Nuclear Plant Systems Overview and Reactor Safety

1. Engineering Technology Division Power Plant Construction and QA/QC Section 6 – Nuclear Plant Systems

2. Section 6 – Nuclear Plant Systems Overview • Nuclear Power testing began in 1934 in Germany and 1942 in the US • Nuclear Power Generation began in 1956 in England • Nuclear Power generates about 20% of the electricity in the US • Nuclear Power generates heat through fission of uranium and decay of fission products • Nuclear renaissance has started

3. Section 6 – Nuclear Plant Systems Introduction – 6.1 - History 1933 – Chain Reaction realized by Leo Szilard 1942 - First artificial nuclear reactor, Chicago Pile 1, at the University of Chicago

4. Section 6 – Nuclear Plant Systems Introduction – 6.1 - History 1943 - U.S. military developed nuclear reactors for the Manhattan Project 1951 - "World's first nuclear power plant" is EBR-1, Experimental Breeder Reactor

5. Section 6 – Nuclear Plant Systems Introduction – 6.1 - History 1953 – Eisenhower Atoms for Peace Speech to UN 1954 – First nuclear power plant built for civil purposes was the AM-1 in Soviet Union (graphite) 1955 – First nuclear powered vehicle, US Navy submarine, the USS Nautilus (PWR)

6. Section 6 – Nuclear Plant Systems Introduction – 6.1 - History 1956 - The first commercial nuclear power station, Calder Hall in Sellafield, England (50 MW) 1961 – SL-1 Accident, Idaho, PWR/BWR cross 1961 – Dresden Unit1, first privately owned commercial reactor (210 MW)

7. Section 6 – Nuclear Plant Systems Introduction – 6.1 – History – US Plants

8. Section 6 – Nuclear Plant Systems Questions?

9. Section 6 – Nuclear Plant Systems Fission Theory – 6.2 Heat 5 6 7 1 Heat 4 2 3 10 Decay Heat 1. Thermal Neutron generated from fission or decay 2. Thermal Neutron absorbed by 92U235 or 93Pu239 3. Compound (or excited) 92U235 or 93Pu239 4. Atom splits creating two fragments – mass conversion to energy. 5. Fast neutrons produced. 6. Fast neutron has thermalized 7. Thermal Neutron absorbed by 92U235 or 93Pu239 8. Fission fragment decays 9 .First excited daughter decays 10. Fast neutron produced 11. Fast neutron absorbed by 92U238 8 11 10 9 Decay Heat

10. Section 6 – Nuclear Plant Systems Fission Theory – 6.2 143 + 90 = 233

11. Section 6 – Nuclear Plant Systems Questions?

12. Section 6 – Nuclear Plant Systems Nuclear Steam Supply Systems – 6.3 BWR PWR NSSS – Main and Support systems needed to generate steam for turbine.

13. Section 6 – Nuclear Plant Systems Nuclear Steam Supply Systems – 6.3 – Reactor Types • PWR – Light Water – Westinghouse, Framatome • PWR – Heavy Water – CANDU - Canada • BWR – Light Water – GE, Toshiba • RBMK – Light Water Graphite – Soviet Union (now Russia) • GCR – Gas Cooled Reactor – England • LMFBR – Liquid Metal (Sodium) Breeder – United States • LMFBR – Liquid Metal (Lead) Breeder – Soviet Union (Russia) • MSRE – Molten Salt – United States • PBR – Pebble Bed – US Lead Design • Natural Reactor – Oklo mine in Gabon, West Africa • Fusion Reactor – The Sun

14. Section 6 – Nuclear Plant Systems Nuclear Steam Supply Systems – 6.3 – World Locations

15. Section 6 – Nuclear Plant Systems Nuclear Steam Supply Systems – 6.3 Questions?

16. Section 6 – Nuclear Plant Systems Nuclear Plant Operation, Maintenance and Control – 6.4

17. Section 6 – Nuclear Plant Systems Nuclear Plant Operation, Maintenance and Control – 6.4 Contamination Radiation Contamination and Radiation

18. Section 6 – Nuclear Plant Systems Nuclear Plant Operation, Maintenance and Control – 6.4 Contamination Radiation Contamination and Radiation

19. Section 6 – Nuclear Plant Systems Nuclear Plant Operation, Maintenance and Control – 6.4 Questions?

20. Section 6 – Nuclear Plant Systems Reactor Safety – 6.5 – Design Basis Accidents A design basis accident (DBA) or maximum credible accident (MCA) is a postulated accident that a nuclear facility must be designed and built to withstand and not lose any systems, structures, and components necessary to assure public health and safety. LOCA – Loss of Coolant Accident – BWR & PWR LOFA – Loss of Flow Accident – BWR & PWR LOPA – Loss of Pressure Accident – PWR Seismic Event – Earthquake – BWR & PWR Containment – Outside Penetration – BWR & PWR

21. Section 6 – Nuclear Plant Systems Reactor Safety – 6.5 – Design Basis Accidents - Criteria • Fuel cladding temperature must not exceed 2192 F • The local fuel cladding oxidation must not exceed 18% of the initial wall thickness • The mass of Zirconium converted into ZrO2 must not exceed 1% of the total mass of cladding • The whole body dose to a member of the staff must not exceed 5 REM per year • Critical organ (i.e., thyroid) dose to a member of the staff must not exceed 30 REM

22. Section 6 – Nuclear Plant Systems Reactor Safety – 6.5 – Design Basis Accidents - Systems • Reactor Protection Systems • Control Rod. • Safety Injection – Boric Acid, Standby Liquid Control – Potassium Pentaborate • Essential Service Water System • Flooding – Large Volumes – up to 50,000 gpm • Emergency Core Cooling Systems • High and Low Pressure – 3,000 to 30,000 gpm • Ventilation • Control Room • Containment

23. Section 6 – Nuclear Plant Systems Reactor Safety – 6.5 – Design Basis Accidents - Systems • Electrical Emergency Systems • Diesel Generator • Batteries • Containment Systems • Reactor Vessel • Primary Containment – Reactor Compartment, Drywell • Secondary Containment – Reactor Building • Standby Gas Treatment • Fission Products • Hydrogen Gas

24. Section 6 – Nuclear Plant Systems Reactor Safety – 6.5 – Design Basis Accidents - Systems

25. Section 6 – Nuclear Plant Systems Reactor Safety – 6.5 – Design Basis Accidents - Systems

26. Section 6 – Nuclear Plant Systems Reactor Safety – 6.6 – Regulations CFR – Code of Federal Regulations

27. Section 6 – Nuclear Plant Systems Reactor Safety – 6.6 – Regulations CFR – Code of Federal Regulations, Title 10

28. Section 6 – Nuclear Plant Systems Reactor Safety – 6.6 – Regulations CFR – Code of Federal Regulations, Title 10, Part ??

29. Section 6 – Nuclear Plant Systems Questions?