A Procedure for the Assessment of the Structural Integrity of Nuclear Pressure VesselsSource: Journal of Pressure Vessel Technology:;1983:;volume( 105 ):;issue: 001::page 28Author:J. M. Bloom
DOI: 10.1115/1.3264235Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: This paper presents a simple engineering procedure that the utility industry can use to assess the integrity of typical nuclear-grade pressure vessels. The procedure recognizes both brittle fracture and plastic collapse and is based on a set of proposed failure assessment curves which make up a safety/failure plane. The plane is defined by the stress intensity factor/fracture toughness ratio as the ordinate and the applied stress/reference plastic collapse stress ratio as the abscissa. The failure assessment procedure is based in part on the British Central Electricity Generating Board’s R-6 failure assessment diagram and the deformation plasticity solutions of the General Electric Company. Two parameters, a plastic collapse parameter (Sr ′ ) and linear elastic fracture mechanics parameter (Kr ′ ) are calculated by the user. The point (Sr ′ , Kr ′ ) is plotted on the appropriate failure assessment diagram. If the point lies inside the respective curve, the structure is safe from failure. Moreover, for a given pressure and a postulated or actual flaw size, the margin of safety of the structure can be simply determined. Consistent with Appendix A of Section XI, (Division 1) of the ASME Boiler and Pressure Vessel Code the procedure presented in this paper is limited to ferritic materials 4 in. (102 mm) and greater in thickness. Details of the derivation of the proposed set of failure assessment curves are provided along with a sample problem illustrating the use of these curves.
keyword(s): Pressure , Plasticity , Deformation , Fracture mechanics , Safety , Pressure vessels , Stress , Engineering processes and practices , ASME Boiler and Pressure Vessel Code , Brittle fracture , Collapse , Failure , Fracture toughness , Thickness AND Reactor vessels ,
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contributor author | J. M. Bloom | |
date accessioned | 2017-05-08T23:16:21Z | |
date available | 2017-05-08T23:16:21Z | |
date copyright | February, 1983 | |
date issued | 1983 | |
identifier issn | 0094-9930 | |
identifier other | JPVTAS-28218#28_1.pdf | |
identifier uri | http://yetl.yabesh.ir/yetl/handle/yetl/97551 | |
description abstract | This paper presents a simple engineering procedure that the utility industry can use to assess the integrity of typical nuclear-grade pressure vessels. The procedure recognizes both brittle fracture and plastic collapse and is based on a set of proposed failure assessment curves which make up a safety/failure plane. The plane is defined by the stress intensity factor/fracture toughness ratio as the ordinate and the applied stress/reference plastic collapse stress ratio as the abscissa. The failure assessment procedure is based in part on the British Central Electricity Generating Board’s R-6 failure assessment diagram and the deformation plasticity solutions of the General Electric Company. Two parameters, a plastic collapse parameter (Sr ′ ) and linear elastic fracture mechanics parameter (Kr ′ ) are calculated by the user. The point (Sr ′ , Kr ′ ) is plotted on the appropriate failure assessment diagram. If the point lies inside the respective curve, the structure is safe from failure. Moreover, for a given pressure and a postulated or actual flaw size, the margin of safety of the structure can be simply determined. Consistent with Appendix A of Section XI, (Division 1) of the ASME Boiler and Pressure Vessel Code the procedure presented in this paper is limited to ferritic materials 4 in. (102 mm) and greater in thickness. Details of the derivation of the proposed set of failure assessment curves are provided along with a sample problem illustrating the use of these curves. | |
publisher | The American Society of Mechanical Engineers (ASME) | |
title | A Procedure for the Assessment of the Structural Integrity of Nuclear Pressure Vessels | |
type | Journal Paper | |
journal volume | 105 | |
journal issue | 1 | |
journal title | Journal of Pressure Vessel Technology | |
identifier doi | 10.1115/1.3264235 | |
journal fristpage | 28 | |
journal lastpage | 34 | |
identifier eissn | 1528-8978 | |
keywords | Pressure | |
keywords | Plasticity | |
keywords | Deformation | |
keywords | Fracture mechanics | |
keywords | Safety | |
keywords | Pressure vessels | |
keywords | Stress | |
keywords | Engineering processes and practices | |
keywords | ASME Boiler and Pressure Vessel Code | |
keywords | Brittle fracture | |
keywords | Collapse | |
keywords | Failure | |
keywords | Fracture toughness | |
keywords | Thickness AND Reactor vessels | |
tree | Journal of Pressure Vessel Technology:;1983:;volume( 105 ):;issue: 001 | |
contenttype | Fulltext |