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 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 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 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 165 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 Effects of Radiation on Materials written by Margaret L. Hamilton and published by ASTM International. This book was released on 2000 with total page 1266 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book ASTM Special Technical Publication written by and published by . This book was released on 1961 with total page 516 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Small Specimen Test Techniques written by and published by . This book was released on 2002 with total page 530 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Acta Polytechnica Scandinavica written by and published by . This book was released on 1998 with total page 124 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Effects of Radiation on Materials written by and published by . This book was released on 2000 with total page 1296 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Guidelines for Prediction of Irradiation Embrittlement of Operating WWER 440 Reactor Pressure Vessels written by International Atomic Energy Agency and published by IAEA. This book was released on 2005 with total page 82 pages. Available in PDF, EPUB and Kindle. Book excerpt: The IAEA International Database on RPV Materials (IDRPVM) is used for prediction and analysis of radiation embrittlement of WWER-440 reactor pressure vessel (RPV) materials. These guidelines will be used for assessment of irradiation embrittlement of RPV ferritic materials as a result of degradation during operation.
Download or read book Metals Abstracts written by and published by . This book was released on 1993 with total page 606 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Exploratory Test of 288 C Radiation Resistance of Two USSR Produced Reactor Pressure Vessel Steels written by MA. Sokolov and published by . This book was released on 2000 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt: The effects of 288°C (550°F) irradiation to 1.0 x 1019 n/cm2, E > 1 MeV, on the Charpy V-notch ductilities of two USSR-produced forging materials were determined experimentally. The materials were provided by the Kurchatov Institute under the umbrella of a joint USA-USSR agreement and represent the Cr-Mo-V forgings employed in the construction of USSR light-water VVER-440 reactor pressure vessels (RPVs) before and after 1980, respectively. The primary difference between the two materials is phosphorus content (0.019% vs. 0.007% P) consistent with their respective USSR Steel Specifications 15Kh2MFA and 15Kh2MFA-A. Specimens for post-irradiation property determinations were irradiated in the Ford Nuclear Reactor in a controlled-temperature assembly at an average fluence rate of 5.6 x 1012 n/cm2-s, E > 1 MeV. The post-irradiation Charpy V-notch 41 J (30 ft-lb) transition temperature elevation for the material representing pre-1980 RPVs was 31°C (55°F). This elevation was accompanied by a 27% reduction in Charpy V-notch upper-shelf energy level. for the material representing the post-1980 RPVs, the transition temperature elevation was
Download or read book Correlation Between Subsize and Full size Charpy Impact Properties of Neutron Irradiated Reactor Pressure Vessel Steels written by N. Soneda and published by . This book was released on 2002 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt: The correlation between subsize and full-size Charpy impact properties of reactor pressure vessel steels have been investigated using 1/3 and 1/4 subsize specimens cut from the broken halves of full-size specimens irradiated to 2.7 x 1023 n m-2 (E>lMeV) at 288 °C. We found that ductile-to-brittle transition temperature (DBTT) and upper shelf energy (USE) of subsize specimens have good correlation with those of full- size specimens irrespective of steel types and irradiation conditions, and the shift in the DBTT due to irradiation embrittlement is independent of specimen size. In addition, 1/4 size Charpy data have more scatter than 1/3 size data. Based on the results, we propose a new method to correlate the absorbed energy curve obtained by the subsize test with that by the full-size test. This correlation method is capable to predict adjusted reference temperatures and USEs used in surveillance test programs.
Download or read book Irradiation and Annealing Behavior of 15Kh2MFA Reactor Pressure Vessel Steel written by U. Bergmann and published by . This book was released on 1993 with total page 25 pages. Available in PDF, EPUB and Kindle. Book excerpt: This work deals with the mechanical properties of reactor pressure vessel (RPV) steels used in the pressurized water reactors (PWR) of former Soviet type WWER-440. The materials under investigation were a forging (base metal 15Kh2MFA) and the corresponding weld. Charpy V-notch specimens and tensile test specimens were irradiated in the PWR WWER-2 Rheinsberg at about 270°C up to the two neutron fluence levels of 4 x 1018 and 5 x 1019 n/cm2 (E > 1 MeV). Post irradiation annealing heat treatments were performed, among others a 475°C/152 h treatment of technical interest.
Download or read book Integrity of Reactor Pressure Vessels in Nuclear Power Plants written by and published by . This book was released on 2009 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication is intended to assist nuclear utilities in optimizing the service life of nuclear power plants. It reviews the latest research on the effects of neutron irradiation on the steels and welds of reactor pressure vessels within light water cooled and moderated reactors.
Download or read book Long Term Irradiation Effects on the Mechanical Properties of Reactor Pressure Vessel Steels from Two Commercial PWR Plants written by Jenny Rouden and published by . This book was released on 2013 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Swedish nuclear power plants all have plant specific surveillance programs which includes samples from all relevant materials that are subjected to a fluence-level that exceeds 1*1017 n/cm2 over the estimated period of operation for the specific power plants. The Swedish pressurized water reactor (PWR)-plants are currently planning for a service period beyond 50 years of operation. As a portion of that, two of the three PWR units at the Ringhals site are conducting a major effort to verify the fitness to service of the reactor pressure vessel (RPV). In this case it is the weld in the belt-line region of the RPV, which is the apparent limiting factor. The weld metal contains high Nickel and high Manganese levels, not commonly used in other PWR-reactors. The effort includes a densified testing of the available surveillance capsule material in order to better understand the degradation phenomena and also an extended testing scope. A spin off effect of this program is that high fluence data for the base material also is made available from the testing. The chemical composition of the base metal is valid for many of the currently operating PWR-vessels. This study is an analysis of both the weld and the base material data extracted from the surveillance program. The results are evaluated against currently available data and correlation curves. In general, the results point out that the current Regulatory Guide 1.99 revision 2-correlation regarding the prediction of as-irradiated transition temperature is under-conservative for the tested material. The transition temperature shift, here evaluated as the temperature shift at 41J, is under-predicted by the correlation by as much as 70°C in some cases and increases with increasing fluences. However, prediction made by the French average irradiation embrittlement prediction formula, FIM-formula, is consistently better but still slightly under conservative.
Download or read book Final Results from the Crack Initiation and Arrest of Irradiated Steel Materials Project on Fracture Mechanical Assessments of Pre Irradiated RPV Steels Used in German PWR written by H. Hein and published by . This book was released on 2009 with total page 24 pages. Available in PDF, EPUB and Kindle. Book excerpt: Pre-irradiated original reactor pressure vessel (RPV) materials covering all four German pressurized water reactors (PWR) construction lines were tested in the Crack Initiation and Arrest of Irradiated Steel Materials program to create a database of fracture toughness and arrest values for neutron fluences beyond the end of life range. The new database comprises data from both unirradiated and irradiated RPV base and weld materials generated by tensile, Charpy-V impact, fracture toughness KJc, and crack arrest KIa tests. The test matrix consists of materials with optimized chemical composition and with high Copper or high Nickel content, respectively. Based on the generated and already existing data the RTNDT and the RTT0 (Master Curve) concepts are applied with specific view on reference temperatures, transition temperature shifts, and on possible correlations between the criteria used in both concepts. In this context the consequences of some influencing factors like type and chemical composition of the RPV steel, its manufacturing conditions, and the specimen type and size on the reference temperatures are discussed. Moreover, the test results are assessed with respect to the American Society of Mechanical Engineers (ASME) code and German Nuclear Safety Standards Commission safety standards. The crack arrest characteristics for these typical RPV materials are also determined in a twofold way by testing Compact Crack Arrest specimens and by evaluation of instrumented Charpy-V impact test data. The available results made a good point that crack arrest is a reliable phenomenon that doubtless exists. It is also shown that the obtained KIa data can be enveloped by applying the ASME KIc lower bound curve indexed by different reference temperatures. Finally, the results show that the used RPV materials are well designed in terms of material behavior under irradiated conditions and that optimized manufacture specifications are of great benefit particularly after long operation times.
