BOOK-CHAPTER

Brittle Fracture and Irradiation Effects in Ferritic Pressure Vessel Steels

Abstract

The safe working of any gas-cooled reactor system is dependent on the virtually perfect containment of both fuel and coolant. In order to satisfy these containment requirements, much attention has been given to factors determining the safe working of welded thick-walled steel pressure vessels. In addition to the aspects common to other pressure circuits (stress, temperature, and variations of these) the reactor pressure vessel designer must also consider the effects of neutron bombardment. As a result of neutron irradiation, direct inspection of the reactor pressure vessel during service is not possible and maintenance cannot at present be contemplated. In view of this, and of the serious consequences of failure, somewhat more stringent precautions have to be taken than are common in conventional engineering practice.

Keywords:
Reactor pressure vessel Pressure vessel Materials science Coolant Nuclear engineering Embrittlement Welding Light-water reactor Brittle fracture High pressure Nuclear reactor Brittleness Fracture (geology) Forensic engineering Metallurgy Engineering Composite material Mechanical engineering Engineering physics

Metrics

30
Cited By
5.76
FWCI (Field Weighted Citation Impact)
7
Refs
0.95
Citation Normalized Percentile
Is in top 1%
Is in top 10%

Citation History

Topics

Nuclear Materials and Properties
Physical Sciences →  Materials Science →  Materials Chemistry
Fusion materials and technologies
Physical Sciences →  Materials Science →  Materials Chemistry
Fatigue and fracture mechanics
Physical Sciences →  Engineering →  Mechanics of Materials

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