1. Nuclear Plant Systems ACADs (08-006) Covered Keywords
Nuclear power history, fission, steam supply, reactor types, plant operations and control, DBA, emergency systems, CFR,
Supporting Material
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2. Power Plant Construction and QA/QC Section 6 – Nuclear Plant Systems
Engineering Technology Division
Power Plant Construction and QA/QC
Section 6 – Nuclear Plant Systems

3. 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

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

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

6. Section 6 – Nuclear Plant Systems
Introduction – 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)

7. Section 6 – Nuclear Plant Systems
Introduction – History
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)

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

9. Section 6 – Nuclear Plant Systems
Questions?

10. 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

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Fission Theory – 6.2
= 233

12. Section 6 – Nuclear Plant Systems
Questions?

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

14. 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

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Nuclear Steam Supply Systems – 6.3 – World Locations

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Nuclear Steam Supply Systems – 6.3
Questions?

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

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
Contamination
Radiation
Contamination and Radiation

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

21. 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

22. 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

23. 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

24. 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

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Reactor Safety – 6.5 – Design Basis Accidents - Systems

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

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

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

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

30. Section 6 – Nuclear Plant Systems
Questions?