NUCE 402: Introduction to Nuclear System and Operation Lecture Notes PDF

NUCE 402: Introduction to Nuclear System and Operation Chapter 1-3: Advanced PWR and BWR, Gen-IV reactors Dr. Ahmed Alkaabi Evolutionary PWR & BWR Background  Increase in construction cost  Increased requirement for safety Passive safety system  Gravi...

NUCE 402: Introduction to Nuclear System and Operation Chapter 1-3: Advanced PWR and BWR, Gen-IV reactors Dr. Ahmed Alkaabi Evolutionary PWR & BWR Background  Increase in construction cost  Increased requirement for safety Passive safety system  Gravity  Temperature System Simplification + Constructability  System 80+ by CE  EPR1600  APR1400  ABWR (Advanced Boiling Water Reactor) by GE Advanced Passive Cooling System  Advanced Passive 600 (AP600) & AP1000 by Westinghouse  ESBWR (Economic Simplified Boiling Water Reactor) by GE  The Evolutionary and Advanced Light water Reactor System 80+ PWR by ABB/CE  Large spherical double wall Concrete and steel containment-steam expansion space and heat sink Larger water inventory in Primary 33% bigger pressurizer 25% bigger secondary side The Evolutionary and Advanced Light water Reactor Advanced Boiling Water Reactor(ABWR) by GE  Centrifugal pump internal to RXV Minimizing the risk of LOCA The Evolutionary and Advanced Light water Reactor Advanced Passive 600Mwe PWR by Westinghouse  Passive containment cooling Ultimate heat sink for the decay heat In the event of a LOCA 30% larger pressurizer AP600 Figure 4.15 Cutaway drawing of the AP600 containment. (Courtesy of Westinghouse Electric.) Figure 4.16 AP600 primary system. (Courtesy of Westinghouse Electric.) The Evolutionary and Advanced Light water Reactor Simplified Boiling Water Reactor(SBWR) by GE  The gravity-driven cooling system(GDCS) Natural circulation of the reactor coolant No Pumps in RXV  Passive containment cooling system(PCCS)  Automatic depressurization system(ADS) TAF Figure 4.18 Water level prediction in the SBWR from a LOCA simulation Breeder Reactors Fuel: 235U  238U 238U/ 232Th 239Pu/ 233U Types of breeder reactors  LMFBR: the Liquid metal Cooled Fast Breeder Reactor  GCFR: the Gas Cooled Fast Breeder Reactor  MSBR: the Molten Salt Breeder Reactor  LWBR: the Light Water Breeder Reactor https://www.youtube.com/watch?v=ax1QQyEVW3o  Liquid Metal Fast Breeder Reactor LMFBR  Liquid metal : Na, K Advantage Disadvantage – No elastic scattering-no slow down of neutron – Melting point (98oC) – Good heat transfer – Highly chemically reactive – High boiling point (882oC at 1 atm) – Neutron absorption-24Na-radioactive – No corrosion Experience- Significant commercialization stage Super Phenix (Fr.) : Pool-type Monju (Japan) (280MWe) : Loop-type Fuel High enriched fuel : 15~35% Stainless steel cladding Steam ~500C, 16~18MPa Efficiency ~ 40%  Breeder Reactors- LMFBR Two types of LMFBR Pool type-super phenix in French (1976-1986-1997) R.I.P Loop type-Monju in Japan (1986-1995-2016) Breeder Reactors- GCFR  From HTGR  Fuel: a mixture of PuO2 and UO2  Core: similar to core of an LMFBR  The helium pressure: 10.5 MPa.  Inlet: 298oC and Outlet: 520oC  No radioactive of coolant Figure 4.30 Cross-section of a gas-cooled fast reactor. (Courtesy of General Atomic Company.)  Breeder Reactors-MSBR A thermal breeder :233U-Thorium cycle  233U: the only fissile isotope capable of breeding in thermal reactor.  Mixture of fertile material and coolant(various fluoride salts) Melt to clear, non-viscous fluid. Very small thermal neutron absorption cross section Good heat transfer, low vapor pressure at high temperature No damage by radiation, chemically stable. 233 Pa must be removed Good neutron economy Overall efficiency:~44% at 24MPa and 540oC  Drawback: maintenance and repair Pa: protactinium Breeder Reactors- LWBR Fuel: 233U By reducing the amount of water relative to fuel in the core Shifting the energy spectrum of the neutrons Strict control of losses of neutrons Enough excess 233U to compensate for the loss of 233U Technical feasibility was confirmed at shippingport,USA. LWBR core cross section Typical LWBR fuel module cross-section  Gen IV - Technology Introduces six Generation IV systems chosen by the Generation IV International Forum for further development  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) Surveys system-specific R&D needs for all six systems Collects crosscutting R&D needs  Design and evaluation methods, materials, energy conversion December 2002 Gen IV Nuclear Energy Systems Closed Fuel Closed Fuel Closed Fuel Cycle Cycle Cycle Sodium Fast reactor Lead Fast Reactor Gas Fast Reactor Once Through Once/Closed Closed Fuel Cycle Very High Temperature Reactor Supercritical Water Reactor Molten Salt Reactor  Gen-IV - Demonstration Gen IV Top Priority Next-Generation Nuclear Plant VHTR + H2 NGNP (US) Collaborative with international community NHDD (Kor.) Collaborative with industry, especially utilities Demonstrate H2 and direct-cycle electricity production Result in a commercially viable plant design Gen IV Second Priority  GFR Fast Reactor Closely  LFR coordinated with Advanced  SFR Fuel Cycle Initiative  MSR  SCWR SFR : Gen IV - Technology Roadmap  Candidate Reactor for Global Nuclear Energy Partnership (GNEP)  Reduce spent fuel  Burn trans-U with long half-lives  VHTR : Gen IV - Technology Roadmap  Candidate Reactor for Nuclear Hydrogen Program  Very high temp. needed for H-production  Co-generation & process heat utilization options Gen IV - Technology Roadmap Gen IV Neutron Recycle Process Outlet Temp. Coolant Fuel Systems Spectrum (Reprocessing) (℃)/Pressure U-238/Pu Aqueous (or GFR Fast Gas 850 /high Carbide Pyro) Pb, or U-238/Pu LFR Fast Pyro 550~800/ low Pb/Bi Metal/Nitride UF in salt MSR Thermal Salt Salt process 700 /low Fluoride U-238 SFR Fast Na Pyro/Aqueous 550/low Metal/ MOX Thermal/ Supercritical UO2 SCWR Aqueous 550/very high Fast water Oxide UO2 VHTR Thermal Gas Once-through 1000/ high Oxide Small Modular Reactor  Homework#1  Due date: one week before class