Download or read book Subsize Specimen Testing of a Nuclear Reactor Pressure Vessel Material written by NS. Cannon and published by . This book was released on 1994 with total page 9 pages. Available in PDF, EPUB and Kindle. Book excerpt: A new methodology is proposed to correlate the upper shelf energy (USE) of full size and subsize Charpy specimens of a nuclear reactor pressure vessel plate material, A533B. The methodology appears to be more satisfactory than the methodologies proposed earlier. USE of a notched-only specimen is partitioned into macro-crack initiation and crack propagation energies. USE of a precracked specimen provides the crack propagation energy. AUSE, the difference between the USE of notched-only and precracked specimens, is an estimate of the crack initiation energy. AUSE was normalized by a factor involving the dimensions of the Charpy specimen and the plastic stress concentration factor at the notch root. The normalized values of AUSE were found to be invariant with specimen size.
Download or read book Small Specimen Test Techniques Applied to Nuclear Reactor Vessel Thermal Annealing and Plant Life Extension written by W. R. Corwin and published by ASTM International. This book was released on 1993 with total page 460 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Small Specimen Test Techniques written by W. R. Corwin and published by ASTM International. This book was released on 1998 with total page 630 pages. Available in PDF, EPUB and Kindle. Book excerpt: As part of an increasing interest in radiation embrittlement for aging nuclear reactors, scientists gathered in New Orleans in January 1997 to consider the interests and capabilities of the scientific-testing community and of the commercial light-water-cooled power-reactor industry in terms of improving methods to characterize component integrity. The resulting 37 papers concentrate on the use of unique small and miniature specimens; nondestructive, nonintrusive, and in- situ test techniques for measuring mechanical and fracture properties; the application of tests to irradiation-induced embrittlement; and actual examples of tests to determine material integrity and to evaluate potential component life extension. They consider experimental, analytical, and computational aspects. Annotation copyrighted by Book News, Inc., Portland, OR
Download or read book Effects of Radiation on Materials written by Arvind S. Kumar and published by ASTM International. This book was released on 1994 with total page 1319 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Status of USA Nuclear Reactor Pressure Vessel Surveillance for Radiation Effects written by Lendell E. Steele and published by ASTM International. This book was released on 1983 with total page 290 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Small Specimen Test Techniques written by ASTM International Committee E10 on Nuclear Technology and Applications and published by ASTM International. This book was released on 2002 with total page 495 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Application of Subsize Specimens in Nuclear Plant Life Extension written by NS. Cannon and published by . This book was released on 1993 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt: The U.S. Department of Energy is sponsoring a research effort through Sandia National Laboratories and the University of Missouri-Rolla to test a correlation for the upper shelf energy (USE) values obtained from the impact testing of subsize Charpy V-notch specimens to those obtained from the testing of full-size samples. The program involves the impact testing of unirradiated and irradiated full-, half-, and third-size Charpy V-notch specimens. A correlation between subsize and full-size testing results has been developed in an earlier effort and tested on HT-9 material utilized in fusion reactor applications. To verify the applicability of the correlation on LWR materials, unirradiated and irradiated full-, half-, and third-size Charpy V-notch specimens of a commercial pressure vessel steel (ASTM A533 Grade B) will be tested. The correlation methodology is based on the partitioning of the USE into crack initiation and crack propagation energies. To accomplish this partition, both precracked and notched-only specimens will be used. Whereas the USE of notched-only specimens is the sum of both crack initiation and crack propagation energies, the USE of precracked specimens reflects only the crack propagation component. The difference in the USE of the two types of specimens represents a measure of the crack initiation energy. Normalizing the values of the crack initiation energy to the fracture volume of the sample produces similar values for the full-, half-, and third-size specimens. In addition, the ratios of the USE and the crack propagation energy are also in agreement for full-, half-, and third-size specimens. These two observations will be used to predict the USE of full-size specimens based on subsize USE data. This paper will provide details of the program and present results obtained from the application of the developed correlation methodology to the impact testing of the unirradiated full-, half-, and third-size A533 Grade B Charpy V-notch specimens.
Download or read book Characterizing Material Properties by the Use of Full Size and Subsize Charpy Tests written by E. Van Walle and published by . This book was released on 2000 with total page 18 pages. Available in PDF, EPUB and Kindle. Book excerpt: A total of 565 instrumented impact tests (232 performed on full-size and 333 on subsize Charpy-V specimens) have been analyzed in order to derive meaningful assumptions on the correlations existing between test results obtained on specimens of different size. Nine materials (pressure vessel steels) have been considered, in both the as-received and irradiated state, for a total of 19 conditions examined. For the analysis of data, conventional as well as novel approaches have been investigated; the former ones, based on a review of the existing literature, include predictions of upper-shelf energy (USE) values by the use of normalization factors (NF), shifts of index temperatures related to energy/lateral expansion/shear fracture levels, and a combination of both approaches (scaling+shifting of energy curves). More original and recent proposals have also been verified, available in the literature but also proposed by SCK•CEN in the frame of enhanced surveillance of nuclear reactor pressure vessels. Conclusions are drawn regarding the applicability and reliability of these methodologies.
Download or read book Comparison of Compact Reconstituted and Subsize Charpy Specimens written by G. Hofmann and published by . This book was released on 1998 with total page 9 pages. Available in PDF, EPUB and Kindle. Book excerpt: During the operation time of nuclear power plants change of material properties of the reactor pressure vessel may occur due to ageing or irradiation effects. A common tool to investigate this change of material properties is the determination of the shift in transition temperature by means of the Charpy impact test. Suitable index temperatures are derived from the test data of tested specimens of surveillance programs or from test data of specimens cut out of templets of RPVs. Due to lack of material, subsize and/or reconstituted specimens will be often used. In this paper investigations on reconstituted specimens are discussed and compared to results of compact (original) and subsize impact specimens. From the experimental data base the conclusion can be drawn that valid index temperatures for safety analysis can be derived from the test data of reconstituted specimens with minimum insert lengths of 10mm. Also from the test data of subsize specimens valid index temperatures can be obtained, if corresponding correlation functions to the original conventional ISO Charpy test data are applied.
Download or read book Radiation Embrittlement and Surveillance of Nuclear Reactor Pressure Vessels An International Study written by L. E. Steele and published by ASTM International. This book was released on 1983 with total page 226 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Miniaturized Testing of Engineering Materials written by V. Karthik and published by CRC Press. This book was released on 2016-09-15 with total page 123 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book is a comprehensive overview of methods of characterizing the mechanical properties of engineering materials using specimen sizes in the micro-scale regime (0.3-5.0 mm). A range of issues associated with miniature specimen testing like correlation methodologies for data transferability between different specimen sizes, use of numerical simulation/analysis for data inversion, application to actual structures using scooped out samples or by in-situ testing, and more importantly developing a common code of practice are discussed and presented in a concise manner.
Download or read book Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels written by Lendell E. Steele and published by ASTM International. This book was released on 1986 with total page 303 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book The Actual Properties of WWER 440 Reactor Pressure Vessel Materials Obtained by Impact Tests of Subsize Specimens Fabricated Out of Samples Taken from the RPV written by YN. Korolev and published by . This book was released on 1998 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt: This paper presents the results of a study on degradation due to irradiation occurring in WWER-440 reactor pressure vessel (RPV) steel, using subsize Charpy specimens (5x5x27.5 mm3). An application of subsize specimens for estimation of irradiation embrittlement of RPV steel has been substantiated. Comparison between ductile-to-brittle transition temperatures (DBTT) for full-size and subsize Charpy specimens has been carried out. The relation between these two values has been clarified. The results of testing trepans and templates cut out from WWER-440 reactor pressure vessels are considered. The main results of the program TACIS-91/1.1. are discussed.
Download or read book On Impact Testing of Subsize Charpy V notch Type Specimens written by and published by . This book was released on 1994 with total page 29 pages. Available in PDF, EPUB and Kindle. Book excerpt: The potential for using subsize specimens to determine the actual properties of reactor pressure vessel steels is receiving increasing attention for improved vessel condition monitoring that could be beneficial for light-water reactor plant-life extension. This potential is made conditional upon, on the one hand, by the possibility of cutting samples of small volume from the internal surface of the pressure vessel for determination of actual properties of the operating pressure vessel. The plant-life extension will require supplemental surveillance data that cannot be provided by the existing surveillance programs. Testing of subsize specimens manufactured from broken halves of previously tested surveillance Charpy V-notch (CVN) specimens offers an attractive means of extending existing surveillance programs. Using subsize CVN type specimens requires the establishment of a specimen geometry that is adequate to obtain a ductile-to-brittle transition curve similar to that obtained from full-size specimens. This requires the development of a correlation of transition temperature and upper-shelf toughness between subsize and full-size specimens. The present study was conducted under the Heavy-Section Steel Irradiation Program. Different published approaches to the use of subsize specimens were analyzed and five different geometries of subsize specimens were selected for testing and evaluation. The specimens were made from several types of pressure vessel steels with a wide range of yield strengths, transition temperatures, and upper-shelf energies (USEs). Effects of specimen dimensions, including depth, angle, and radius of notch have been studied. The correlation of transition temperature determined from different types of subsize specimens and the full-size specimen is presented. A new procedure for transforming data from subsize specimens was developed and is presented.
Download or read book Use of Subsize Specimens for Determination of Radiation Embrittlement of Operating Reactor Pressure Vessels written by AD. Amayev and published by . This book was released on 1993 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt: This paper presents groundwork for determining the ductile-to-brittle transition temperature (DBTT) from subsize specimens (5 by 5 by 27.5 and 3 by 4 by 27.0 mm) and describes the correlation between the DBTT obtained from tests of standard Charpy specimens and subsize specimens. A method for taking samples from the inside surface of reactor pressure vessels and fabricating small specimens from them was developed in the USSR. This method is used to assess the effectiveness of pressure vessel recovery by annealing. Some results of the DBTT evaluation for the base and weld metal before and after recovery are given.
Download or read book Effects of Radiation on Materials written by D. S. Gelles and published by ASTM International. This book was released on 1996 with total page 1169 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book From Charpy to Present Impact Testing written by D. Francois and published by Elsevier. This book was released on 2002-06-18 with total page 497 pages. Available in PDF, EPUB and Kindle. Book excerpt: From Charpy to Present Impact Testing contains 52 peer-reviewed papers selected from those presented at the Charpy Centenary Conference held in Poitiers, France, 2-5 October 2001. The name of Charpy remains associated with impact testing on notched specimens. At a time when many steam engines exploded, engineers were preoccupied with studying the resistance of steels to impact loading. The Charpy test has provided invaluable indications on the impact properties of materials. It revealed the brittle ductile transition of ferritic steels. The Charpy test is able to provide more quantitative results by instrumenting the striker, which allows the evolution of the applied load during the impact to be determined. The Charpy test is of great importance to evaluate the embrittlement of steels by irradiation in nuclear reactors. Progress in computer programming has allowed for a computer model of the test to be developed; a difficult task in view of its dynamic, three dimensional, adiabatic nature. Together with precise observations of the processes of fracture, this opens the possibility of transferring quantitatively the results of Charpy tests to real components. This test has also been extended to materials other than steels, and is also frequently used to test polymeric materials. Thus the Charpy test is a tool of great importance and is still at the root of a number of investigations; this is the reason why it was felt that the centenary of the Charpy test had to be celebrated. The Société Française de Métallurgie et de Matériaux decided to organise an international conference which was put under the auspices of the European Society for the Integrity of Structures (ESIS). This Charpy Centenary Conference (CCC 2001) was held in Poitiers, at Futuroscope in October 2001. More than 150 participants from 17 countries took part in the discussions and about one hundred presentations were given. An exhibition of equipment showed, not only present day testing machines, but also one of the first Charpy pendulums, brought all the way from Imperial College in London. From Charpy to Present Impact Testing puts together a number of significant contributions. They are classified into 6 headings: •Keynote lectures,•Micromechanisms,•Polymers,•Testing procedures,•Applications,•Modelling.
