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Application Of Subsize Specimens For Re Irradiation Embrittlement Monitoring Of The First Generation Of Vver 440 Rpv Steels
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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.
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 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 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 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 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 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 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.
Book Synopsis Investigation of Material Behavior Under Reirradiation After Annealing Using Subsize Specimens by : AM. Kryukov
Download or read book Investigation of Material Behavior Under Reirradiation After Annealing Using Subsize Specimens written by AM. Kryukov and published by . This book was released on 1993 with total page 7 pages. Available in PDF, EPUB and Kindle. Book excerpt: Experimental results are presented from a study of changes in the ductile-to-brittle transition temperature of VVER-440 base and weld metals under cyclic irradiation and recovery. The transition temperatures were determined from the results of subsize V-notch impact specimens measuring 5 by 5 by 27.5 mm. Specimen irradiation was carried out in a commercial reactor at a temperature of 270°C in three irradiation and recovery cycles. Annealing of specimens was performed at 340, 420, and 460°C. The shift in the transition temperature of subsize specimen data in the first irradiation cycle was compared to the transition temperature shift determined from tests using standard Charpy specimens.
Book Synopsis On the Mechanism of Irradiation Embrittlement Enhancement in Reactor Pressure Vessel Steels at High Neutron Fluences by : IA. Stepanov
Download or read book On the Mechanism of Irradiation Embrittlement Enhancement in Reactor Pressure Vessel Steels at High Neutron Fluences written by IA. Stepanov and published by . This book was released on 2004 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt: The DBTT shift in irradiated VVER pressure vessel steels is represented by standard guidelines with a power law dependence on fast neutron fluence multiplied by a material constant. However, from recent data on surveillance specimens for several units of VVER-440, an irradiation embrittlement enhancement has been observed at neutron fluences above (2-3)x1020 n/cm2 (E>0.5 MeV) with a significant deviation from the standard guideline. This suggests an additional mechanism of irradiation embrittlement at high fluences.
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 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 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 Investigation of the Development of Irradiation - Induced Precipitates in VVER-440-Type Reactor Pressure Vessel Steels and Weld Metals After Irradiation and Annealing by : J. Böhmert
Download or read book Investigation of the Development of Irradiation - Induced Precipitates in VVER-440-Type Reactor Pressure Vessel Steels and Weld Metals After Irradiation and Annealing written by J. Böhmert and published by . This book was released on 1999 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt: The development of irradiation-induced precipitates in VVER-440 type reactor pressure vessel steels 15Kh2MFA and weld metals SV-10KhMFT during irradiation and post-irradiation annealing is studied by small angle neutron and X-ray scattering. The kinetic conditions for the precipitation of particles, which already exist in the unirradiated state, seem to be improved at temperatures of about 270°C due to the irradiation. The size distribution of the irradiation-induced precipitates depends on the copper content and differs between weld and base metal. A strong correlation between the formation of irradiation-induced precipitates and the irradiation hardening is found. The hardness nearly linearly depends on the number of these precipitates.
Book Synopsis The Effects of Flux on Radiation Embrittlement of Low-Copper Pressure Vessel Steels by : C. Zhang
Download or read book The Effects of Flux on Radiation Embrittlement of Low-Copper Pressure Vessel Steels written by C. Zhang and published by . This book was released on 2000 with total page 9 pages. Available in PDF, EPUB and Kindle. Book excerpt: The effects of neutron flux (E>1MeV) on the radiation embrittlement of the low-copper RPV steels are investigated. Tested materials include the forging matrix (JF) weld (JW) of Japan's SA 508-3 steel as well as the matrix (CF) and weld (CW) of China's domestic RPV steel. JF and CF were irradiated to fluences from 3.2 to 4.9 x 1023n/m2(E>1MeV) at 280±5°C, JW and CW irradiated to fluences of 1.4 and 1.5 x 1023n/m2 at 290±5°C, respectively, in the test reactor. JF and JW are also used as surveillance specimens for PWR RPV, and two sets of surveillance data have been acquired. The experimental results indicate that the transition temperature shifts (?RTNDT) for JF irradiated in the test reactor are larger than those from surveillance specimens, when these ?RTNDT are normalized to an effective fluence of 2x1023n/m2 (E>1MeV) and an effective temperature of 290°C. This shows notably the influence of neutron flux on ?RTNDT. The mean ?RTNDT for CF and CW is about 0.7 times that for JF and JW in terms of the normalized data, which imply the influences of the impurities besides Cu and microstructures on radiation embrittlement of low-copper RPV steels.
Book Synopsis The Swiss Research Program on Irradiation Embrittlement and Annealing of Reactor Pressure Vessel Steels by : DH. Njo
Download or read book The Swiss Research Program on Irradiation Embrittlement and Annealing of Reactor Pressure Vessel Steels written by DH. Njo and published by . This book was released on 1989 with total page 22 pages. Available in PDF, EPUB and Kindle. Book excerpt: The present research program on irradiation embrittlement and annealing of reactor pressure vessel (RPV) steels in Switzerland is carried out at the Paul Scherrer Institute for Reactor Research. The particular program structure and its relation to the concept for an improved surveillance program is described.
Book Synopsis On Impact Testing of Subsize Charpy V-notch Type Specimens by :
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.
