around 400 g per day of tritium will be produced in the Pb-15.7Li for a fusion power of 2400 MW. Ports containing H&CD and diagnostics would eventually lead to a TBR decreasing of 0.02 [14,35].…”

Section: Tritium Management and Pb-157li Main Issuesmentioning

confidence: 99%

Consistent integration in preparing the helium cooled lithium lead DEMO-2007 reactor

Li-Puma

Bonnemason

Cachon

et al. 2009

Fusion Engineering and Design

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“…The tritium breeding blanket is an important part of fusion reactor due to its functionality of tritium production which will provide the fuel self‐sufficiency to the reactor and also take out the energy deposited by neutrons to utilize in power production 11‐13 . There are many design concepts proposed worldwide for breeding blankets, 14‐25 India is also working on lead lithium cooled ceramic breeder (LLCB) blanket concept and helium cooled ceramic breeder (HCCB) concepts for Indian DEMO 25‐28 . HCCB concept has beryllium as neutron multiplier and lithium titanate as tritium breeder.…”

Section: Introductionmentioning

confidence: 99%

Helium cooled dual breeder blanket–preliminary design analyses of a candidate breeding blanket concept for near term IndianDEMOfusion reactor

et al. 2020

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Summary Helium cooled dual breeder (HCDB) blanket concept is designed for Indian DEMO fusion reactor and it is made of two tritium breeder materials PbLi and Li2TiO3. It has helium as a coolant and the India specific RAFMS as a structural material. High‐pressure helium first cools the plasma facing first‐wall and after that, it will extract heat from PbLi and ceramic breeder. Since PbLi is not used as a coolant, it therefore circulates with a low flow rate. It will overcome the corrosion and MHD issues associated with high temperature and high flow rate of PbLi. The idea behind the concept is to make a design which can be made using the existing blanket materials, extract high‐grade heat from the reactor and also enhance the availability. In HCDB blanket the role of neutron multiplier is done by PbLi, an alternative to the beryllium and it eliminates the issue associated with high toxic beryllium handling. It can be a potential tritium breeding blanket concept along with lead lithium cooled ceramic breeder (LLCB) and helium cooled ceramic breeder (HCCB) for near term Indian demonstration nuclear fusion power plant. In order to realize the HCDB conceptual design, preliminary estimations of tritium production, nuclear heat density have been carried out. The thermal behaviors of the HCDB blanket in Indian DEMO conditions have been also assessed and reported here. The assessment establishes the proof of HCDB blanket concept and supports it to be a good alternate blanket candidate for the Indian DEMO. The paper describes the HCDB concept along with analysis to verify the tritium self‐sufficiency and materials temperature limits.

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Parametric neutronic analysis of HCLL blanket for DEMO fusion reactor utilizing vacuum vessel ITER FDR design

Cited by 12 publications

References 1 publication

Multiphysics analysis with CAD-based parametric breeding blanket creation for rapid design iteration

Multiphysics analysis with CAD-based parametric breeding blanket creation for rapid design iteration

Consistent integration in preparing the helium cooled lithium lead DEMO-2007 reactor

Helium cooled dual breeder blanket–preliminary design analyses of a candidate breeding blanket concept for near term IndianDEMOfusion reactor

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