Estimation of fracture toughness of Zr 2.5% Nb pressure tube of Pressurised Heavy Water Reactor using cyclic ball indentation technique
Description
Highlights: • Measurement of fracture toughness of pressure tube is required for its fitness assessment. • Pressure tube removal from the core consumes large amount of radiation for laboratory test. • A remotely operable In situ Property Measurement System (IProMS) has been designed in house. • Conventional and IProMS tests conducted on pressure tube spool pieces having different mechanical properties. • Correlation has been established between the conventional and IProMS estimated fracture properties. - Abstract: In Pressurised Heavy Water Reactors (PHWRs) fuel bundles are located inside horizontal pressure tubes made up of Zr 2.5 wt% Nb alloy. Pressure tubes undergo degradation during its service life due to high pressure, high temperature and radiation environment. Measurement of mechanical properties of degraded pressure tubes is important for assessing their fitness for further operation. Presently as per safety guidelines imposed by the regulatory body, a few pre-decided pressure tubes are removed from the reactor core at regular intervals during the planned reactor shut down to carry out post irradiation examination (PIE) in a laboratory which consumes lots of man-rem and imposes economic penalties. Hence a system is indeed felt necessary which can carry out experimental trials for measurement of mechanical properties of pressure tubes under in situ conditions. The only way to accomplish this important objective is to develop a system based on an in situ measurement technique. In the field of in situ estimation of properties of materials, cyclic ball indentation is an emerging technique. Presently, commercial systems are available for doing an indentation test either on the outside surface of a component at site or on a test piece in a laboratory. However, these systems cannot be used inside a pressure tube for carrying out ball indentation trials under in situ conditions. Considering the importance of such measurements, an In situ Property Measurement System (IProMS) based on cyclic ball indentation technique has been designed and developed indigenously. The remotely operable system is capable to carry out indentation trials on the inside surface of the pressure tube and estimates the important mechanical properties like yield strength, ultimate tensile strength, hardness etc. It is known that fracture toughness is one of the important life limiting parameters of the pressure tube. Effort has also been made to estimate the fracture toughness of the pressure tube using the data from ball indentation trials. Curved compact tension (CCT) specimens have been prepared from Zr 2.5 wt% Nb pressure tube spool pieces having different mechanical properties. Fracture toughness of these specimens was measured by conventional test techniques which were later used as reference data for bench marking. This paper highlights the comparison between tensile properties measured from conventional tests and IProMS trials and relates the fracture toughness parameters measured from conventional tests with the IProMS estimated fracture properties. A methodology has been developed to relate the IProMS estimated properties like strength coefficient, indentation energy to fracture etc. with the fracture properties estimated through conventional tests.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2016.04.034Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2016.04.034;
- PII
- S0029-5493(16)30062-0;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 305
- Journal Page Range
- p. 9-17
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 48060415
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Descriptors DEI
- FRACTURE PROPERTIES; FUEL ELEMENT CLUSTERS; HARDNESS; NIOBIUM ALLOYS; PHWR TYPE REACTORS; POST-IRRADIATION EXAMINATION; PRESSURE RANGE MEGA PA 10-100; PRESSURE TUBES; RADIATION DOSE UNITS; REACTOR CORES; SAFETY STANDARDS; SERVICE LIFE; TEMPERATURE RANGE 0400-1000 K; TENSILE PROPERTIES; ULTIMATE STRENGTH; YIELD STRENGTH; ZIRCONIUM ALLOYS
- Descriptors DEC
- ALLOYS; FUEL ASSEMBLIES; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; LIFETIME; MECHANICAL PROPERTIES; PRESSURE RANGE; PRESSURE RANGE MEGA PA; REACTOR COMPONENTS; REACTORS; STANDARDS; TEMPERATURE RANGE; TRANSITION ELEMENT ALLOYS; TUBES; UNITS
Optional Information
- Copyright
- Copyright (c) 2016 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.