Codes and standards and applications for design and analysis of pressure vessel and piping components 1990
Conference
·
OSTI ID:5905481
- General Dynamics Corporation (US)
This book contains articles presented at the 1990 Pressure Vessels and Piping Conference. It is organized under the following headings: Section 1: New rules for design of tubesheet heat exchangers, Section 2: The process of code advancement, Section 3: Challenges to the nuclear codes, Section 4: Panel in pressure vessel research council (PVRC) review of ASME nuclear codes and standards, Section 5: Classification of stresses and deformations for code design evaluations, Section 6: Advancement in codes and standards for piping, components and supports, Section 7: The role of codes and standards for plant life extension, Section 8: Codes and standards for nondestructive examination.
- OSTI ID:
- 5905481
- Report Number(s):
- CONF-900617--; ISBN: 0-7918-0497-6
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210700 -- Nuclear Power Plants-- Regulation & Licensing
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200 -- Nuclear Reactor Technology-- Components & Accessories
220900* -- Nuclear Reactor Technology-- Reactor Safety
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
ABSTRACTS
COMPUTER CODES
CONTAINERS
DESIGN
DOCUMENT TYPES
FLANGES
HEAT EXCHANGERS
LEADING ABSTRACT
MAINTENANCE
MATERIALS TESTING
MEETINGS
NONDESTRUCTIVE TESTING
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PIPES
POWER PLANTS
PRESSURE VESSELS
REACTOR COMPONENTS
REACTOR SAFETY EXPERIMENTS
SAFETY STANDARDS
SHEETS
STANDARDS
STRESS ANALYSIS
TESTING
THERMAL POWER PLANTS
210700 -- Nuclear Power Plants-- Regulation & Licensing
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200 -- Nuclear Reactor Technology-- Components & Accessories
220900* -- Nuclear Reactor Technology-- Reactor Safety
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
ABSTRACTS
COMPUTER CODES
CONTAINERS
DESIGN
DOCUMENT TYPES
FLANGES
HEAT EXCHANGERS
LEADING ABSTRACT
MAINTENANCE
MATERIALS TESTING
MEETINGS
NONDESTRUCTIVE TESTING
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PIPES
POWER PLANTS
PRESSURE VESSELS
REACTOR COMPONENTS
REACTOR SAFETY EXPERIMENTS
SAFETY STANDARDS
SHEETS
STANDARDS
STRESS ANALYSIS
TESTING
THERMAL POWER PLANTS