Development of indigenous insulation material for superconducting magnets and study of its characteristics under influence of intense neutron irradiation

26th International Cryogenic Engineering Conference & International Cryogenic Materials Conference 2016

材料科学;物理学

Sharma, Rajiv^1 ; Tanna, V.L.^1 ; Rao, C.V.S.^1 ; Abhangi, Mitul^1 ; Vala, Sudhirsinh^1 ; Sundaravel^2 ; Varatharajan, S.^2 ; Sivakumar, S.^2 ; Sasi, K.^2 ; Pradhan, S.^1

Institute for Plasma Research, India^1

Indira Gandhi Centre for Atomic Research, Kalpakkam, India^2

关键词: Electrical breakdown strengths;    Fast neutron fluence;    Fusion machines;    Glass fiber reinforced composite;    Insulation materials;    Insulation system;    MCNP simulations;    Surface degradation;   

Others  :  https://iopscience.iop.org/article/10.1088/1757-899X/171/1/012149/pdf
DOI  :  10.1088/1757-899X/171/1/012149

学科分类：材料科学（综合）

来源: IOP

【 摘 要 】

Epoxy based glass fiber reinforced composites are the main insulation system for the superconducting magnets of fusion machines. 14MeV neutrons are generated during the DT fusion process, however the energy spectra and flux gets modified to a great extent when they reach the superconducting magnets. Mechanical properties of the GFRP insulation material is reported to degrade up to 30%. As a part of R & D activity, a joint collaboration with IGCAR, Kalpakkam has been established. The indigenous insulation material is subjected to fast neutron fluence of 1014- 1019n/m2(E>0.1 MeV) in FBTR and KAMINI Reactor, India. TRIM software has been used to simulate similar kind of damage produced by neutrons by ion irradiation with 5 MeV Al ions and 3 MeV protons. Fluence of the ions was adjusted to get the same dpa. We present the test experiment of neutron irradiation of the composite material (E-glass, S-glass fiber boron free and DGEBA epoxy). The test results of tensile, inter laminar shear and electrical breakdown strength as per ASTM standards, assessment of micro-structure surface degradation before and after irradiation will be presented. MCNP simulations are carried out for neutron flux, dose and damages produced in the insulation material.