Reaktor Nuklir Generasi IV

Transcription

1 Reaktor Nuklir Generasi IV Dr. Eng. Pribadi Mumpuni Adhi Politeknik Negeri Jakarta

2 Tujuan Sustainability - Providing sustainable energy that meets clean air objectives, gives long-term availability of systems and effective fuel utilization for worldwide energy production. Also to minimize and manage waste, thereby improving protection for the public and the environment. Economics -Compared to the other energy resources it should have life cycle cost advantage, and the level of financial is comparable to other energy projects. Safety - The reactors will excel in safety and reliability; there will be very low likelihood of core damage, along with minimized severity in the case of an accident. Emergency response systems will be optimized and will not require offsite emergency response. Proliferation Resistance - The reactor's use and processing of nuclear fuel will increase the assurance of materials being unattractive for theft and terrorism, along with a physical protection system to prevent the fuel from ending up in the wrong hands. 2

3 Generasi Reaktor Nuklir 3

4 Tipe Reaktor Gas cooled fast reactor (GFR) Lead cooled fast reactor (LFR) Sodium cooled fast reactor (SFR) Molten salt reactor (MSR) Supercritical water cooled reactor (SCWR) Very high temperature reactor (VHTR) 4

5 Neutron spectrum (fast/ther mal) Coolant Temperature ( C) Pressure* Fuel Fuel cycle Size (MWe) Use Gas-cooled fast reactors fast helium 850 high U closed, on site 1200 electricity & hydrogen Lead-cooled fast reactors fast lead or Pb-Bi low U closed, regional ** electricity & hydrogen Molten salt fast reactors fast fluoride salts low UF in salt closed 1000 electricity & hydrogen Molten salt reactor - advanced hightemperature reactors Sodium-cooled fast reactors thermal fluoride salts fast sodium low UO 2 particles in prism. U-238 & MOX open hydrogen closed electricity Supercritical water-cooled reactors thermal or fast water very high UO 2 (thermal) open closed (fast) electricity Very high temperature gas reactors thermal helium high UO 2 prism or pebbles open hydrogen & electricity 5

6 Nuclear Fuel Cycle 6

7 Lead-cooled Fast Reactor 7

8 Inherent and Passive Safety Features of LFR Larger scattering cross section High neutron confinement performance, Better neutron economy, Large fuel P/D High performance of Pb-208 due to low capture cross section (See GLABAL 2011 Paper No , Pb-208 is the final stable nucleus in Th decay chain) Pb-206 is low activation coolant (See ICONE-8385) Heavy nuclide mass Low moderating power Hard spectrum Negative coolant void coefficient, Better MA burning capability Low burn-up reactivity swing Long life core Higher boiling temperatures No coolant boiling in transient conditions 8

9 Inherent and Passive Safety Features of LFR Chemical inertness with water and air No chemical reaction, No hydrogen generation and fire Lowest stored potential energy compared with water and sodium No release of chemical / mechanical energy, No vaporization and pressurization Heavy coolant Lift-up and dispersion of fuel pellets Avoid of re-critical accident 9

10 Additional Advantages of LFR Large scattering cross section of lead Good neutron confinement Smaller core size Large shielding effects for neutrons and γ-rays Reduction of thickness of reflectors and shields Large fuel P/D High level of natural circulation capability No production of γ-ray emitters Much lower dose-rate around primary loops γ-ray emitter (Na-24 : half-life of 15 h) in SFR Heavy coolant Lift force of gas/steam bubbles Capability of coolant circulation without pumps 10

11 Drawbacks of LFR Production of alpha-ray emitter, Po-210 from neutron irradiation of Bi & Pb Need of Po-210 measure High solubility of Ni, Fe, etc. Need of material corrosion measure Very heavy coolant Restriction of reactor size / Need of seismic measure/ Erosion measure (<2m/s) Melting temperature of Pb (327 C) High operation temperature Bi resource is not abundant Selection of lead (Pb) rather than LBE (Pb-Bi) 11

12 1 Concept of LSPR studied in 1990s (LBE-cooled long-life Safe Simple Small Portable Proliferation resistant Reactor) Long life core Small reactors are constructed in factories of the nuclear energy park, Transported to the site, and deployed. Sealed reactor vessel without being opened at the site. Excellent proliferation resistance in refueling -At the end of the reactor life, it is replaced by a new one. The old one is shipped to the nuclear energy park. Environment -No radioactive waste left at the site. (Site is free from waste problems.) Steam generator Core LSPR Control rod 12 Pump

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15 2 Small, Sealed, Transportable, Autonomous Nuclear Reactor (SSTAR) 15

16 3 Development Phases of Heavy Liquid Metal Coolant (HLMC) in Russia 1951 The first Pb-Bi circulation test facility (IPPE) 1963 The first nuclear submarine K-27 (Project 645 using Pb-Bi coolant 1971 Nuclear submarines (Projects 705 and 705K) using Pb-Bi coolant 2013 Development of SVBR-100 and BREST-OD-300 using Pb-Bi and Pb coolants is continued

17 The 1st experience of heavy liquid metal coolant technology in Russia Typical examples of slag deposition at the 1st phases of Pb-Bi coolant development ( ) The 1st nuclear submarine K-27 (Project 645) using Pb-Bi coolant Commissioning 1963 Accident 1968 Cause of accident melting of fuel elements in reactor core due to deterioration of heat exchange due to slag deposition Slag deposition on the inner surface of pipe Slag deposition in heat-exchange assembly Compositions in slag (%) (based on the samples analyzed) Fe Cr Ni O 2 Pb Bi 4,0x ,9 2,0x ,7 2,0x ,2 0,9-2, Slag deposited on the surface of heatexchange tubes of recuperator

18 Reaktor Daya Experimental (RDE) 18

19 Download Materi Kuliah 19