Neutronic performance of Indian LLCB TBM set conceptual design in ITER

• Published in: Fusion engineering and design 2016-12, Vol.113, p.71-81
• Main Authors: Swami, H.L., Shaw, A.K., Mistry, A.N., Danani, C.
• Format: Article
• Language: English
• Subjects: Breeder reactors; Conceptual design; Design engineering; DPA; Fusion; Fusion reactors; ITER; Lithium; LLCB TBM set; MCNP; Neutron flux; Neutrons; Nuclear cross sections; Nuclear engineering; Nuclear heating; Nuclear power plants; Nuclear reactors; Nuclear safety; Performance evaluation; Radiation transport; Stainless steel; TPR; Tritium
• ISSN: 0920-3796; 1873-7196
• DOI: 10.1016/j.fusengdes.2016.09.012

•Neutronic analyses of conceptual design of LLCB test blanket module in ITER have been performed.•The estimated total tritium production rate in the LLCB TBM is 1.66E+17tritons/s.•Total heat deposited in the LLCB TBM is 0.46MW and highest power density at TBM first wall is 5.2Watt/cc.•The estimation shows the maximum DPA 2.72 at TBM FW. Tritium breeding blanket testing program in ITER is an important milestone towards the development of the fusion reactors. ITER organization is providing an opportunity to the partner countries to test their breeding blanket concepts. A mock-up of Indian Lead Lithium Ceramic Breeder (LLCB) tritium breeding blanket known as LLCB Test Blanket Module (TBM) will be tested in ITER equatorial port no. 2. LLCB blanket consists of lead lithium (PbLi) as a neutron multiplier & tritium breeder, ceramic breeder (Li2TiO3) as a tritium breeder and India specific Reduced Activation Ferretic Martinic Steel (IN-RAFMS) as a structural material. A stainless steel block which is cooled by water, called as shield block, is attached with TBM to provide neutron shield to ITER TBM port. A comprehensive neutronic performance evaluation is required for the design of the LLCB TBM set (TBM+shield block) and associated ancillary systems in ITER. The neutronic performance of the conceptual design of TBM set in ITER has been carried out and reported here. In order to carry out the neutronic performance evaluation, the neutronic models of the LLCB TBM set along with TBM frame have been constructed and inserted in the equatorial port of ITER reference neutronic model C-lite. Neutronic responses such as tritium production rate, nuclear heating, neutron flux & spectra, gas production & DPA in the LLCB TBM set are calculated considering 500MW fusion power & fluence level of 0.3MWa/m2. Radiation transport code MCNP6 and FENDL 2.1 nuclear cross-section data library are used to perform the neutronic analyses of the LLCB TBM set. Neutronic analyses provide the important inputs for the LLCB TBM set engineering design, nuclear safety assessment & other associated ancillary equipment design.