Engineering design and analysis of Indian LLCB TBM set

Ranjithkumar, S.; Sharma, Deepak; Chaudhuri, Paritosh; Danani, Chandan; Kumar, E. Rajendra; Khan, Istiyak; Bhattacharya, S.; Vyas, K.N.

doi:10.1016/j.fusengdes.2015.11.018

Cited by 21 publications

(3 citation statements)

References 3 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Lead-Lithium (Pb-Li) alloys in its eutectic composition (Pb 83 Li 17 ) are considered as one of the important candidates among materials being tested as liquid blankets [1][2][3]. At international level, large amount of experimental work is carried out to understand various properties of Pb-Li under high temperature conditions [4][5][6][7][8][9][10] and various thermoelectric potentials are developed [11,12]. On the other hand, less theoretical attempts are performed so far to compute various physical and chemical properties of Pb-Li alloys [13][14][15][16][17][18][19].…”

Section: Introductionmentioning

confidence: 99%

Electrical Transport Properties of Liquid Pb-Li Alloys

Khambholja¹,

Abhishek²

2021

Phys. Scr.

View full text Add to dashboard Cite

It is generally observed that electrical transport properties of simple liquid metal based alloys can be explained well in terms of Faber-Ziman theory, 2k F scattering model and finite mean free path approach. However, these approaches give poor description for materials, which show departure from nearly free electron (NFE) model. Taking Pb-Li as a test case of a system showing departure from NFE (which also exhibit compound formation tendency and disparate mass system), a new technique is proposed to compute electrical transport properties using model potential formalism coupled with t-matrix formulation. We have treated valence number of Pb & Li as a parameter in determining phase shifts. Further, rather than calculating phase shift in terms of Muffin-Tin potential, we have used model potential formalism. Present results suggest that compared to other three theoretical approaches mentioned above, present coupling scheme reproduce qualitative features of electrical transport properties of liquid Pb-Li alloys, which can be used further to study electrical transport properties of similar systems.

show abstract

Section: Introductionmentioning

confidence: 99%

Electrical Transport Properties of Liquid Pb-Li Alloys

Khambholja¹,

Abhishek²

2021

Phys. Scr.

View full text Add to dashboard Cite

show abstract

“…The conceptual design of the Indian TBM set model is shown in figure 1 [9]. The TBM shield module has an outer dimension of 170 cm (poloidal)×52.6 cm (toroidal)×133.9 cm (radial); detailed dimensions of the steel and water channels are given in figure 2 [9,10]. It consists of two parts, the side part is made of steel and a water mixture and the middle part is made of steel, which allows a path to all pipes of the LLCB TBM.…”

Section: Introductionmentioning

confidence: 99%

A neutronic experiment to support the design of an Indian TBM shield module for ITER

Swami

Abhangi

Sharma

et al. 2019

Plasma Sci. Technol.

View full text Add to dashboard Cite

A shield module is associated with an Indian Test Blanket Module (TBM) in ITER to limit the radiation doses in port inter-space areas. The shield module is made of stainless steel plates and water channels. It is identified as an important component for radiation protection because of its radiation exposure control functionality. The radiation protection classification leads to more assurance of the component design. In order to validate and verify the design of the shield module, a neutronic laboratory-scale experiment is designed and executed. The experiment is planned by considering the irradiation under a neutron source of 14 MeV and yields of 10 10 n s −1 . The reference neutron spectrum of the ITER TBM shield module has been achieved through optimization of the neutron source spectrum by a combination of steel and lead materials. The neutron spectrum and flux are measured using a multiple foil activation technique and neutron dose-rate meter LB 6411 (He-3 proton recoil counter with polyethylene), respectively. The neutronic design simulation is assessed using MCNP5 and FENDL 2.1 crosssection data. The paper covers neutronic design, irradiation and the outcome of the experiment in detail.

show abstract

“…India has proposed the lead-lithium cooled ceramic breeder (LLCB) as the blanket concept to be tested in ITER [1]. The helium-cooled ceramic breeder (HCCB) is an alternative Indian solid breeder blanket concept for future fusion devices (like ITER and DEMO) [2,3].…”

Section: Introductionmentioning

confidence: 99%

Design optimization of first wall and breeder unit module size for the Indian HCCB blanket module

Sharma¹,

Chaudhuri²

2018

Plasma Sci. Technol.

Self Cite

View full text Add to dashboard Cite

The Indian test blanket module (TBM) program in ITER is one of the major steps in the Indian fusion reactor program for carrying out the R&D activities in the critical areas like design of tritium breeding blankets relevant to future Indian fusion devices (ITER relevant and DEMO). The Indian Lead-Lithium Cooled Ceramic Breeder (LLCB) blanket concept is one of the Indian DEMO relevant TBM, to be tested in ITER as a part of the TBM program. Helium-Cooled Ceramic Breeder (HCCB) is an alternative blanket concept that consists of lithium titanate (Li 2 TiO 3) as ceramic breeder (CB) material in the form of packed pebble beds and beryllium as the neutron multiplier. Specifically, attentions are given to the optimization of first wall coolant channel design and size of breeder unit module considering coolant pressure and thermal loads for the proposed Indian HCCB blanket based on ITER relevant TBM and loading conditions. These analyses will help proceeding further in designing blankets for loads relevant to the future fusion device.

show abstract

Engineering design and analysis of Indian LLCB TBM set

Cited by 21 publications

References 3 publications

Electrical Transport Properties of Liquid Pb-Li Alloys

Electrical Transport Properties of Liquid Pb-Li Alloys

A neutronic experiment to support the design of an Indian TBM shield module for ITER

Design optimization of first wall and breeder unit module size for the Indian HCCB blanket module

Contact Info

Product

Resources

About