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LW SMR technology development. Think different…

LW SMR technology development. Think different…. Design, technology and innovations. Safety. (Second edition) ID - OR USA 2013. Pre-words and Abbr … :. SMR – Small Modular Reactor LOFA – Loss of Flow Accident Rr (s) – (Nuclear) R eactor(s) LOCA – Loss of Coolant Accident

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LW SMR technology development. Think different…

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  1. LW SMR technology development. Think different… Design, technologyandinnovations. Safety. (Second edition) ID - OR USA 2013

  2. Pre-words and Abbr… : SMR – Small Modular Reactor LOFA – Loss of Flow Accident Rr(s) – (Nuclear)Reactor(s) LOCA – Loss of Coolant Accident NPP – (Naval) Nuclear Propulsion Plant LOHS – Loss of Heat Sink FNPP – Floating Nuclear Power Plant CHF – Critical Heat Flux (I or II) PP – Power Plant FE– Fuel Element (or pin) LW SMR– Light Water SMR FI – Flow instabilities SCWR– Super-Critical Water Reactor GEN – Generation (for Rr(s)) LMR– Liquid Metal Reactor D/S – dimensions and sizes HTGR– High-Temperature Gas cooled RrPCS – Primary Circuit System SG – Steam Generator SCS – Secondary Circuit System ConOps – Conception of Operations h/e(s) – heat exchanger(s) BNT – (design) based on Naval Technology SL – Safety Limits

  3. Talking about LW SMR: • SMR Worldwide • SMR Historical aspect (SU-Ru only) • SMR Conception Y/N • SMR Different designs • Development reasons • SMR RV dimensions • SMR Safety analysis • SMR Road map? And: Perspective for new step to G5?

  4. 1. SMR Worldwide: Place SMRs in the reactors World fleet: • Experimental and Researches Rr(s) – 750 • Naval Rr(s) – (USSR - Russia 490, USA~ 270, etc.~ 30) • Power Rr(s) – 440 (+140) in building, licensing, design or planning) We can not ignore naval experience in design, development SMR…

  5. 2.1. History (SU-Ru only):

  6. 2.2. History (SU-Ru NIB only):

  7. 3. SMR conception Y/N? SMR in the modern and right/correct understanding: • Small – From 3 aspects of D/S: compact Rr design, PP constructional sizes, and site size (not including resources) • Relatively Modular – From 2 aspects of modularity: in Rr and main components (Rr interns) design, and modularity mostly in PP • Advanced design? (core - 40 y/old, SG, h/e(s), s-systems today) • In-depth & advanced Rr passive safety for reactor and systems(?) • Modern technology and advanced project process (soft, simulations scientific and training – Yes, and…) … but, not only something else: • New materials (core, SG, h/e(s)). We are in XXI century… • Advanced Rr operating algorithms and developed ConOps • Reliability and Economy. Parameters and PP SMR efficiency? • Decommission process from first design steps…

  8. 4. Different designs concepts: Ways for SMR development projects today: • From Large Power Reactors (> USA) • From Naval reactors and systems (> Russia) • Independent projects based on own and exported new/advanced technology, and designs (Argentina, China, Korea, India, etc., all “sponge” -countries) Type of SMR perspective for today and or tomorrow: • LMR – perspective for 20… and up to… • HTGR– perspective for 20… and up to… • LW SMR– next 40… 50 yrs • SCWR– perspective 20… and up to… • Etc.

  9. 5. SMR development reasons: SMR development reasons for today (?): • Decentralized electrical-grids development as part of Energy National Security Policy (USA) • North and Fare East territories development(Russia, Canada, USA-?). Example: 4 DCV via North-Iced Ocean in 2011, 46 in 2012, 372 in 2013 (at least 15 days shorter voyage) • New technology and industry development (USA - ?, Argentina, China, Korea, India, and other developing countries). 08/12/2013 first Naval LW PWR in India and Argentinian project - critical aspect for development

  10. 6. SMR dimensions: Reactors, SG and containments approximate D/S (w/out main and supporting systems): • NuCore (BNT project + decommission cont.)* • mPower (reactor only) • NuScale • Regular LWR:

  11. 7. LW SMR Safety analysis: 7.1. LW SMR SL problem statement: 7.2. LW SMR SL classification diagram(s): 7.3. Core/Fuel SL and new fuel options: 7.4. H-T vs. T-H, flow regimes, FI and SL: 7.5. LW SMR NC and nointerferences aspects: 7.6. LW SMR operating& control aspects: 7.7. LW SMR NC design specials:

  12. 7.1. LW SMR SL statement: What happened after …? This happened because … Core Safety aspects: Power & WR Tau Control Systems: Ro Reactor C-Sys Other C-sys CHF I Fair Etc. Rr. Safety aspects: T1C M-flow LOFA External events: Seismic A-Crash LOHS-LOFA PCS Safety aspects: P1C H1C LOCA Ops & control Human factor: Plans? Design SCS Safety aspects: T2C P2C P FW PP Sub-Sys safety: P4C P-loss: Com E-Powr DG E-Powr BB E-Powr

  13. 7.2. LW SMR SL diagram:

  14. 7.3. Core/Fuel SL and new fuel:

  15. 7.4. H-T vs. T-H & flow regimes:

  16. 7.5. LW SMR NC and no:

  17. 7.6. LW SMR operating/control:

  18. 7.7. LW SMR NC design:

  19. 8. SMR development R-map: Main problems and/or issues for inventors, designers, scientists: • Fuel composition – UO2(new reactors with >35 y/old feel) substitution to different matrix and type as alternative Si+C (?) • Fuel cladding – Zr-cladding substitution to SS and alloys, or Si+C (?) • Core configuration and design – “standard/well known” core is not acceptable for NC… • SG design – d-Pressure through 1C and 2C and S-Sys always problems • Rr(s) sizes and dimensions – +/- • Reactor control and operating algorithms development and optimizations … • ConOps (PP with SMR operating procedures) … • Parameters 1C and 2C optimizations … • Economical (efficiency) problems solutions … • Licensing … (no good examples here)

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