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Using Subsize Impact Bend Specimens For Estimation Of Irradiation And Re Irradiation Embrittlement Of Vver Rpv Steels
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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.
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:
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 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 Monitoring of Radiation Embrittlement of the First and Second Generation of VVER RPV Steels by : Ya. I. Shtrombakh
Download or read book Monitoring of Radiation Embrittlement of the First and Second Generation of VVER RPV Steels written by Ya. I. Shtrombakh and published by . This book was released on 2007 with total page 18 pages. Available in PDF, EPUB and Kindle. Book excerpt: The analysis of the current condition on the prediction of radiation embrittlement for VVER RPV materials of the first and second generation has been carried out. The radiation lifetime of a definite type of pressure vessel is determined by various parameters caused by operational features and the chemical composition of pressure vessel's metal. The emphasis on re-irradiation embrittlement kinetics is given for the first generation of VVER RPV steels (VVER-440/179 and VVER-440/230 grades). The technique for the first generation RPV materials monitoring, based on sampling and studies of metal from the pressure vessel's inner surface, is considered. The current program of cutting out templates, for the inner surface of a RPV wall, and their re-irradiation in surveillance channels of VVER-440 units with full core and dummy assembles is described. The new approaches to re-irradiation embrittlement models are analyzed. The basic problems of VVER-440/213 and VVER-1000 metal monitoring are analyzed. The representativity of VVER-440/213 and VVER-1000 RPV surveillance programs is discussed. The necessity of updating of the current standard reference dependences for the prediction of radiation embrittlement of RPV materials is shown. The most urgent questions of reactor dosimetry for VVER pressure vessel materials have been covered. The lifetime extension problem for the first and second generation of VVER units is considered.
Book Synopsis Irradiation, Annealing, and Reirradiation Effects on American and Russian Reactor Pressure Vessel Steels by : MA. Sokolov
Download or read book Irradiation, Annealing, and Reirradiation Effects on American and Russian Reactor Pressure Vessel Steels written by MA. Sokolov and published by . This book was released on 2000 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt: One of the options to mitigate the effects of irradiation on reactor pressure vessels (RPVs) is to thermally anneal them to restore the toughness properties that have been degraded by neutron irradiation. Even though a postirradiation anneal may be deemed successful, a critical aspect of continued RPV operation is the rate of embrittlement upon reirradiation. There are insufficient data available to allow for verification of available models of reirradiation embrittlement or for the development of a reliable predictive methodology. This is especially true in the case of fracture toughness data. Under the U.S.-Russia Joint Coordinating Committee for Civilian Nuclear Reactor Safety (JCCCNRS), Working Group 3 on Radiation Embrittlement, Structural Integrity, and Life Extension of Reactor Vessels and Supports agreed to conduct a comparative study of annealing and reirradiation effects on RPV steels. The Working Group agreed that each side would irradiate, anneal, reirradiate (if feasible), and test two materials of the other. Charpy V-notch (CVN) and tensile specimens were included. Oak Ridge National Laboratory (ORNL) conducted such a program (irradiation and annealing, including static fracture toughness) with two weld metals representative of VVER-440 and VVER-1000 RPVs, while the Russian Research Center-Kurchatov Institute (RRC-KI) conducted a program (irradiation, annealing, reirradiation, and reannealing) with Heavy-Section Steel Technology (HSST) Program Plate 02 and Heavy-Section Steel Irradiation (HSSI) Program Weld 73W. The results for each material from each laboratory are compared with those from the other laboratory. The ORNL experiments with the VVER welds included irradiation to about 1 x 1019 n/cm2 (>1 MeV), while the RRC-KI experiments with the U.S. materials included irradiations from about 2 to 18 x 1019 n/cm2 (>1 MeV). In both cases, irradiations were conducted at ~290 °C and annealing treatments were conducted at ~454 °C. The ORNL and RRC-KI experiments have shown generally good agreement for both the Russian and U.S. steels. While recoveries of the Charpy 41-J transition temperatures were substantial in all cases, significantly less recovery of the lateral expansion and shear fracture in some cases (no recovery in one case) deserves further attention. The RRC-KI results for the U.S. steels showed reirradiation embrittlement rates which are conservative relative to the lateral shift prediction based on Charpy impact energy.
Book Synopsis Recueil factice de progr. et d'art. de presse sur diverses pièces de F. Ducrot by :
Download or read book Recueil factice de progr. et d'art. de presse sur diverses pièces de F. Ducrot written by and published by . This book was released on with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Correlation Between Subsize and Full-size Charpy Impact Properties of Neutron-Irradiated Reactor Pressure Vessel Steels by : N. Soneda
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.
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 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 Master Curve Evaluation of Irradiated Russian VVER Type Reactor Pressure Vessel Steels by : H-W Viehrig
Download or read book Master Curve Evaluation of Irradiated Russian VVER Type Reactor Pressure Vessel Steels written by H-W Viehrig and published by . This book was released on 2001 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt: Results of a joint German/Russian irradiation program performed on the prototype pressurized water reactor VVER-2 of the Rheinsberg nuclear power plant (Germany) are summarized. The experiment comprises Charpy V-notch (CVN), precracked Charpy size (SENB) and compact tension (CT) specimens made of different heats of Russian VVER type reactor pressure vessel (RPV) base and weld metals. Reference temperatures, T0, were evaluated according to the Master Curve (MC) concept using the multi temperature method. Neutron irradiation induced ductile-to-brittle transition temperature (DBTT) shifts determined on the basis of CVN and SENB tests are compared. On the base of the DBTT the neutron embrittlement sensitivity and the annealing behavior of tested RPV steels are evaluated. Different heats of the same VVER-RPV steel exhibit different neutron induced embrittlement and annealing behavior. The determined CVN transition temperatures correlates to the T0 temperatures evaluated by the MC concept.
Book Synopsis Irradiation and Post-Annealing Reirradiation Effects on Fracture Toughness of RPV Steel Heat JRQ by : P. Tipping
Download or read book Irradiation and Post-Annealing Reirradiation Effects on Fracture Toughness of RPV Steel Heat JRQ written by P. Tipping and published by . This book was released on 2004 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt: A plate of A533 grade B class 1 steel designated heat JRQ has been used for many research studies around the world, especially those sponsored by the International Atomic Energy Agency. In this study, groups of Charpy impact, tensile, and precracked Charpy specimens of the JRQ plate were irradiated by the Paul Scherrer Institute to four different fast neutron fluences [from 0.39 to 5.0 x 1023 n/m2 (>1 MeV)] in a test reactor. Additional specimens were given a post-irradiation thermal annealing treatment at 460°C for 18 h when 50% of the target fluence was reached, followed by reirradiation to the same target fluences for the four groups of irradiated specimens. Additionally, Oak Ridge National Laboratory has thermally annealed some of the reirradiated specimens, as well as some of those in the irradiated only condition. Charpy impact, tensile, fracture toughness, and hardness tests have been performed to evaluate material response in the various conditions and for comparison with the unirradiated material. Except at the highest fluence, the results show that the material given an intermediate annealing treatment exhibited irradiation-induced transition temperature shifts about the same as those that were only irradiated. However, the upper-shelf energies were generally higher and the yield strengths were generally lower for the reirradiated groups. At the highest fluence, the Charpy 41-J temperature shift was significantly lower for the reirradiated group relative to the irradiated group at the same total fluence. The intermediate thermal annealing resulted in less reirradiation embrittlement of fracture toughness than Charpy impact toughness, while annealing after reirradiation resulted in significant increases in Charpy upper-shelf energy above that in the unirradiated condition. Comparisons of Charpy impact and fracture toughness results are mixed relative to transition temperature shifts for irradiated and reirradiated conditions.
Book Synopsis Radiation Embrittlement of Cr-Ni-Mo and Cr-Mo RPV Steels by : Yu. A. Nikolaev
Download or read book Radiation Embrittlement of Cr-Ni-Mo and Cr-Mo RPV Steels written by Yu. A. Nikolaev and published by . This book was released on 2007 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt: Radiation embrittlement kinetics of Cr-Mo and Cr-Ni-Mo steels, used for manufacturing VVER-440 and VVER-1000 RPV steels, respectively, are under consideration. Radiation embrittlement of VVER-440 and VVER-1000 RPV steels exposed to irradiation for 17-22 years is analyzed. Extremely high levels of thermal aging of VVER-1000 RPV steels at 320°C is pointed out. The neutron flux effect problem and the problem of accelerated radiation embrittlement of welds with high nickel contents are emphasized. The effect of phosphorus, copper, silicon, manganese, and nickel contents on radiation embrittlement of VVER-440 and VVER-1000 RPV steels is studied using the Russian surveillance database and representative results of research programs. The trend curves for VVER-440 and VVER-1000 RPV steels are proposed. The mechanisms of radiation embrittlement of Cr-Ni-Mo and Cr-Mo RPV steels are supposed.
