nuclear plant systems
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ACADs (08-006) Covered
KeywordsNuclear power history, fission, steam supply, reactor types, plant operations and control, DBA, emergency systems, CFR,
Supporting Material
1.2.1.4 1.2.1.5 1.2.1.6 1.2.4.7 1.2.1.8 1.2.1.11 1.1.9.1.2
2.1.1.2 5.4.3.2
Power Plant Construction and QA/QC
Section 6 – Nuclear Plant Systems
Engineering Technology Engineering Technology DivisionDivision
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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
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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
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Section 6 – Nuclear Plant Systems
1943 - U.S. military developed nuclear reactors for the Manhattan Project
1951 - "World's first nuclear power plant" is EBR-1, Experimental Breeder Reactor
Introduction – 6.1 - History
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Section 6 – Nuclear Plant Systems
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)
Introduction – 6.1 - History
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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)
Introduction – 6.1 - History
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Section 6 – Nuclear Plant Systems
Introduction – 6.1 – History – US Plants
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Questions?
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Section 6 – Nuclear Plant Systems
Fission Theory – 6.2
1. Thermal Neutron generated from fission or decay2. 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 thermalized7. Thermal Neutron absorbed by 92U235 or 93Pu239
8. Fission fragment decays9 .First excited daughter decays10. Fast neutron produced11. Fast neutron absorbed by 92U238
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2 3
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10
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Heat
Decay Heat
Decay Heat
Heat
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Section 6 – Nuclear Plant Systems
143 + 90 = 233
Fission Theory – 6.2
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Questions?
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Section 6 – Nuclear Plant Systems
Nuclear Steam Supply Systems – 6.3
NSSS – Main and Support systems needed to generate steam for turbine.
BWR
PWR
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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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Section 6 – Nuclear Plant Systems
Nuclear Steam Supply Systems – 6.3 – World Locations
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Section 6 – Nuclear Plant Systems
Nuclear Steam Supply Systems – 6.3
Questions?
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Section 6 – Nuclear Plant Systems
Nuclear Plant Operation, Maintenance and Control – 6.4
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Section 6 – Nuclear Plant Systems
ContaminationRadiationContamination and Radiation
Nuclear Plant Operation, Maintenance and Control – 6.4
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Section 6 – Nuclear Plant Systems
Nuclear Plant Operation, Maintenance and Control – 6.4
ContaminationRadiationContamination and Radiation
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Section 6 – Nuclear Plant Systems
Questions?
Nuclear Plant Operation, Maintenance and Control – 6.4
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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 & PWRLOFA – Loss of Flow Accident – BWR & PWRLOPA – Loss of Pressure Accident – PWRSeismic Event – Earthquake – BWR & PWRContainment – Outside Penetration – BWR & PWR
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Section 6 – Nuclear Plant Systems
• 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
Reactor Safety – 6.5 – Design Basis Accidents - Criteria
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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
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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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Section 6 – Nuclear Plant Systems
Reactor Safety – 6.5 – Design Basis Accidents - Systems
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Section 6 – Nuclear Plant Systems
Reactor Safety – 6.5 – Design Basis Accidents - Systems
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Section 6 – Nuclear Plant Systems
Reactor Safety – 6.6 – Regulations
CFR – Code of Federal Regulations
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Section 6 – Nuclear Plant Systems
Reactor Safety – 6.6 – Regulations
CFR – Code of Federal Regulations, Title 10
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Section 6 – Nuclear Plant Systems
Reactor Safety – 6.6 – Regulations
CFR – Code of Federal Regulations, Title 10, Part ??
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Questions?
Section 6 – Nuclear Plant Systems
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