Finite element analysis of prestressed concrete reactor vessels. [NONSAP code]
Abstract
Several present and proposed gas-cooled reactors use concrete pressure vessels. In addition, concrete is almost universally used for the secondary containment structures of water-cooled reactors. Regulatory agencies must have means of assuring that these concrete structures perform their containment functions during normal operation and after extreme conditions of transient overpressure and high temperature. The NONSAP nonlinear structural analysis program has been extensively modified to provide one analytical means of assessing the safety of reinforced concrete pressure vessels and containments. Several structural analysis codes were studied to evaluate their ability to model the nonlinear static and dynamic behavior of three-dimensional structures. The NONSAP code was selected because of its availability and because of the ease with which it can be modified. In particular, the modular structure of this code allows ready addition of specialized material models. Major modifications have been the development of pre- and post-processors for mesh generation and graphics, the addition of an out-of-core solver, and the addition of constitutive models for reinforced concrete subject to either long-term or short-term loads. Emphasis was placed on development of a three-dimensional analysis capability.
- Authors:
- Publication Date:
- Research Org.:
- Los Alamos Scientific Lab., NM (USA)
- OSTI Identifier:
- 7096072
- Report Number(s):
- LA-UR-77-530; CONF-770807-9
TRN: 77-017306
- DOE Contract Number:
- W-7405-ENG-36
- Resource Type:
- Conference
- Resource Relation:
- Conference: 4. international conference on structural mechanics in reactor technology, San Francisco, CA, USA, 15 Aug 1977
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; HTGR TYPE REACTORS; PRESSURE VESSELS; STRESS ANALYSIS; COMPUTER CALCULATIONS; FINITE ELEMENT METHOD; N CODES; PRESTRESSED CONCRETE; BUILDING MATERIALS; COMPUTER CODES; CONCRETES; CONTAINERS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; MATERIALS; NUMERICAL SOLUTION; REACTORS; 210300* - Power Reactors, Nonbreeding, Graphite Moderated
Citation Formats
Smith, P D, Cook, W A, and Anderson, C A. Finite element analysis of prestressed concrete reactor vessels. [NONSAP code]. United States: N. p., 1977.
Web.
Smith, P D, Cook, W A, & Anderson, C A. Finite element analysis of prestressed concrete reactor vessels. [NONSAP code]. United States.
Smith, P D, Cook, W A, and Anderson, C A. 1977.
"Finite element analysis of prestressed concrete reactor vessels. [NONSAP code]". United States.
@article{osti_7096072,
title = {Finite element analysis of prestressed concrete reactor vessels. [NONSAP code]},
author = {Smith, P D and Cook, W A and Anderson, C A},
abstractNote = {Several present and proposed gas-cooled reactors use concrete pressure vessels. In addition, concrete is almost universally used for the secondary containment structures of water-cooled reactors. Regulatory agencies must have means of assuring that these concrete structures perform their containment functions during normal operation and after extreme conditions of transient overpressure and high temperature. The NONSAP nonlinear structural analysis program has been extensively modified to provide one analytical means of assessing the safety of reinforced concrete pressure vessels and containments. Several structural analysis codes were studied to evaluate their ability to model the nonlinear static and dynamic behavior of three-dimensional structures. The NONSAP code was selected because of its availability and because of the ease with which it can be modified. In particular, the modular structure of this code allows ready addition of specialized material models. Major modifications have been the development of pre- and post-processors for mesh generation and graphics, the addition of an out-of-core solver, and the addition of constitutive models for reinforced concrete subject to either long-term or short-term loads. Emphasis was placed on development of a three-dimensional analysis capability.},
doi = {},
url = {https://www.osti.gov/biblio/7096072},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Sat Jan 01 00:00:00 EST 1977},
month = {Sat Jan 01 00:00:00 EST 1977}
}