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Indian molten salt breeder reactor (IMSBR)

Discussion in 'Indian Defence Industry' started by ni8mare, May 25, 2017.

  1. ni8mare

    ni8mare FULL MEMBER

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    Abstract. The third stage of Indian nuclear power programme envisages the use of thorium as
    the fertile material with 233U, which would be obtained from the operation of Pu/Th-based fast
    reactors in the later part of the second stage. Thorium-based reactors have been designed in many
    configurations, from light water-cooled designs to high-temperature liquid metal-cooled options.
    Another option, which holds promise, is the molten salt-fuelled reactor, which can be configured to
    give significant breeding ratios. A crucial part for achieving reasonable breeding in such reactors
    is the need to reprocess the salt continuously, either online or in batch mode. India has recently
    started carrying out fundamental studies so as to arrive at a conceptual design of Indian molten salt
    breeder reactor (IMSBR). Presently, various design options and possibilities are being studied from
    the point of view of reactor physics and thermal hydraulic design. In parallel, fundamental studies
    on natural circulation and corrosion behaviour of various molten salts have also been initiated.

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  2. ni8mare

    ni8mare FULL MEMBER

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    upload_2017-5-25_1-57-34.png

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    upload_2017-5-25_10-25-19.png
     
    Last edited: May 25, 2017
  3. ni8mare

    ni8mare FULL MEMBER

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    upload_2017-5-25_2-3-9.png upload_2017-5-25_2-3-23.png

    5.2 Major design goals of Indian molten salt breeder reactor (IMSBR)
    Efficient utilization of thorium resources is essential in the third stage of Indian nuclear power programme. Results published in [16] suggest that considering an out-of-core time of three years, the cycle fissile inventory required for setting up one GWe FBR with metallic fuel consisting of 233U and thorium is much higher compared to the 233U inventory required for the MSBR, while the breeding ratio for both are comparable. Thus, MSBR seems to be the better option for the third stage from the point of view of fuel
    economy. Following are the design goals, which have been proposed for the IMSBR:
    (1) Electrical power of the reactor: 850 MWe.
    (2) Reactor design is based on 233U/ Th fuel cycle.
    (3) The design should avoid use of graphite/carbon-based moderators; hence, the design should be preferably based on fast/epithermal neutron energy spectrum.
    (4) Breeding ratio should be such that a self-sustaining operation of the reactor is achieved after accounting for losses in reprocessing and associated fuel handling.
    (5) High-efficiency power conversion system (η ≥ 45%).
    (a) Supercritical carbon dioxide-based Brayton cycle is the preferred option.
    (b) Ultrasupercritical steam cycle is an alternative option.
    (6) Aim to have air-cooled condenser. Design to incorporate long-term cooling even in the case of prolonged station black-out (SBO).
    (7) Safety comparable or better than the currently designed advanced reactors.
    (8) Provision for passive dumping into passively cooled criticality safe dump tanks under postulated accident conditions.
    (9) Strong negative temperature and void coefficients.
    (10) The removal of decay heat by natural circulation.
    (11) The reactor core outlet temperature ≥800◦C.
    (12) Low pressure system with low salt velocities to avoid issues of erosion.
    (13) Minimization of initial requirement of fissile material inventory.
    (14) Decoupling the reactor from the reprocessing plant leading to simplified reprocessing: Aim to achieve batch mode reprocessing and minimization of the amount of salt to be reprocessed each year.
    (15) Reduced chemical toxicity, hence avoiding salts based on beryllium.
    (16) Economics: Use of salts based on easy availability. Preferable to avoid lithium based salts.
    (17) Metallic structural material: High creep strength alloys compatible to selected salts. Preferable to have 100 years life. This will require development of special alloys for use at high temperatures and joining techniques to minimize corrosion issues, especially those prevalent in the heat-affected zone.
    (18) Accessibility of all major internal components for in-service inspection and onsite repair.
    (19) A future goal of fuel cycle could be the incineration of minor actinides.
    (20) A future goal could also be hydrogen production or preferably a co-generation system, where a part of the thermal energy is utilized for hydrogen and a part for electricity generation. Desalination to obtain potable water from the waste heat of thermodynamic cycle is also an important goal.
     

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  4. Ankit Kumar 001

    Ankit Kumar 001 Major Technical Analyst

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    Is there a fast breeder reactor in commercial operation anywhere in the world ?
     
  5. Vyom

    Vyom Captain GEO STRATEGIC ANALYST

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    Nope. India is the only country making one FBR.
     
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  6. nik141993

    nik141993 2nd Lieutant FULL MEMBER

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  7. Vyom

    Vyom Captain GEO STRATEGIC ANALYST

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  8. Pundrick

    Pundrick Lieutenant FULL MEMBER

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    You mis-understood it with Thorium based reactor.
     
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