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Generation IV Nuclear Power Plants

Generation IV Nuclear Power Plants. P M V Subbarao Professor Mechanical Engineering Department. Valuing the greenhouse gas emissions from A Rankine Cycle Systems ……. Generation IV Nuclear Power Plants. Generation IV designs will use fuel more efficiently, reduce waste production,

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Generation IV Nuclear Power Plants

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  1. Generation IV Nuclear Power Plants P M V Subbarao Professor Mechanical Engineering Department Valuing the greenhouse gas emissions from A Rankine Cycle Systems ……

  2. Generation IV Nuclear Power Plants • Generation IV designs will • use fuel more efficiently, • reduce waste production, • be economically competitive, • meet stringent standards of safety and • proliferation resistance. • Nearly100 experts evaluated 130 reactor concepts and selected six reactor technologies for further research and development. • These include the:   • Gas-cooled Fast Reactor (GFR) • Lead-cooled Fast Reactor (LFR) • Molten Salt Reactor (MSR) • Supercritical Water-cooled Reactor (SCWR) • Sodium-cooled Fast Reactor (SFR) and • Very High Temperature Reactor (VHTR).

  3. Technology Road Map

  4. Nuclear Pebbles

  5. Heat Transfer Model for Pebble

  6. Gas Cooled Reactors Gas Cooled Reactors (GCR) and Advanced Gas Cooled Reactors (AGR) use carbon dioxide or Helium as the coolant

  7. High temperature gas cooled reactors • High temperature gas cooled reactors (HTGR) offer an alternative to conventional light-water cooled and moderated reactors. • They use graphite as the moderator and helium as the coolant. • One design concept, called a pebble bed reactor, uses a fuel made of tennis-ball sized spheres known as "pebbles". • Each pebble contains thousands of tiny "kernels" consisting of enriched uranium and graphite compressed together and coated externally with temperature resistant ceramic. • The pebbles are stacked in the reactor and cooled by helium.

  8. Modular High-Temperature Gas-Cooled Reactor (MHGCR) : Test Plant –HTR-10 The reactor core contains about 27000 spherical fuel elements of 6 cm diameter. Form a pebble bed of 180 cm in diameter and 197 cm in average height. The mean power density is 2MW/m3. The reactor achieved its first criticality in December 2000. The helium temperature at the outlet of the core can reach up to 850C.

  9. Design of MHTGR-250 reactor • Based on the successful operation of HTR-10, a demonstration MHTGR plant coupling two reactor modules with a sub-C steam turbine set was designed. • The reactor is pebble bed, called MHTGR-250. • It is expected to have a thermal power of 250 MW under operating pressure of 7.0 Mpa. • Flow rate of Helium 96.2 kg/sec (346.3 t/h). • Helium inlet/outlet temperatures of 250/750°C. • The pressure drop of the primary loop was estimated to be 200 kPa. • Blowers are used to overcome the pressure drop. • Blowers consume nearly 4 MW power.

  10. Supercritical Rankine Cycles with MHGR

  11. Model – 2 :MHTGR Supercritical Power Plant

  12. MHGR as Steam generator • SG for the Live Steam Supplier : For the selected turbine set, the feedwater temperature is 283°C, while the SC steam parameters at SG outlet are 25.4 MPa/571°C. • For the helium side of SG, the inlet temperature is kept at 750°C to maintain 179°C temperature difference between the helium and the SC steam for effective heat transfer. • The outlet helium temperature is designed to 330°C to maintain effective heat transfer between the helium and the feedwater. • Although high steam pressure and temperature involves modifications of the once-through SG and relevant pipes, no additional difficulties in design and manufacture are expected.

  13. Reheat Exchanger for Reheat Steam Supply • For the selected turbine set, the steam parameters at the inlet of the reheat exchanger are 4.38 MPa/311°C and 4.19 MPa/569°C at the outlet. • For the helium side of reheat exchanger, the helium temperature at both inlet and outlet should be 350°C/750°C.

  14. Deployment mode of MHTGR SC plant with live steam reheat cycle

  15. Deployment mode of MHTGR SC plant with live steam reheat cycle

  16. Deployment mode of MHTGR SC plant with live steam reheat cycle

  17. Closing Remarks • The prospective deployments of MHTGR-250 SC plants can achieve a net plant efficiency of 45% or above. • At present and in the foreseeable future, the MHTGR-250 SC/ASC plants appear the prospective high efficiency NPP types. • Reference: Science and Technology of Nuclear Installations Volume 2008 (2008), Article ID 159083, 9 pages doi:10.1155/2008/159083

  18. Lead-Cooled Fast Reactor (LFR)

  19. Molten Salt Reactor (MSR)

  20. Sodium-Cooled Fast Reactor (SFR)

  21. Comparison of Life-Cycle Emissions Tons of Carbon Dioxide Equivalent per Gigawatt-Hour

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