Published 1995 | Version v1
Book

Load-carrying capacity of nuclear reactors under internal pressure considering work-hardening effect

  • 1. Korea Advanced Inst. of Science and Technology, Taejon (Korea, Republic of). Dept. of Mechanical Engineering
  • 2. Korea Atomic Energy Research Inst., Taejon (Korea, Republic of). Nuclear Safety Research Div.

Description

A nuclear reactor is simplified and regarded as a pressure vessel to obtain its load-carrying capacity. Load-carrying capacity of a nuclear reactor is calculated by a finite element limit analysis considering work-hardening effect. The work-hardening effect generally enhances the safety margin of a pressure vessel from the incipient yielding to the rupture. In the calculation, the wall thickness of a nuclear reactor is altered as a design parameter to identify the validity of the current design. The current design proves to be a good design in the sense of a pressure vessel from the numerical result. The numerical result provides load-carrying capacity and collapse modes of a nuclear reactor with the variation of the wall thicknesses and demonstrates the capability of the present method for the optimum design of a pressure vessel

Additional details

Publishing Information

Publisher
American Society of Mechanical Engineers.
Imprint Place
New York, NY (United States)
ISBN
0-7918-1328-2
Imprint Title
High pressure technology 1995. PVP-Volume 297
Imprint Pagination
197 p.
Journal Page Range
p. 9-14.

Conference

Title
Joint ASME/JSME pressure vessels and piping conference.
Dates
23-27 Jul 1995.
Place
Honolulu, HI (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
27026111
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
DEFORMATION; DESIGN; NUCLEAR POWER PLANTS; NUMERICAL ANALYSIS; PLASTICITY; PRESSURE DEPENDENCE; PRESSURE VESSELS; SYSTEMS ANALYSIS; THEORETICAL DATA
Descriptors DEC
CONTAINERS; DATA; INFORMATION; MATHEMATICS; MECHANICAL PROPERTIES; NUCLEAR FACILITIES; NUMERICAL DATA; POWER PLANTS; THERMAL POWER PLANTS

Optional Information

Secondary number(s)
CONF-950740--.