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Gas cooled SMRs

The electric output generally varies between 100 and 287 MW the ACACIA has a lower electric output of 18 to 23 MW. The GT-MHR and the GTHTR have the highest electric outputs of 287 and 274 MW, respectively. [Pg.30]

Except for the HTR-PM, all designs provide for a cogeneration option, often with multiple non-electric applications. The HTR-PM provides for electricity generation only. High [Pg.30]

Pre-application licensing interactions have been started for the GT-MHR pre-application licensing has been made for the PBMR. [Pg.31]

The targeted deployment dates, when specified by the designers, are generally between 2010 and 2020. The earliest dates for a demonstration prototype operation start-up are specified for the projects of PBMR, GTHTR-300, and HTR-PM they are around 2010. [Pg.31]

Progress achieved since previous IAEA publications [Pg.31]

Of the twenty-six concepts and designs addressed, 13 (50%) are water cooled SMRs, 6 (23%) are gas cooled SMRs-high temperature gas cooled reactors (HTGRs), 6 are sodium or lead-bismuth cooled fast reactors, and 1 is a non-conventional very high temperature reactor concept, a liquid salt cooled reactor with HTGR type prismatic fuel. [Pg.14]

Other gas cooled SMRs (HTGRs) were not addressed in the abovementioned publications. [Pg.31]

The designers of gas cooled SMRs (HTGRs) mention the following major factors as contributing to the improved nuclear power plant (NPP) economy ... [Pg.36]

Energy conversion efficiency is an important factor that defines the specific (i.e. per unit of the useful energy produced) values of the resource consumption, emissions and discharges. These values are inversely proportional to the efficiency, so that, for example, gas cooled SMRs with direct Brayton power cycles (energy conversion efficiency -50%) may offer a substantial reduction in the discharged (rejected) heat when compared to present day LWRs (energy conversion efficiency -32%). Heat discharges could also be minimized by purposeful use of the rejected heat (see Annex XV). [Pg.39]

For gas cooled SMRs (HTGRs), the features commonly mentioned in conjunction with the effective resource utilization, minimized waste and reduced environmental impacts are ... [Pg.40]

Similar to gas cooled SMRs (see Section 4.3.2), the proven fission product confinement capability of TRISO type coated particle fuel at very high temperatures is specified as an important inherent safety feature for the prevention of consequences of severe accidents (DID Level 4 in Table 4). In addition to this, chemical inertness and low pressure of the liquid salt coolant eliminate the potential for damage to the confinement structure by rapid chemical energy releases or coolant vaporization. It is also mentioned that most fission products (excluding primary krypton and xenon) and all actinides escaping the fuel are soluble in the liquid salt and will remain in the liquid salt at very high temperatures. [Pg.47]

The intrinsic proliferation resistance features common to all gas cooled SMRs (HTGRs) include high fuel bum-up (low residual inventory of plutonium, high content of " Pu), a difficult to process fuel matrix, radiation barriers, and a low ratio of fissile to fuel block/ fuel pebble mass. [Pg.48]

Most of the innovative gas cooled SMRs addressed in this report incorporate the following technical features to support physical protection of the plant ... [Pg.50]

The only design in this category - the AHTR - incorporates the features similar to that of the innovative gas cooled SMRs (HTGRs). Large thermal margins of coated particle fuel and the location of the reactor in an underground silo are mentioned in conjunction with physical protection of the plant. [Pg.51]

The majority of inputs in this table are for the gas cooled SMRs (HTGRs) targeting the use of direct gas turbine cycles. The R D programmes address the development of turbo-machinery design, the validation and testing of power conversion system components, and further development and integrated tests of the complete power conversion systems. [Pg.52]

Table III.9 of Appendix III indicates the available or planned test facilities in Member States with respect to further R D programmes for innovative SMRs. The majority of facilities specified are for water cooled and gas cooled SMRs, which reflects a more advanced design status achieved by such reactors. At the same time. Table III.9 includes several facilities for lead-bismuth cooled reactors. Table III.9 of Appendix III indicates the available or planned test facilities in Member States with respect to further R D programmes for innovative SMRs. The majority of facilities specified are for water cooled and gas cooled SMRs, which reflects a more advanced design status achieved by such reactors. At the same time. Table III.9 includes several facilities for lead-bismuth cooled reactors.
Provisions for fiill-scope fuel cycle service agreements or fuel leasing Water cooled SMRs IRIS (Annex H) CAREM (Annex III) VBER-300 (Annex VII) RMWR (Annex X) RUTA-70 (Annex XII) Gas cooled SMRs GT-MHR (Annex XV) ACACIA (Annex XIX) Liquid metal cooled SMRs BMN-170 (Annex XXI) RBEC-M (Annex XXIU) 9... [Pg.56]

Option of a turnkey contract for a NPP Water cooled SMRs SMART (Atmex I) CAREM (Annex III) Gas cooled SMRs GT-MHR (Annex XV) 3... [Pg.57]

No information provided Water cooled SMRs SCOR (Annex V) KAMADO (Annex XIII) Gas cooled SMRs FAPIG-HTGR (Annex XVm) Liquid metal cooled SMRs PEACER (Annex XXIV) MS-LBCR (Annex XXV) Non-conventional SMRs AHTR (Annex XXVI) 6... [Pg.57]

See other pages where Gas cooled SMRs is mentioned: [Pg.15]    [Pg.30]    [Pg.30]    [Pg.36]    [Pg.38]    [Pg.40]    [Pg.43]    [Pg.43]    [Pg.48]    [Pg.50]    [Pg.55]    [Pg.55]    [Pg.61]    [Pg.65]    [Pg.67]    [Pg.75]    [Pg.76]    [Pg.77]    [Pg.78]    [Pg.79]    [Pg.80]    [Pg.81]    [Pg.82]    [Pg.83]    [Pg.84]    [Pg.84]    [Pg.85]    [Pg.86]    [Pg.87]    [Pg.417]   


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