NUREG-1150 methodology overview
Conference
·
OSTI ID:5897542
The Nuclear Engineering Department of National Tsing Hua University organized a workshop on Severe Accident Management. The workshop was sponsored by Taiwan Power Company and was held at Taipei, Taiwan from July 31 to August 11, 1989. The topics covered in the workshop included the general in-vessel LWR severe accident phenomena, containment responses and performances under severe accident conditions, results of Level 1 PRAs of three Nuclear Power Plants at Taiwan, and also two lectures related to the NUREG-1150 report just published by US NRC. This presentation covers these two lectures.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (USA)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 5897542
- Report Number(s):
- SAND-89-1863C; CONF-8908123-1-Vugraphs; ON: DE89016368
- Country of Publication:
- United States
- Language:
- English
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Wed Dec 31 23:00:00 EST 1986
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SURRY-2 REACTOR
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Light-Water Moderated
Boiling Water Cooled
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Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
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A CODES
ACCIDENTS
ASIA
BWR TYPE REACTORS
C CODES
COMPUTER CODES
CONTAINMENT
DISEASES
DOSES
ECONOMICS
EMERGENCY PLANS
ENRICHED URANIUM REACTORS
FAILURE MODE ANALYSIS
FISSION PRODUCT RELEASE
GAS COOLED REACTORS
GRAND GULF-1 REACTOR
GRAND GULF-2 REACTOR
GRAPHITE MODERATED REACTORS
H CODES
HAZARDS
HEALTH HAZARDS
HELIUM COOLED REACTORS
HTGR TYPE REACTORS
ISLANDS
ISOTOPES
L CODES
M CODES
MANAGEMENT
NEOPLASMS
P CODES
PEACH BOTTOM-1 REACTOR
PEACH BOTTOM-2 REACTOR
PEACH BOTTOM-3 REACTOR
POWER REACTORS
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RADIOACTIVITY TRANSPORT
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REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
REGULATIONS
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S CODES
SAFETY
SEQUOYAH-1 REACTOR
SEQUOYAH-2 REACTOR
SOURCE TERMS
SURRY-1 REACTOR
SURRY-2 REACTOR
SURRY-3 REACTOR
SURRY-4 REACTOR
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
T CODES
TAIWAN
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
X CODES
ZION-1 REACTOR
ZION-2 REACTOR