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Author: International Atomic Energy Agency Publisher: IAEA ISBN: Category : Business & Economics Languages : en Pages : 70
Book Description
This publication has been developed under the Coordinated Research Project (CRP) entitled: Surveillance Program Results Application to Reactor Pressure Vessel Integrity Assessment. This publication provides a summary of master curve fracture toughness test results on small surveillance type specimens of the IAEA reference material JRQ and other national steels from numerous laboratories around the world. These results were a key ingredient used in the development of the guidance given in IAEA Technical Reports Series No. 429, Guidelines for Application of the Master Curve Approach to Reactor Pressure Vessel Integrity. This publication has been written to allow utility engineers and scientists to directly measure fracture toughness and apply the results using the master curve approach for RPV structural integrity assessment.--Publisher description.
Author: International Atomic Energy Agency Publisher: IAEA ISBN: Category : Business & Economics Languages : en Pages : 70
Book Description
This publication has been developed under the Coordinated Research Project (CRP) entitled: Surveillance Program Results Application to Reactor Pressure Vessel Integrity Assessment. This publication provides a summary of master curve fracture toughness test results on small surveillance type specimens of the IAEA reference material JRQ and other national steels from numerous laboratories around the world. These results were a key ingredient used in the development of the guidance given in IAEA Technical Reports Series No. 429, Guidelines for Application of the Master Curve Approach to Reactor Pressure Vessel Integrity. This publication has been written to allow utility engineers and scientists to directly measure fracture toughness and apply the results using the master curve approach for RPV structural integrity assessment.--Publisher description.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
These guidelines have been developed under an International Atomic Energy Agency (IAEA) Co-ordinated Research Project (CRP) titled ''Surveillance Programme Results Application to Reactor Pressure Vessel Integrity Assessment.'' The IAEA has sponsored a series of five CRPs that have led to a focus on measuring the best irradiation fracture parameters using relatively small test specimens for assuring structural integrity of reactor pressure vessel (RPV) materials in Nuclear Power Plants (NPPs).
Author: RB. Jenkins Publisher: ISBN: Category : Nuclear pressure vessels Languages : en Pages : 11
Book Description
Every commercial nuclear power reactor pressure vessel (RPV) is required to have a reactor vessel surveillance program at the time of plant licensing. The program is part of a continuing structural integrity assessment of the RPV. As such, the surveillance program supplements Section III of the American Society of Mechanical Engineers (ASME) Code [1],1 which is the design basis for nuclear power plant component pressure boundaries. The Code assumes that the materials of construction are ductile in the evaluation and design of all components. The surveillance program for each RPV is intended to provide assurance of continued applicability of the ASME Code, Appendix G, assessment of that RPV's operating limits. This assessment ensures that the RPV is always in a condition which precludes the unstable propagation of flaws in the vessel wall material.
Author: International Atomic Energy Agency Publisher: IAEA ISBN: Category : Business & Economics Languages : en Pages : 120
Book Description
The master curve approach for assessing the fracture toughness of a sampled irradiated material has been gaining acceptance throughout the world. This direct measurement approach is preferred over the correlative and indirect methods used in the past to assess irradiated reactor pressure vessel (RPV) integrity. The master curve methodology already has been or is being assimilated into the ASME Boiler and Pressure Vessel Code, ASTM standards, USNRC regulations, German regulations (KTA 3203), IAEA PTS guidelines for WWER reactors as well as the VERLIFE "Unified Procedure for WWER Component Lifetime Assessment" and other industry guidance documents governing RPV integrity analysis. As this report was prepared using the results of many research projects and experiments, these guidelines for application will be used for a long time to evaluate and assess the residual life of RPVs.
Author: Milan Brumovsk Publisher: ISBN: Category : Nuclear pressure vessels Languages : en Pages : 28
Book Description
Surveillance specimen programs in reactor pressure vessels (RPVs) are an important part of monitoring material property changes during reactor operations. Results of testing such specimens in surveillance programs, if properly designed and operated, should be the basis for assessing RPV integrity and lifetime. This paper describes special features of surveillance programs in individual water-water energetic reactors (WWERs)V-230 and V-213 for WWER-440s and V-320 for WWER-1000sthat lead to changes in normative embrittlement trend curves of base and weld metals in these RPVs. Finally, VERLIFE procedures for evaluating test results of surveillance specimens are described together with their application to RPV integrity assessment with the use of both types of transition temperatures: critical temperature of brittleness, Tk, and reference temperature, T0.
Author: Patrick Todeschini Publisher: ISBN: Category : Nuclear Reactor Technology Languages : en Pages : 18
Book Description
This paper describes the methodology of the French surveillance program as well as some aspects of the experience gained during its progress. Its main uses in the structural integrity assessment of the vessel consist of updating and validating the conservatism of the prediction of the lower-bound toughness curve used to assess the margins against brittle fracture. Its perspectives in the frame of the planned extended operation beyond 40 years are associated with the flux reductions that will be implemented in the 900-MWe fleet. Two surveillance capsules are dedicated to a specific monitoring in the 40 to 60-year range to complement the data set in the relevant fluence range.
Author: International Atomic Energy Agency
Author: International Atomic Energy Agency
Author: IAEA.
Author: 
Author: 
Author: S. Chatterjee (Nuclear physicist)
Author: RB. Jenkins
Author: International Atomic Energy Agency
Author: Milan Brumovsk
Author: K. G. Hoge
Author: Patrick Todeschini