Final Results from the CARINA Project on Crack Initiation and Arrest of Irradiated German RPV Steels for Neutron Fluences in the Upper Bound PDF Download
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Author: M. Widera Publisher: ISBN: Category : Crack arrest Languages : en Pages : 28
Book Description
Comprehensive crack initiation and crack arrest tests were performed, up to neutron fluences far beyond the end of life range, on irradiated original reactor pressure vessel (RPV) steel specimens from German pressurized water reactors (PWR). The neutron fluences applied to the specimen materials under light water reactor conditions were between 5.44 x 1018n/cm2 and 7.67 x 1019n/cm2 (E > 1 MeV) with a neutron flux from 2.64 x 1010n/cm2s to 2.55 x 1012n/cm2s. The objective was to extend the already existing experimental database to reach a final comparative assessment of both the RTNDT and the RTT0 (Master Curve) concepts for proof of sufficient margin against RPV brittle fracture and to assess the impact of important factors such as neutron flux, manufacturing effects and specific irradiation effects such as late blooming effects. The test data show that most of the measured fracture toughness data are enveloped by the "lower bound" ASME KIc-curve for crack initiation and that the RTT0 concept compared to the RTNDT concept leads to lower reference temperatures for the base materials. However, for the weld materials, the general trend of RTNDT > RTT0 is less or not at all pronounced. It was also found that the measured ?T41 and ?T0 data show a good correlation and that the RTT0 of heat affected zone (HAZ) materials is lower compared to the base materials. Finally, the applicability of both the RTNDT and the Master curve concepts for crack arrest was confirmed, except the alternative use of RTT0 for indexing of the KIa fracture toughness curve could not be confirmed by the measured data. The application of a so-called duplex specimen geometry for crack arrest testing led to essential improvements; however, further optimizations of the specimens' fabrication process are still recommended. Finally, the complete database is assessed with respect to benefits for future RPV safety analyses.
Author: M. Widera Publisher: ISBN: Category : Crack arrest Languages : en Pages : 28
Book Description
Comprehensive crack initiation and crack arrest tests were performed, up to neutron fluences far beyond the end of life range, on irradiated original reactor pressure vessel (RPV) steel specimens from German pressurized water reactors (PWR). The neutron fluences applied to the specimen materials under light water reactor conditions were between 5.44 x 1018n/cm2 and 7.67 x 1019n/cm2 (E > 1 MeV) with a neutron flux from 2.64 x 1010n/cm2s to 2.55 x 1012n/cm2s. The objective was to extend the already existing experimental database to reach a final comparative assessment of both the RTNDT and the RTT0 (Master Curve) concepts for proof of sufficient margin against RPV brittle fracture and to assess the impact of important factors such as neutron flux, manufacturing effects and specific irradiation effects such as late blooming effects. The test data show that most of the measured fracture toughness data are enveloped by the "lower bound" ASME KIc-curve for crack initiation and that the RTT0 concept compared to the RTNDT concept leads to lower reference temperatures for the base materials. However, for the weld materials, the general trend of RTNDT > RTT0 is less or not at all pronounced. It was also found that the measured ?T41 and ?T0 data show a good correlation and that the RTT0 of heat affected zone (HAZ) materials is lower compared to the base materials. Finally, the applicability of both the RTNDT and the Master curve concepts for crack arrest was confirmed, except the alternative use of RTT0 for indexing of the KIa fracture toughness curve could not be confirmed by the measured data. The application of a so-called duplex specimen geometry for crack arrest testing led to essential improvements; however, further optimizations of the specimens' fabrication process are still recommended. Finally, the complete database is assessed with respect to benefits for future RPV safety analyses.
Author: H. Hein Publisher: ISBN: Category : Crack arrest Languages : en Pages : 24
Book Description
Pre-irradiated original reactor pressure vessel (RPV) materials covering all four German pressurized water reactors (PWR) construction lines were tested in the Crack Initiation and Arrest of Irradiated Steel Materials program to create a database of fracture toughness and arrest values for neutron fluences beyond the end of life range. The new database comprises data from both unirradiated and irradiated RPV base and weld materials generated by tensile, Charpy-V impact, fracture toughness KJc, and crack arrest KIa tests. The test matrix consists of materials with optimized chemical composition and with high Copper or high Nickel content, respectively. Based on the generated and already existing data the RTNDT and the RTT0 (Master Curve) concepts are applied with specific view on reference temperatures, transition temperature shifts, and on possible correlations between the criteria used in both concepts. In this context the consequences of some influencing factors like type and chemical composition of the RPV steel, its manufacturing conditions, and the specimen type and size on the reference temperatures are discussed. Moreover, the test results are assessed with respect to the American Society of Mechanical Engineers (ASME) code and German Nuclear Safety Standards Commission safety standards. The crack arrest characteristics for these typical RPV materials are also determined in a twofold way by testing Compact Crack Arrest specimens and by evaluation of instrumented Charpy-V impact test data. The available results made a good point that crack arrest is a reliable phenomenon that doubtless exists. It is also shown that the obtained KIa data can be enveloped by applying the ASME KIc lower bound curve indexed by different reference temperatures. Finally, the results show that the used RPV materials are well designed in terms of material behavior under irradiated conditions and that optimized manufacture specifications are of great benefit particularly after long operation times.
Author: DJ. Michel Publisher: ISBN: Category : Crack propagation Languages : en Pages : 23
Book Description
The fatigue and creep-fatigue crack propagation performance of Type 316 stainless steel has been investigated following fast neutron (n) irradiation to fluence levels of ~1.5 x 1022 and ~5 x 1022 n/cm2 (>0.1 MeV), ~6 and 26 displacements per atom (dpa), respectively, at 649°C. The purpose of this work was to evaluate the effects of neutron fluence and temperature on the crack propagation resistance and failure mode of the steel. The results from fatigue tests of the annealed steel show that irradiation to both fluence levels at 649°C produced no significant effect on the crack propagation rate when compared with unirradiated steel tested at 649°C. For the 20 percent cold-worked steel, however, irradiation to the lower fluence level increased the crack propagation rate while at the higher fluence level the crack propagation rate was only slightly increased relative to the unirradiated material. For tests conducted using creep-fatigue cycling, the effect of a 1-min hold time at the maximum cyclic load was to produce a marked increase in the crack propagation rate of the annealed steel irradiated to the lower fluence level. At the higher fluence level, the inclusion of a 2-min hold time in the creep-fatigue cycle resulted in a further increase in the crack propagation rate. The effect of a 1-min hold time in the irradiated, 20 percent cold-worked steel was to significantly increase the crack propagation rates, particularly at the low fluence level at 649°C. Scanning electron microscope examination of the fracture surfaces of the tested specimens revealed that the failure mode of the specimens which exhibited increased crack propagation rates was primarily intergranular while a transgranular mode was observed for specimens with lower crack propagation rates. The results point toward a synergistic relationship between thermomechanical history, precipitate formation, and hold time effects as the responsible mechanism for the crack propagation performance.
Author: Tao Jiang Publisher: Springer ISBN: 3030059553 Category : Technology & Engineering Languages : en Pages : 785
Book Description
In recent years, global metallurgical industries have experienced fast and prosperous growth. High-temperature metallurgical technology is the backbone to support the technical, environmental, and economical needs for this growth. This collection features contributions covering the advancements and developments of new high-temperature metallurgical technologies and their applications to the areas of processing of minerals; extraction of metals; preparation of refractory and ceramic materials; sintering and synthesis of fine particles; treatment and recycling of slag and wastes; and saving of energy and protection of environment. The volume will have a broad impact on the academics and professionals serving the metallurgical industries around the world.
Author: Yuri Hovanski Publisher: Springer ISBN: 3030057526 Category : Technology & Engineering Languages : en Pages : 275
Book Description
This book is a compilation of the recent progress on friction stir technologies including high-temperature applications, industrial applications, dissimilar alloy/materials, lightweight alloys, simulation, control, characterization, and derivative technologies. The volume offers a current look at friction stir welding technology from application to characterization and from modeling to R&D. Contributions document advances in application, controls, and simulation of the friction stir process to aid researchers in seeing the current state-of-the-art.
Author: M. Widera
Author: M. Widera
Author: H. Hein
Author: U.S. Nuclear Regulatory Commission
Author: S. K. Iskander
Author: S. K. Iskander
Author: DJ. Michel
Author: S. J. Paprocki
Author: Tao Jiang
Author: Frederick Fongsun Ling
Author: Yuri Hovanski