Progress in engineering design of Indian LLCB TBM set for testing in ITER

Chaudhuri, Paritosh; Ranjithkumar, S.; Sharma, Deepak; Danani, Chandan; Swami, H.L.; Bhattacharya, R.; Patel, Ankur; Kumar, E. Rajendra; Vyas, K.N.

doi:10.1016/j.fusengdes.2014.02.001

Cited by 43 publications

(22 citation statements)

References 10 publications

Supporting

Mentioning

Contrasting

Unclassified

Order By: Relevance

“…Similarly, the Test Blanket Modules (TBMs) based on liquid metal breeder blanket concept have been proposed by many of the participating countries. This includes LeadLithium Cooled Ceramic Breeder (LLCB) TBM proposed by India [4], Dual Coolant Lead Lithium (DCLL) TBM by the USA [5], Dual Functional Lithium-Lead (DFLL) TBM by China [6] and liquid lithium self-cooled breeder blanket design by the Russian Federation [7]. These blanket designs require flow of liquid metal through the TBM channels with finite velocity.…”

Section: A N U S C R I P Tmentioning

confidence: 99%

Mechanical and tribological properties of crystalline aluminum nitride coatings deposited on stainless steel by magnetron sputtering

Choudhary

Mishra

et al. 2015

Journal of Nuclear Materials

View full text Add to dashboard Cite

Section: A N U S C R I P Tmentioning

confidence: 99%

Mechanical and tribological properties of crystalline aluminum nitride coatings deposited on stainless steel by magnetron sputtering

Choudhary

Mishra

et al. 2015

Journal of Nuclear Materials

View full text Add to dashboard Cite

“…A Mock-up of the Indian LLCB breeding blanket module [30][31][32] has Li 2 TiO 3 as tritium breeder. A neutronic model of this blanket module is constructed and inserted in the 3-D ITER neutronic model [33].…”

Section: Radiation Transport Simulationsmentioning

confidence: 99%

Multi-model quantification of defects in irradiated lithium titanate

Danani

Swami

Chaudhuri

et al. 2019

Fusion Engineering and Design

Self Cite

View full text Add to dashboard Cite

Lithium based ceramics (Li 2 TiO 3 , Li 4 SiO 4 etc.) in the packed pebble form, used in breeder blankets to breed tritium, are promising candidates for future fusion reactors. Neutron induced trap sites in the ceramic breeder affect the diffusion and inventory of tritium and thereby influence the quantity of tritium recovered. In the present work, a multi model framework has been employed to quantify the number of defects, which can be used to evaluate trap-sites, due to neutron irradiation in porous Li 2 TiO 3 pebbles. This framework is based on a three stage calculation viz. (i) radiation transport, (ii) obtaining the primary knock-on atom (PKA) energy spectrum and (iii) quantifying the ensuing damage by collision cascade simulations. The output of one stage is coupled to the next stage and finally the defect distribution is obtained. We use radiation transport calculations to obtain the neutron spectrum in ceramic pebbles. This is used as an input to SPECTER, a code that uses evaluated cross-sections, to obtain the Primary Knock-on Atom (PKA) energy spectrum. The PKA energy spectrum is then used to find the number and distribution of vacancies and displacements in porous Li 2 TiO 3 pebbles using binary collision approximation (BCA) based Monte Carlo simulations. The vacancy distribution and the number of vacancies in Li 2 TiO 3 have been evaluated for the ITER neutron source using the above frame work. The PKA energy spectrum of Li, Ti and O PKAs, have been obtained using SPECTER, and their average energies are 680, 120 and 320 keV respectively. The collision cascade simulations shows the expected Bragg peak for the number of defects created and has a range of 6-8 microns for O and Li PKA respectively and a fraction of a micron for Ti PKA. The total number of displaced atoms which is equal to the number of vacancies, at the end of the collision cascades, obtained using the above framework has also been used to estimate the displacements per atom (dpa) in Li 2 TiO 3 and this shows a good agreement with the dpa calculated using the NRT model.

show abstract

“…India has proposed the lead-lithium-cooled ceramic breeder (LLCB) and helium-cooled ceramic breeder (HCCB) as two breeding blanket options for DEMO. A module of the LLCB blanket is planned to be tested in ITER through the Indian Test Blanket Module (TBM) program [4][5][6]. The engineering [7] and nuclear analyses [8] of the Indian LLCB blanket module have already been performed.…”

Section: Introductionmentioning

confidence: 99%

Preliminary performance analysis and optimization based on 1D neutronics model for Indian DEMO HCCB blanket

Aggarwal

Danani

Youssef

2020

Plasma Sci. Technol.

View full text Add to dashboard Cite

India, under its breeding blanket R&D program for DEMO, is focusing on the development of two tritium breeding blanket concepts; namely the lead-lithium-cooled ceramic breeder and the helium-cooled ceramic breeder (HCCB). The study presented in this paper focuses on the neutronic design analysis and optimization from the tritium breeding perspective of the HCCB blanket. The Indian concept has an edge-on configuration and is one of the variants of the helium-cooled solid breeder blanket concepts proposed by several partner countries in ITER. The Indian HCCB blanket having lithium titanate (Li 2 TiO 3 ) as the tritium breeder and beryllium (Be) as the neutron multiplier with reduced-activation ferritic/martensitic steel structure aims at utilizing the low-energy neutrons at the rear part of the blanket. The aim of the optimization study is to minimize the radial blanket thickness while ensuring tritium self-sufficiency and provide data for further neutronic design and thermal-hydraulic layout of the HCCB blanket. It is found that inboard and outboard blanket thicknesses of 40 cm and 60 cm, respectively, can give a tritium breeding ratio (TBR) >1.3, with 60% 6 Li enrichment, which is assumed to be sufficient to cover potential tritium losses and associated uncertainties. The results also demonstrated that the Be packing fraction (PF) has a more profound impact on the TBR as compared to 6 Li enrichment and the PF of Li 2 TiO 3 .

show abstract

Progress in engineering design of Indian LLCB TBM set for testing in ITER

Cited by 43 publications

References 10 publications

Mechanical and tribological properties of crystalline aluminum nitride coatings deposited on stainless steel by magnetron sputtering

Mechanical and tribological properties of crystalline aluminum nitride coatings deposited on stainless steel by magnetron sputtering

Multi-model quantification of defects in irradiated lithium titanate

Preliminary performance analysis and optimization based on 1D neutronics model for Indian DEMO HCCB blanket

Contact Info

Product

Resources

About