Potentially buoyant releases at TMI-1 (Three Mile Island Unit 1): Source term and steam properties
Conference
·
· Transactions of the American Nuclear Society; (USA)
OSTI ID:5264861
The Emergency Dose Calculation Model for Three Mile Island-Unit 1 (TMI-1) was recently revised to take into account the guidance of NUREG/CR-3354: Potentially Buoyant Releases at Boiling and Pressurized Water Reactors. This guidance was applied to the modeling of radioactive steam releases from the main steam relief valves and atmospheric dump valves at TMI-1. This paper presents an overview of the modeling of the steam release, starting with the calculation of steam flow rate at the valve inlet and ending with the ejection of the steam into the atmosphere.
- OSTI ID:
- 5264861
- Report Number(s):
- CONF-890604--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (USA) Journal Volume: 59
- Country of Publication:
- United States
- Language:
- English
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Potentially buoyant releases at TMI-1 (Three Mile Island Unit 1): Plume rise and off-site doses
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MARCH calculations performed for the TMI-2 (Three Mile Island Unit) analysis exercise program
Conference
·
Sat Dec 31 23:00:00 EST 1988
· Transactions of the American Nuclear Society; (USA)
·
OSTI ID:5321552
Experimenting with sodar in support of emergency preparedness at Three Mile Island-1
Conference
·
Sat Dec 31 23:00:00 EST 1988
· Transactions of the American Nuclear Society; (USA)
·
OSTI ID:6835351
MARCH calculations performed for the TMI-2 (Three Mile Island Unit) analysis exercise program
Conference
·
Thu Dec 31 23:00:00 EST 1987
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5684167
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
54 ENVIRONMENTAL SCIENCES
540130 -- Environment
Atmospheric-- Radioactive Materials Monitoring & Transport-- (1990-)
ATMOSPHERIC CIRCULATION
BOILERS
CONTROL EQUIPMENT
DOSES
ENRICHED URANIUM REACTORS
EQUIPMENT
FAILURES
FLOW RATE
FLOW REGULATORS
MATHEMATICAL MODELS
NATIONAL ORGANIZATIONS
POWER REACTORS
PRESSURE DEPENDENCE
PWR TYPE REACTORS
RADIATION DOSES
REACTOR SAFETY
REACTORS
RECOMMENDATIONS
RELIEF VALVES
SAFETY
SOURCE TERMS
STEAM
STEAM GENERATORS
THERMAL REACTORS
THREE MILE ISLAND-1 REACTOR
TUBES
US NRC
US ORGANIZATIONS
VALVES
VAPOR GENERATORS
VELOCITY
VOLATILITY
WATER COOLED REACTORS
WATER MODERATED REACTORS
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Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
54 ENVIRONMENTAL SCIENCES
540130 -- Environment
Atmospheric-- Radioactive Materials Monitoring & Transport-- (1990-)
ATMOSPHERIC CIRCULATION
BOILERS
CONTROL EQUIPMENT
DOSES
ENRICHED URANIUM REACTORS
EQUIPMENT
FAILURES
FLOW RATE
FLOW REGULATORS
MATHEMATICAL MODELS
NATIONAL ORGANIZATIONS
POWER REACTORS
PRESSURE DEPENDENCE
PWR TYPE REACTORS
RADIATION DOSES
REACTOR SAFETY
REACTORS
RECOMMENDATIONS
RELIEF VALVES
SAFETY
SOURCE TERMS
STEAM
STEAM GENERATORS
THERMAL REACTORS
THREE MILE ISLAND-1 REACTOR
TUBES
US NRC
US ORGANIZATIONS
VALVES
VAPOR GENERATORS
VELOCITY
VOLATILITY
WATER COOLED REACTORS
WATER MODERATED REACTORS