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Application Of The Reconstituted Subsize Specimens For Assessment Of Irradiation Embrittlement Of Rpv Steels
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Book Synopsis Application of the Reconstituted Subsize Specimens for Assessment of Irradiation Embrittlement of RPV Steels by : YI. Shtrombakh
Download or read book Application of the Reconstituted Subsize Specimens for Assessment of Irradiation Embrittlement of RPV Steels written by YI. Shtrombakh and published by . This book was released on 2002 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt: The actual values of the weld metal characteristics required for determination of the RPV lifetime, that is the ductile-to-brittle transition temperature (DBTT) in the unirradiated condition (Tk0), the phosphorus and copper contents (that are known to affect the radiation stability of steel), were not measured during manufacturing of old VVER-440 reactors. The small samples (templets) were cut out of the inside surface of the old Russian VVER-440 reactor pressure vessels (RPV) to assess the actual condition of the RPV material before and after post-irradiation annealing and after re-irradiation. Calculations have shown that it is not admissible to cut out samples of the size appropriate for machining of fullsize Charpy specimens necessary to comply with Russian Guide for determination of RPV steel DBTT. An application of subsize specimens for estimation of irradiation embrittlement of RPV steel was substantiated. In order to substantiate application of reconstituted subsize specimens made from broken subsize specimens for assessment of irradiation embrittlement of RPV materials, the correlation dependencies between the DBTT values of reconstituted and standard subsize specimens were developed. With this aim reconstitution of broken 5x5x27.5 mm specimens was performed by the stud-welding method. Both unirradiated and irradiated to high fluence steels were used in this program. The influence of reconstitution on the correlation dependence of DBTT for standard fullsize and subsize impact specimens was studied. Irradiation and re-irradiation kinetics of RPV steels were studied using subsize specimens machined from templets of operating units.
Book Synopsis Application of Subsize Specimens for Irradiation Embrittlement Monitoring of VVER-440/213 RPV Steels by : A. V. Nikolaeva
Download or read book Application of Subsize Specimens for Irradiation Embrittlement Monitoring of VVER-440/213 RPV Steels written by A. V. Nikolaeva and published by . This book was released on 2008 with total page 23 pages. Available in PDF, EPUB and Kindle. Book excerpt: Results of VVER-440/213 reactor pressure vessel (RPV) surveillance specimens studies showed that all surveillance impact bend specimens were irradiation with a lead factor more than 20 compared to irradiation of the pressure vessel inner surface. This is a special problem of radiation embrittlement assessment for VVER-440/213 RPV materials. Prediction of radiation embrittlement of RPV materials using surveillance specimens is efficient on the basis of accelerated irradiation compared to irradiation of the RPV inner surface. However, the lead factor, which is the ratio of neutron flux affecting surveillance specimens to neutron flux affecting the RPV inner surface in the maximum irradiated zone, should be not too high, when acceleration of steel irradiation would not cause qualitative changes in physical processes of irradiation damage. It is generally assumed that irradiation with a lead factor less than 3-6 provides adequate assessment of radiation embrittlement dependence on the damage dose. In the top part of the chains with VVER-440/213 surveillance specimens, fast neutron flux decreases ~20 times and the top capsules are irradiated with a neutron flux range close to the flux maximum on the inner surface of the reactor pressure vessel; i.e., the lead factor there is around 1. This concerns both reactors with full core and with dummies on the periphery of the core. The gradient of the neutron flux in the top and bottom parts of chains is great enough; hence, the volume of homogeneously irradiated metal is low. However, there is an opportunity to use material from the top capsules of irradiation sets for correct evaluation of the transition temperature using subsize specimens. As surveillance specimens in the top capsules are irradiated at the same conditions as the pressure vessel, their study allows precise determination of radiation embrittlement of RPV materials. The results of studies of irradiation embrittlement of VVER-440/213 RPV steels using subsize specimens are discussed.
Book Synopsis Application of Subsize Specimens for Re-Irradiation Embrittlement Monitoring of the First Generation of VVER-440 RPV Steels by : Ya. I. Shtrombakh
Download or read book Application of Subsize Specimens for Re-Irradiation Embrittlement Monitoring of the First Generation of VVER-440 RPV Steels written by Ya. I. Shtrombakh and published by . This book was released on 2008 with total page 9 pages. Available in PDF, EPUB and Kindle. Book excerpt: The first generation of VVER-440 Units were not supplied with RPV steel surveillance programs. Therefore, cutting out of samples (templetes) from the inner side of RPV wall is the only possibility for re-irradiation embrittlement monitoring of the first generation of VVER-440 RPV steels. Calculations showed that it is possible to cut out a sample of 7×60×95 mm (with consequent repair) from a RPV core weld. Thus, it is impossible to machine the standard 10×10×55 mm Charpy V-notch specimens to determine RPV steel radiation embrittlement. Therefore it is necessary to use subsize specimens (5×5×27.5 mm and 3×4×27 mm) for ductile-to-brittle transition temperature evaluation of templet material. The small samples were cut out from the inner surface of the all old Russian VVER-440 RPVs to assess the actual condition of the RPV material before and after post-irradiation annealing and after re-irradiation. Special monitoring programs of periodic sampling of RPVs and re-irradiation of the templet material in surveillance channels of VVER-440/213 RPVs were developed. The state of the art of application of subsize specimens for re-irradiation embrittlement monitoring of the first generation of VVER-440 RPV steels is discussed.
Author :ASTM International Committee E10 on Nuclear Technology and Applications Publisher :ASTM International ISBN 13 :0803128975 Total Pages :495 pages Book Rating :4.8/5 (31 download)
Book Synopsis Small Specimen Test Techniques by : ASTM International Committee E10 on Nuclear Technology and Applications
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:
Book Synopsis ASTM Special Technical Publication by :
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:
Book Synopsis Using Subsize Impact Bend Specimens for Estimation of Irradiation and Re-Irradiation Embrittlement of VVER RPV Steels by : A. V. Nikolaeva
Download or read book Using Subsize Impact Bend Specimens for Estimation of Irradiation and Re-Irradiation Embrittlement of VVER RPV Steels written by A. V. Nikolaeva and published by . This book was released on 2008 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt: Results of impact bend tests of subsize Charpy V-notch-type (CVN) specimens are used in Russia for monitoring both re-irradiation embrittlement of the first generation of VVER-440 (including VVER-440/179 and VVER-440/230, i.e., projects B-179 and B-230) reactor pressure vessel (RPV) steels and irradiation embrittlement of VVER-440/213 RPV steels. For the first generation of VVER-440 RPVs, no surveillance program was foreseen and only subsize specimens (5 by 5 by 27.5 mm and 3 by 4 by 27 mm) can be manufactured from samples taken from the inner surface of the RPV for radiation embrittlement monitoring. For VVER-440/213 RPVs, 80 % of the surveillance specimens are irradiated with a lead factor greater than 20. Only four specimens of base metal and four specimen halves of weld seam material are irradiated with a lead factor less than 3. Taking into account that full-size (10 by 10 by 55 mm) CVN specimens were used in surveillance programs, using subsize specimens enables to solve the flux effect problem for VVER-440/213 RPV beltline materials and ensure representativity of surveillance programs. Application of subsize specimens for the estimation of radiation embrittlement requires developing a correlation between transition temperature values evaluated using test results of standard (full-size) and subsize CVN specimens. Such a correlation is discussed.
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:
Book Synopsis Selection of the Optimum Irradiation Fluence to Assess Annealing During Reconstitution of Charpy Impact Specimens by : E. Otsuka
Download or read book Selection of the Optimum Irradiation Fluence to Assess Annealing During Reconstitution of Charpy Impact Specimens written by E. Otsuka and published by . This book was released on 2002 with total page 9 pages. Available in PDF, EPUB and Kindle. Book excerpt: Surveillance specimens, for example Charpy specimens, are used to monitor the effect of irradiation embrittlement on Reactor Pressure Vessel (RPV) steels. Reconstitution technology is an advanced method that can be used to avoid possible shortages of surveillance specimens in case of long-term operation beyond design life. The validation of the reconstitution technology for surveillance specimens of RPV steels down to an insert length of 10 mm requires investigating the eventual annealing effect during reconstitution. The optimum irradiation conditions for reconstitution studies of irradiated specimens were investigated based on the basic data obtained on un-irradiated specimens. The irradiation fluence of 1 x 1019 n/cm2 was found most appropriate to assess the influence of annealing during reconstitution.
Book Synopsis Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels by : Lendell E. Steele
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 1993 with total page 405 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Effects of Radiation on Materials by :
Download or read book Effects of Radiation on Materials written by and published by . This book was released on 1996 with total page 1192 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis 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 by : YN. Korolev
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.
Book Synopsis Use of Subsize Specimens for Determination of Radiation Embrittlement of Operating Reactor Pressure Vessels by : AD. Amayev
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.
Book Synopsis Small Specimen Test Techniques by : W. R. Corwin
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
Book Synopsis Application of the Floating Curve Model for Estimation of Re-Irradiation Embrittlement of VVER-440 RPV Steels by : AV. Nikolaeva
Download or read book Application of the Floating Curve Model for Estimation of Re-Irradiation Embrittlement of VVER-440 RPV Steels written by AV. Nikolaeva and published by . This book was released on 2000 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt: Radiation embrittlement and its mitigation by annealing of VVER-440 reactor pressure vessel steels are studied. The Russian regulatory approach for prediction of radiation embrittlement of VVER-440 steels is considered. Results of an investigation of materials cut out of operating nuclear power plants are discussed. Different models of re-irradiation embrittlement are compared. A new model for assessment of embrittlement under re-irradiation is developed.
Book Synopsis Determination of Toughness and Embrittlement for Reactor Pressure Vessel Steels Using Ultrasonic Measurements by : A. L. Hiser
Download or read book Determination of Toughness and Embrittlement for Reactor Pressure Vessel Steels Using Ultrasonic Measurements written by A. L. Hiser and published by . This book was released on 2002 with total page 439 pages. Available in PDF, EPUB and Kindle. Book excerpt: Neutron irradiation embrittlement of nuclear reactor pressure vessel (RPV) steels results in a loss of fracture toughness (e.g., reduction in load carrying capacity of the steel). For the setting of operational limits and assuring the continued safe operation of the plant, current procedures estimate the effects of neutron embrittlement using empirical relations or the results of small samples irradiated in the plant. These procedures account for uncertainties in the estimates through the use of margin terms to ensure the conservatism of the resultant estimate vis-a-vis the "real" material toughness. Therefore, the ability to develop non destructive measurements that can estimate the actual RPV steel fracture toughness in situ would provide more accurate evaluations of operating limits for plants. This study was undertaken to evaluate the suitability of ultrasonic attenuation measurements for estimating the fracture toughness of RPV steels. Ultrasonic measurements were made on samples in three distinct phases: (1) a heat treated RPV steel to induce changes in its fracture toughness; (2) several irradiated RPV steels to assess actual neutron embrittlement changes in fracture toughness; and (3) a matrix of unirradiated RPV steels with a range of as fabricated toughness levels. The results indicate that ultrasonic attenuation is generally able to identify differences in responses for samples with different toughness levels, although in some cases the differences in ultrasonic responses are small. The results from the three phases are not consistent, as in some cases reduced toughness results in higher attenuation and in other cases lower attenuation. This trend is not surprising given the different types of microstructural changes that result in the toughness changes for each phase of this work. In addition, different trends were identified for plate and weld materials.
Book Synopsis Effects of Radiation on Materials by : Stan T. Rosinski
Download or read book Effects of Radiation on Materials written by Stan T. Rosinski and published by ASTM International. This book was released on 2001 with total page 879 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Effects of Radiation on Materials by : D. S. Gelles
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:
