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    Ex-Vessel Loss of Coolant Accident Analysis of ITER Divertor Cooling System Using Modified RELAP/SCADAPSIM/Mod 4.0 

    Source: Journal of Nuclear Engineering and Radiation Science:;2017:;volume( 003 ):;issue: 004:;page 41009
    Author(s): Saraswat, S. P.; Munshi, P.; Khanna, A.; Allison, C.
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The initial design of ITER incorporated the use of carbon fiber composites in high heat flux regions and tungsten was used for low heat flux regions. The current design includes tungsten for both these regions. The present ...
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    Thermal Hydraulic and Safety Assessment of First Wall Helium Cooling System of a Generalized Test Blanket System in ITER Using RELAP/SCDAPSIM/MOD4.0 Code 

    Source: Journal of Nuclear Engineering and Radiation Science:;2017:;volume( 003 ):;issue: 001:;page 14503
    Author(s): Saraswat, S. P.; Munshi, P.; Khanna, A.; Allison, C.
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The key objective of the test blanket module (TBM) program is to develop the design technology for DEMO and future power-producing fusion reactors. The proposed first wall of the test blanket system (TBS) is a generalized ...
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    Thermal Hydraulic Safety Assessment of LLCB Test Blanket System in ITER Using Modified relap/scdapsim/mod4.0 Code 

    Source: Journal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 002:;page 21001
    Author(s): Saraswat, S. P.; Munsh, P.; Khanna, A.; Allison, C.
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: This work attempts to investigate the thermal hydraulic safety of lithium lead ceramic breeder (LLCB) test blanket system (TBS) in International Thermonuclear Experimental Reactor (ITER) with the help of modified thermal ...
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