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Author: WL. Server Publisher: ISBN: Category : Fracture toughness Languages : en Pages : 11
Book Description
The International Atomic Energy Agency (IAEA) has sponsored a series of Coordinated Research Programs (CRPs) that have been focused on integrity of reactor pressure vessel (RPV) materials. The emphasis in the last few years has been on the development of a large fracture mechanics database of three-point bend fracture toughness tests on precracked Charpy specimens and larger 1T (25.4 mm thickness) compact tension specimens, using the Master Curve approach that has been standardized in ASTM Test Method for the Determination of Reference Temperature, To, for Ferritic Steels in the Transition Range (E 1921). More than 20 international laboratories have conducted a significant amount of fracture toughness testing to allow evaluation of the Master Curve results obtained following ASTM E 1921. The current CRP also has the objective to develop international guidelines for producing adequate Master Curve data and applying the data to RPV integrity analyses. This paper will first describe a preliminary review of the data that have been produced with emphasis on the A533B-1 correlation monitor heat JRQ, which has served as a key material for the CRP. The main emphasis of the paper will be on the development of international guidelines for applying the Master Curve data that can be obtained from irradiated sample material for the most limiting RPV material.
Author: WL. Server Publisher: ISBN: Category : Fracture toughness Languages : en Pages : 11
Book Description
The International Atomic Energy Agency (IAEA) has sponsored a series of Coordinated Research Programs (CRPs) that have been focused on integrity of reactor pressure vessel (RPV) materials. The emphasis in the last few years has been on the development of a large fracture mechanics database of three-point bend fracture toughness tests on precracked Charpy specimens and larger 1T (25.4 mm thickness) compact tension specimens, using the Master Curve approach that has been standardized in ASTM Test Method for the Determination of Reference Temperature, To, for Ferritic Steels in the Transition Range (E 1921). More than 20 international laboratories have conducted a significant amount of fracture toughness testing to allow evaluation of the Master Curve results obtained following ASTM E 1921. The current CRP also has the objective to develop international guidelines for producing adequate Master Curve data and applying the data to RPV integrity analyses. This paper will first describe a preliminary review of the data that have been produced with emphasis on the A533B-1 correlation monitor heat JRQ, which has served as a key material for the CRP. The main emphasis of the paper will be on the development of international guidelines for applying the Master Curve data that can be obtained from irradiated sample material for the most limiting RPV material.
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: 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: 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: ISBN: 9789201110091 Category : Political Science Languages : en Pages : 167
Book Description
This publication provides information about the master curve approach for assessing the structural integrity of reactor pressure vessels (RPVs) under current and future operation and accident conditions in nuclear power plants (NPPs). This direct measurement of fracture toughness approach is technically superior to the correlative and indirect methods used in the past to assess irradiated RPV integrity. The results in the report should allow utility engineers and scientists to directly measure fracture toughness using small surveillance sized specimens and apply the results using the master curve approach for RPV structural integrity assessment in NPPs.
Author: International Atomic Energy Agency Publisher: ISBN: 9781523129942 Category : Languages : en Pages : 181
Book Description
This publication provides information about the master curve approach for assessing the structural integrity of reactor pressure vessels (RPVs) under current and future operation and accident conditions in nuclear power plants (NPPs). This direct measurement of fracture toughness approach is technically superior to the correlative and indirect methods used in the past to assess irradiated RPV integrity. The results in the report should allow utility engineers and scientists to directly measure fracture toughness using small surveillance sized specimens and apply the results using the master curve approach for RPV structural integrity assessment in NPPs.
Author: Robert Odette Publisher: Newnes ISBN: 012397349X Category : Technology & Engineering Languages : en Pages : 673
Book Description
High-performance alloys that can withstand operation in hazardous nuclear environments are critical to presentday in-service reactor support and maintenance and are foundational for reactor concepts of the future. With commercial nuclear energy vendors and operators facing the retirement of staff during the coming decades, much of the scholarly knowledge of nuclear materials pursuant to appropriate, impactful, and safe usage is at risk. Led by the multi-award winning editorial team of G. Robert Odette (UCSB) and Steven J. Zinkle (UTK/ORNL) and with contributions from leaders of each alloy discipline, Structural Alloys for Nuclear Energy Applications aids the next generation of researchers and industry staff developing and maintaining steels, nickel-base alloys, zirconium alloys, and other structural alloys in nuclear energy applications. This authoritative reference is a critical acquisition for institutions and individuals seeking state-of-the-art knowledge aided by the editors’ unique personal insight from decades of frontline research, engineering and management. Focuses on in-service irradiation, thermal, mechanical, and chemical performance capabilities. Covers the use of steels and other structural alloys in current fission technology, leading edge Generation-IV fission reactors, and future fusion power reactors. Provides a critical and comprehensive review of the state-of-the-art experimental knowledge base of reactor materials, for applications ranging from engineering safety and lifetime assessments to supporting the development of advanced computational models.
Author: WL. Server
Author: WL. Server
Author: 
Author: International Atomic Energy Agency
Author: International Atomic Energy Agency
Author: IAEA.
Author: International Atomic Energy Agency
Author: Martin L. Grossbeck
Author: International Atomic Energy Agency
Author: Robert Odette
Author: