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Neutron Fluence Determination For Light Water Reactor Pressure Vessels
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Book Synopsis Neutron Fluence Determination for Light Water Reactor Pressure Vessels by : R. Gold
Download or read book Neutron Fluence Determination for Light Water Reactor Pressure Vessels written by R. Gold and published by . This book was released on 1994 with total page 10 pages. Available in PDF, EPUB and Kindle. Book excerpt: A general description of limitations that exist in pressure vessel neutron fluence determinations for commercial light water reactors is presented. Complexity factors that arise in light water reactor pressure vessel neutron fluence calculations are identified and used to analyze calculational limitations. Two broad categories of calculational limitations are introduced, namely benchmark field limitations and deep penetration limitations. Explicit examples of limitations that can arise in each of these two broad categories are presented. These limitations are used to show that the recent draft regulatory guide for the determination of pressure vessel neutron fluence, developed by the Nuclear Regulatory Commission, is based upon procedures and assumptions that are not valid. To eliminate the complexity and limitations of calculational methods, it is recommended that the determination of light water reactor pressure vessel neutron fluence be based upon experiment. Recommendations for improved methods of pressure vessel surveillance neutron dosimetry are advanced.
Book Synopsis Neutron Fluence at the Pressure Vessel of a Pressurized Water Reactor Determined with the MCNP Code by : Peter Gyula Laky
Download or read book Neutron Fluence at the Pressure Vessel of a Pressurized Water Reactor Determined with the MCNP Code written by Peter Gyula Laky and published by . This book was released on 1994 with total page 111 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Effects of Nickel on Irradiation Embrittlement of Light Water Reactor Pressure Vessel Steels by : International Atomic Energy Agency
Download or read book Effects of Nickel on Irradiation Embrittlement of Light Water Reactor Pressure Vessel Steels written by International Atomic Energy Agency and published by IAEA. This book was released on 2005 with total page 70 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication sets out the findings of a co-ordinated research project to determine the influence of the mechanism of the deterioration effect in radiation embrittlement of reactor pressure vessel steels with a high nickel content in nuclear power plants, including procurement of materials, determination of mechanical properties, irradiation and testing of specimens, and microstructural characterisation.
Author :American Nuclear Society. Standards Committee Working Group ANS-19.10 Publisher : ISBN 13 : Total Pages : pages Book Rating :4.:/5 (122 download)
Book Synopsis American National Standard by : American Nuclear Society. Standards Committee Working Group ANS-19.10
Download or read book American National Standard written by American Nuclear Society. Standards Committee Working Group ANS-19.10 and published by . This book was released on with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This standard provides a procedure for the evaluation of the best-estimate fast (E > 1.0 MeV) neutron fluence in the annular region between the core and the inside surface of the vessel, through the pressure vessel and the reactor cavity, between the top and bot-tom of the active fuel given the neutron source in the core. This evaluation employs both fast neutron flux computations and measurement data from in-vessel and cavity dosimetry, as appropriate. The standard applies to both U.S.-designed pressurized water reactors (PWRs) and boiling water reactors (BWRs).
Book Synopsis Neutron Fluence Determination for WER-440 Reactor Pressure Vessel Ageing Surveillance by : SY. Antonov
Download or read book Neutron Fluence Determination for WER-440 Reactor Pressure Vessel Ageing Surveillance written by SY. Antonov and published by . This book was released on 1994 with total page 7 pages. Available in PDF, EPUB and Kindle. Book excerpt: The neutron flux and fluence determination on Bulgarian WER-440/230 (Units No 1-4 of Kozloduy NPP) Reactor Pressure Vessels is discussed. In these reactors weld 4 of RPV undergoes the most severe irradiation embrittlement. The choice of the neutron transport calculational parameters is substantiated. The inconsistency of 3D neutron flux values obtained by the 3D code TORT and by the synthesis method of DOT 2D results in the point of most severe irradiation embrittlement is within 3% limits range. Radiochemical analysis of the templets sampled out from the Unit No 2 vessel after 16 cycles of exploitation, before and after the annealing, was carried out. The calculated and experimental values of the neutron fluence on the Unit 2 RPV are compared.
Book Synopsis American National Standard Methods for Determining Neutron Fluence in BWR and PWR Pressure Vessel and Reactor Internals by :
Download or read book American National Standard Methods for Determining Neutron Fluence in BWR and PWR Pressure Vessel and Reactor Internals written by and published by . This book was released on 2009 with total page 7 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Neutron Dosimetry for VVER Reactor Pressure Vessels in the Czech Republic by : B. Osmera
Download or read book Neutron Dosimetry for VVER Reactor Pressure Vessels in the Czech Republic written by B. Osmera and published by . This book was released on 2001 with total page 8 pages. Available in PDF, EPUB and Kindle. Book excerpt: The paper gives a description of the contemporary methods used for the fast neutron fluence determination applied to the reactors of the Dukovany VVER-440 nuclear power plant (NPP). Measurement methods include measurements in containers with supplementary surveillance program and in the reactor cavity. Retrospective dosimetry using scraps of reactor pressure vessel cladding material is being prepared. Information is also given about the analogous methods prepared for the reactors of the Temelin VVER-1000 NPP. The results at measured points (reactor cavity, surveillance) are recalculated to the reactor pressure vessel inner wall by using the conversion factors obtained in mock-up experiments carried out for both VVER- 440 and VVER-1000 at the LR-0 research reactor. The experimental works are completed with fluence calculations for which two methods have been developed. The DAVKA code is the LEPRICON system adaptation for the VVER reactors and the INCAL 3D code makes use of the influence functions of the given volume of the fuel element to the total fluence. Measurements can be completed by gamma scanning of surveillance specimens rest activities.
Book Synopsis Analysis of the Behaviour of Advanced Reactor Pressure Vessel Steels Under Neutron Irradiation by : International Atomic Energy Agency
Download or read book Analysis of the Behaviour of Advanced Reactor Pressure Vessel Steels Under Neutron Irradiation written by International Atomic Energy Agency and published by . This book was released on 1986 with total page 144 pages. Available in PDF, EPUB and Kindle. Book excerpt: The final report of an IAEA co-ordinated research programme involving nine organizations in eight Member States during the period 1977-1983. The irradiation response of seven steels typical of modern practice, in the form of plants, forgings and submerged arc welds supplied by worldwide suppliers, was determined under light water reactor pressure vessel irradiation conditions.
Download or read book Reactor Dosimetry written by Harry Farrar and published by ASTM International. This book was released on 1994 with total page 854 pages. Available in PDF, EPUB and Kindle. Book excerpt: Proceedings of the 8th ASTM-Euratom Symposium, held in Vail, Colorado, Aug.-Sept. 1993, to provide a forum for experts to discuss their latest results under the broad theme of dosimetry for the correlation of radiation effects. Preceded by a summary of the keynote presentations and followed by summa
Download or read book Reactor Dosimetry written by J.P. Genthon and published by Springer Science & Business Media. This book was released on 2012-12-06 with total page 995 pages. Available in PDF, EPUB and Kindle. Book excerpt: Proceedings of the Fifth ASTM - Euratom Symposium on Rector Dosimetry, GKSS Research Centre, Geesthacht, F.R.G., September 24-28, 1984
Book Synopsis The Power Distribution and Neutron Fluence Measurements and Calculations in the VVER-1000 Mock-Up on the LR-0 Research Reactor by : M. Košt'ál
Download or read book The Power Distribution and Neutron Fluence Measurements and Calculations in the VVER-1000 Mock-Up on the LR-0 Research Reactor written by M. Košt'ál and published by . This book was released on 2012 with total page 10 pages. Available in PDF, EPUB and Kindle. Book excerpt: The power density distribution in a reactor has significant influence on core structures and pressure vessel mechanical resistance, as well as on the physical characteristics of nuclear fuel. This quantity also has an effect on the leakage neutron and photon field. This issue has become of increasing importance, as it touches on actual questions of the VVER nuclear power plant life time extension. This paper shows the comparison of calculated and experimentally determined pin by pin power distributions. The calculation has been performed with deterministic and Monte Carlo approaches. This quantity is accompanied by the neutron and photon flux density calculation and measurements at different points of the light water zero-power (LR-0) research reactor mock-up core, reactor built-in component (core barrel), and reactor pressure vessel and model. The effect of the different data libraries used for calculation is discussed.
Download or read book Reactor Dosimetry written by Harry Farrar and published by ASTM International. This book was released on 1989 with total page 792 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Determination of the Neutron and Gamma Flux Distribution in the Pressure Vessel and Cavity of a Boiling Water Reactor by : Mehdi Asgari
Download or read book Determination of the Neutron and Gamma Flux Distribution in the Pressure Vessel and Cavity of a Boiling Water Reactor written by Mehdi Asgari and published by . This book was released on 1990 with total page 101 pages. Available in PDF, EPUB and Kindle. Book excerpt: Abstract.
Book Synopsis Neutron Irradiation Embrittlement of Reactor Pressure Vessel Steels by : Lendell E. Steele
Download or read book Neutron Irradiation Embrittlement of Reactor Pressure Vessel Steels written by Lendell E. Steele and published by . This book was released on 1975 with total page 252 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Neutron Dosimetry Overview for WWERs by : Milan Brumovsk
Download or read book Neutron Dosimetry Overview for WWERs written by Milan Brumovsk and published by . This book was released on 2018 with total page 42 pages. Available in PDF, EPUB and Kindle. Book excerpt: Neutron dosimetry is a mandatory part of the monitoring of irradiation conditions within the reactor pressure vessels (RPVs) of all type of reactors, including water-water energetic reactors (WWERs). The main experimental part is connected with the surveillance specimen programs because the determination of neutron fluence in each of the surveillance specimens is required for the evaluation of radiation damage in RPV materials. Ex-vessel (cavity) neutron dosimetry is practically mandatory for all WWERs because it serves as the basis for fitting results from calculations of neutron fluence in the RPV wall. In addition, retrospective neutron dosimetry in WWER RPVs is supported by a high content (approximately 1 wt.%) of niobium in the upper layer of the austenitic cladding on the inner RPV surface. This paper describes the main principles of experimental neutron dosimetry in WWER RPVs and some specific results for different types of their units and different surveillance specimen programs. Some discussion is also held regarding different approaches for neutron fluence determination, i.e., for a differential threshold energy equal to 0.5 MeV in WWER studies.
Book Synopsis Integrity of Reactor Pressure Vessels in Nuclear Power Plants by :
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.
Book Synopsis Neutron Dosimetry for Reactor Pressure Vessel Applications by : WC. Morgan
Download or read book Neutron Dosimetry for Reactor Pressure Vessel Applications written by WC. Morgan and published by . This book was released on 1970 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt: The neutron dosimetry analysis effort discussed is aimed solely at obtaining the most accurate projections of neutron fluence and future radiation embrittlement in the pressure vessel of an operating commercial power reactor. The mechanical property changes in materials for reactor pressure vessel applications are caused by neutron/atomic lattice interactions that are highly sensitive to material composition, irradiation temperature, and population and energy of the damage causing neutrons. Of these, the neutron fluence and spectra are most difficult to define accurately for a given irradiation condition since neither can be measured directly. Nevertheless, if radiation induced changes are to be understood and subsequently used as a basis for projecting changes in real reactor components, the neutron dosimetry analysis must be as precise as possible; the ultimate results of any such projections are highly dependent upon the accuracy of the neutron spectrum and neutron fluence used as input. Improvements in both of these areas, as well as in standardization of approaches, are needed for accurate projection of radiation induced changes in reactor pressure vessels. The current status of neutron dosimetry in power reactors is reviewed, and guidelines are provided for improving future dosimetry of reactor pressure vessel surveillance programs.
