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Specimen-Size Considerations in Crack-Arrest Testing of Irradiated RPV Steels

Specimen-Size Considerations in Crack-Arrest Testing of Irradiated RPV Steels PDF Author: MP. Landow
Publisher:
ISBN:
Category : Crack-arrest toughness
Languages : en
Pages : 14

Book Description
Few crack-arrest data are available for irradiated reactor pressure vessel steels, in part because the specimens commonly used to investigate crack-arrest behavior are relatively large (200 mm square by 50 mm thick). This paper addresses the question of specimen-size requirements for crack-arrest testing of irradiated RPV steels and offers several recommendations with regard to specimen size, specimen design, and testing procedures for efficient utilization of the limited space available in irradiation capsules.

Specimen-Size Considerations in Crack-Arrest Testing of Irradiated RPV Steels

Specimen-Size Considerations in Crack-Arrest Testing of Irradiated RPV Steels PDF Author: MP. Landow
Publisher:
ISBN:
Category : Crack-arrest toughness
Languages : en
Pages : 14

Book Description
Few crack-arrest data are available for irradiated reactor pressure vessel steels, in part because the specimens commonly used to investigate crack-arrest behavior are relatively large (200 mm square by 50 mm thick). This paper addresses the question of specimen-size requirements for crack-arrest testing of irradiated RPV steels and offers several recommendations with regard to specimen size, specimen design, and testing procedures for efficient utilization of the limited space available in irradiation capsules.

The Use of Small-scale Specimens for Testing Irradiated Material

The Use of Small-scale Specimens for Testing Irradiated Material PDF Author: W. R. Corwin
Publisher: ASTM International
ISBN: 0803104405
Category : Alloys
Languages : en
Pages : 387

Book Description


Final Results from the Crack Initiation and Arrest of Irradiated Steel Materials Project on Fracture Mechanical Assessments of Pre-Irradiated RPV Steels Used in German PWR

Final Results from the Crack Initiation and Arrest of Irradiated Steel Materials Project on Fracture Mechanical Assessments of Pre-Irradiated RPV Steels Used in German PWR PDF 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.

Fracture Mechanics

Fracture Mechanics PDF Author: D. T. Read
Publisher: ASTM International
ISBN: 0803109490
Category : Fractura de sólidos
Languages : en
Pages : 1108

Book Description


Crack Arrest Concepts for Failure Prevention and Life Extension

Crack Arrest Concepts for Failure Prevention and Life Extension PDF Author: Gyoujin Cho
Publisher: Woodhead Publishing
ISBN: 9781855732643
Category : Technology & Engineering
Languages : en
Pages : 334

Book Description
The proceedings of a seminar held at TWI in September, 1995, focusing on crack arrest philosophy which aknowledges that a brittle crack is arrested when it emerges from the critical region. Papers from prestigious researchers presented a critique and assessment of the theory and its application under: Introduction to crack arrest concepts; Recent trends in crack arrest research; Application of crack arrest concepts.

Advances in Nuclear Science and Technology

Advances in Nuclear Science and Technology PDF Author: Jeffery Lewins
Publisher: Springer Science & Business Media
ISBN: 0306470888
Category : Technology & Engineering
Languages : en
Pages : 180

Book Description
Since its initiation in 1962, this series has presented authoritative reviews of the most important developments in nuclear science and engineering, from both theoretical and applied perspectives. In addition, many original contributions are included.

Crack-Arrest Testing of Irradiated Nuclear Reactor Pressure Vessel Steels at the Oak Ridge National Laboratory

Crack-Arrest Testing of Irradiated Nuclear Reactor Pressure Vessel Steels at the Oak Ridge National Laboratory PDF Author: SK. Iskander
Publisher:
ISBN:
Category : ASME KIa curve
Languages : en
Pages : 9

Book Description
Crack-arrest testing of nuclear pressure vessel steels has been conducted at Oak Ridge National Laboratory for many years. Four methods have been used to initiate fast-running cracks in crackarrest specimens: (1) the deposition of a brittle weld bead using hardfacing weld electrodes, (2) water quenching a chevron crack tip, (3) quenching the crack tip by discharging a large current into the crack tip region, and (4) the use of duplex specimens. A problem often encountered with Methods 1 and 4 is the control of the width of the heat-affected zone (HAZ). The HAZ is generally tough and can arrest crack propagation before it has run into the test section. Irradiated crack-arrest specimens were prepared using Methods 1, 3, and 4. Method 1 was the most successful, while Method 4 was the least successful. This paper will discuss some of the reasons for the success, or lack of, as well as the results of testing both a high-copper weldment and a low-copper forging in terms of the shift and shape of the Ka toughness curve compared to the Charpy V-notch shift. The present ASTM Test Method for Determining Plane-Strain Crack-Arrest Fracture Toughness, KIa, of Ferritic Steels (E 1221-88) validity criteria will also be discussed in light of the results.

Critical Experiments, Measurements, and Analyses to Establish a Crack-arrest Methodology for Nuclear Pressure Vessel Steels

Critical Experiments, Measurements, and Analyses to Establish a Crack-arrest Methodology for Nuclear Pressure Vessel Steels PDF Author: Alan R. Rosenfield
Publisher:
ISBN:
Category : Fracture mechanics
Languages : en
Pages : 124

Book Description


INIS Atomindex

INIS Atomindex PDF Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 870

Book Description


Final Results from the CARINA Project on Crack Initiation and Arrest of Irradiated German RPV Steels for Neutron Fluences in the Upper Bound

Final Results from the CARINA Project on Crack Initiation and Arrest of Irradiated German RPV Steels for Neutron Fluences in the Upper Bound PDF 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.