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