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TMI-2 containment building accident water sampling and reactor primary coolant accident source term

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6792007
None
Research Organization:
NRC, Washington, DC 20555
OSTI ID:
6792007
Report Number(s):
CONF-811103-
Conference Information:
Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 39
Country of Publication:
United States
Language:
English

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Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
CONTAINMENT
CONTAINMENT BUILDINGS
COOLANTS
DAMAGE
ENRICHED URANIUM REACTORS
ISOTOPES
LOSS OF COOLANT
POWER REACTORS
PWR TYPE REACTORS
RADIOISOTOPES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTORS
SAMPLING
SYSTEMS ANALYSIS
THERMAL REACTORS
THREE MILE ISLAND-2 REACTOR
WATER COOLED REACTORS
WATER MODERATED REACTORS