Dynamics and Seismic Issues in primary and secondary systems
Conference
·
OSTI ID:7013256
- General Electric Co., San Jose, CA (US)
- Univ. of California, Berkeley, CA (US)
his book contains the papers presented at the conference held in Pittsburgh, on the subject of pressure vessels and piping systems. Topics discussed were: dynamics of MDF secondary systems; impacting effects of seismic loading in feeder pipes of PHWR plants; random vibration methods for the seismic qualification of secondary systems; interaction in primary-secondary systems; and system response through novel applications of transfer function.
- OSTI ID:
- 7013256
- Report Number(s):
- CONF-8806210--
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210400 -- Power Reactors
Nonbreeding
Otherwise Moderated or Unmoderated
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ABSTRACTS
CONTAINERS
COOLING SYSTEMS
DOCUMENT TYPES
DYNAMIC LOADS
ENERGY SYSTEMS
HEAVY WATER COOLED REACTORS
HEAVY WATER MODERATED REACTORS
INTERACTIONS
LEADING ABSTRACT
MEETINGS
PHWR TYPE REACTORS
PIPELINES
PRESSURE VESSELS
PRIMARY COOLANT CIRCUITS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
SECONDARY COOLANT CIRCUITS
SEISMIC EFFECTS
210400 -- Power Reactors
Nonbreeding
Otherwise Moderated or Unmoderated
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ABSTRACTS
CONTAINERS
COOLING SYSTEMS
DOCUMENT TYPES
DYNAMIC LOADS
ENERGY SYSTEMS
HEAVY WATER COOLED REACTORS
HEAVY WATER MODERATED REACTORS
INTERACTIONS
LEADING ABSTRACT
MEETINGS
PHWR TYPE REACTORS
PIPELINES
PRESSURE VESSELS
PRIMARY COOLANT CIRCUITS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
SECONDARY COOLANT CIRCUITS
SEISMIC EFFECTS