Published 1994
| Version v1
Book
Aspects of design and stress classification of a PWR support structure
- 1. COPES/IPEN-CNEN/SP, Sao Paulo (Brazil). Structural Mechanics Div.
Description
This paper presents the stress analysis of a support structure of a nuclear PWR vessel. Different geometries and thermal boundary conditions are considered to achieve a viable design of the support structure. FE analyses are performed with the ANSYS program. For the stress verification, the ASME Section 3 requirements are applied. This article also presents: (1) a discussion on the stress classification and linearization, and (2) the jurisdictional boundary between the ASME Subsection NB (Class 1 Components) and Subsection NF (Components Supports)
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-1350-9
- Imprint Title
- Recertification and stress classification issues. PVP-Vol. 277
- Imprint Pagination
- 175 p.
- Journal Page Range
- p. 103-108.
Conference
- Title
- 1994 pressure vessels and piping conference.
- Dates
- 19-23 Jun 1994.
- Place
- Minneapolis, MN (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 26030473
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- A CODES; DESIGN; FINITE ELEMENT METHOD; PRESSURE VESSELS; PWR TYPE REACTORS; STANDARDS; STRESS ANALYSIS; STRESS INTENSITY FACTORS; SUPPORTS; THEORETICAL DATA
- Descriptors DEC
- CALCULATION METHODS; COMPUTER CODES; CONTAINERS; DATA; ENRICHED URANIUM REACTORS; INFORMATION; MECHANICAL STRUCTURES; NUMERICAL DATA; NUMERICAL SOLUTION; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-940613--.