Experimental Potentialities of the MBIR Reactor

Transcription

1 International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (). Paris, France, 4-7 March 2013 Experimental Potentialities of the MBIR Reactor Based on report #199/456 Yu.G Dragunov, A.V. Lopatkin, I.V. Lukasevich, N.V. Romanova, I.T. Tretiyakov NIKIET M.N. Svyatkin NIIAR L.A. Kochetkov - IPPE JSC «NIKIET» Engineer-designer A.V. Mishukov mishukov@nikiet.ru JSC «NIKIET» RR General Designer, MBIR reactor General Designer I.T. Tretiyakov tretjakov@nikiet.ru 1

2 Introduction The prospects of nuclear power are closely linked with the evolution of fast-neutron reactors and a closed nuclear fuel cycle. Therefore the Federal Special Program entitled Nuclear Energy Technologies of New Generation for the Period up to 2015 and for Long-Term Outlook up to 2020 envisions the creation of a multi-purpose research fast reactor MBIR, that is aimed to provide the evolution of innovative nuclear power technologies. 2

3 The main tasks of MBIR reactor Study of advanced types of nuclear fuel and absorbers Fuel elements and assemblies testing in transient, cyclic and emergency conditions of operation Reactor testing and studies of problems related to closed nuclear fuel cycle, actinide disposal and long-lived fission products burnout Radiation tests of advanced structural materials Study of new and modified liquid-metal coolants and respective their monitoring instrumentation and quality control tools Production of radioisotopes for different applications, generation of modified materials Medicinal use of neutron beams 3

4 MBIR reactor conceptual provisions Priority on research and experimental tasks as well as reliability and safety of research reactor operation Siting at the enterprise having continuous expertise of similar research reactor operation in long time Reactor should me implemented in the short timetable: its commissioning is planned in 2019 The main engineering approaches should be as a rule approbated and approved by application experience in practice The costs to solve the problem of fuel provision should be as low as possible due to using the fuel matrix and the fuel element design proven at other reactors It should be envisaged the achievement of a neutron flux in the reactor core of not less than 5.0 E15 cm-2 s-1 provided minimum necessary thermal reactor power MBIR experimental capabilities should as high as possible correspond with the current and prospective tasks and programs for creation of innovative projects of power reactors max 5.0*E15 min 4

5 Technical characteristics 1 refueling mechanism, 2 CPS actuators; 3 - ECh, 4 rotary plugs; 5 LCh; 6 rotary plug rotators; 7 - VEC; 8 primary pipelines; 9 HEC; 10 vessel and safeguard shroud; 11 FA; 12 radial reflector; 13 IRS Parameter Value Thermal power, MW ~150 Electric power, MW ~40 Maximum neutron flux, n/ cm -2 c up to Standard fuel Vibro-MOX, PuN+UN Experimental fuel Innovative fuel, fuel with MA Core height, mm 550 Maximum linear fuel heat rating, W/cm 470 Maximum annual neutron fluence, cm -2 ~ Service life, year 50 Number of independent loops with various coolants up to 5 (3 loop channels) Total number of experimental assemblies and irradiation devices for radioisotope production up to 14 in the core not limited in the side reflector Number of experimental channels up to 3 in the core Number of horizontal experimental channels (Ø 200 mm) up to 3 (outside the reactor tank) Number of vertical experimental channels (Ø 350 and 50 mm) up to 9 (outside the reactor tank) 5

6 6 MBIR core map FA; CM; ECh; MTA; SRA; IRSA; IRS shielding assemblies

7 Reactor core neutronic characteristics Parameter Value Fuel assemblies number 94 Effective core diameter, cm 88.8 Active length, cm 55 PuO2 share in fresh fuel, % up to 35 Fuel cycle, day 100 Maximum/average burn-up of discharged FA, % h.a. 8.0/10.3 Reactivity decrease in fuel cycle, % 2.9 Average FA power, MW 1.49 Maximum linear fuel heat rating, W/cm 470 Maximum/average core neutron flux, cm -2 s / Fast neutron (En>0.1 MeV) share in the core 0.7 7

8 Experimental device characteristics Experimental devices Location Number Instrumented material test and isotope production assemblies positions Non-instrumented material test and isotope production assemblies positions Experimental channels (ECh) for location of instrumented irradiation devices and/or channel-loop facilities Core SR Core Up to 14 Not limited Up to 3 Size at the core level, mm One core cell, width across flats - 72 One core cell, width across flats - 72 One core cell, width across flats - 72 Neutron flux in a cell, cm-2 s-1 Max Core average (3-4) LCh location positions Horizontal experimental channels (HEC) Vertical experimental channels (VEC) Core center, SR Outside the vessel Outside the vessel 1 Up to 2 Seven core cells Ø Up to 9 ~ ~ 50 8

9 Requirements to loop channels from the point of view of power reactor designers Parameter LCh-Na LCh-Pb LCh-Pb-Bi LCh-Gas (He) LCh-Salt Working fluid Sodium Lead Leadbismuth alloy Gas (high purity helium) Metal fluorides melt Neutron fluence in LCh, cm-2 s (2 3) (0.4 1) Up to Power, MW Up to Up to 0.8 Up to 0.15 Up to 0.15 External diameter, mm Fuel length MBIR core height MBIR core height MBIR core height Side reflector height MBIR core height Т in /Т out of working fluid, 0 С 320/550 Up to 350/ up to 750 Up to 350/ up to / 800 9

10 Experimental Potentialities 10

11 3D-model of MBIR reactor facility hot pipeline Т=547С 08Х16Н11М3-ВД EHX RCP-I IHX cold pipeline Т=354С 09Х18Н9 Reactor IHX intermediate heat exchanger; EHX emergency heat exchanger; RCP-I reactor coolant pump. 11

12 3D model of MBIR main building and equipment layout in the building MBIR equipment layout in the building Air heat exchanger RFM A RFM Ch MBIR main building RCP-I IHX Reactor RFM A refueling machine for assemblies RFM Ch refueling machine for channels 12

13 Conclusion 1. At present time, the first-level MBIR project implementation schedule has been approved, which defines the major project development stages MBIR reactor TA 2011 MBIR reactor concept design 2012 siting and construction license 2013 MBIR reactor standard design R&D program implementation contractual documentation and purchase manufacturing and erection 2018 commissioning and first criticality 2019 power start-up and decommissioning 2. Reactor MBIR: innovative tool for innovative research and advanced national and international projects support. 3. Planned commissioning

14 Thank for your attention! Power start-up and decommissioning Commissioning and first criticality Manufacturing and erection Contractual documentation and purchase R&D program implementation 14