Radiation Damage of Reactor Pressure Vessel Steels

English, C.; Hyde, J.

doi:10.1016/b978-0-08-102865-0.00076-5

Cited by 8 publications

(11 citation statements)

References 37 publications

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“…Thus, the percentages of copper, nickel, and phosphorus in these pressure vessels materials are considered the most influential elements. [16][17][18][19] Thus, chemical composition is more influential on irradiation embrittlement than neutron flux and irradiation temperature at operation conditions. Since in a study conducted by Mager 20 no dependence was observed between the neutron flux value and the embrittlement of the material for neutron flux rates 21 ranging from ¼ 2.5 Â 10 18 n/cm 2 to ¼ 8.8 Â 10 19 n/cm 2 .…”

Section: Stage a Prediction Models Analysis And Sl Methodology Definmentioning

confidence: 99%

Selection of candidate materials for reactor pressure vessels: Application of irradiation embrittlement prediction models and a stringency level methodology

Rodríguez-Prieto¹,

Camacho²,

Sebastián³

2017

Proceedings of the Institution of Mechanical Engineers, Part L:

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The selection of materials for the reactor pressure vessel manufacturing is a complex process that involves great responsibility because small differences in chemical composition can adversely affect the manufacturing process and the in-service behavior of the material. Thus, it is recommendable to perform previous materials pre-selection stages based on the state-of-the-art knowledge, integrating research results with standardized requirements and using simplifier materials selection methodologies like the stringency level method. To address this issue, an evaluation of the influence of chemical composition on the shift of the ductile-to-brittle transition temperature has been performed using the most used and consolidated prediction models that are R.G. 1.99 Rev.2, NUREG/CR-6551, and ASTM E 900-02. A proposal of maximum limits for copper, nickel, and phosphorous to avoid irradiation embrittlement has been presented to carry out the process. The results have been analyzed by using the stringency level methodology to support the decision process. To this end, a materials data collection has been carried out to analyze the requirements described by 20 different specifications of materials from first to fourth generation of light water reactors, covering the main designs of pressurized reactors from Western Europe, North America, Japan, and Russia. It can be concluded that more recently developed materials exhibit more stringent requirements than earlier developed materials.

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Section: Stage a Prediction Models Analysis And Sl Methodology Definmentioning

confidence: 99%

Selection of candidate materials for reactor pressure vessels: Application of irradiation embrittlement prediction models and a stringency level methodology

Rodríguez-Prieto¹,

Camacho²,

Sebastián³

2017

Proceedings of the Institution of Mechanical Engineers, Part L:

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show abstract

“…The numerical predictions are not in quantitative agreement with the experimental curve, but increasing the nucleation rate may lead to a good agreement. Whatever the modelling chosen (effective parameter q χ or accounting explicitly for nucleation through A n ), two key questions remain: (1) what is the most relevant fracture mechanism related to void nucleation from carbides: increasing porosity vs. accelerated coalescence of larger scale voids, (2) in any cases, how to calibrate these parameters and to corroborate with fractographic observations. Figure 12: (a) Load-displacement curves for Material #2: solid lines and dashed lines correspond to numerical results using Eq.…”

Section: Discussionmentioning

confidence: 99%

“…Reactor Pressure Vessel (RPV) of Light Water Reactors (LWR) are made of low alloy steels such as A508 for modern LWRs [1]. These ferritic steels exhibit a ductile brittle transition [2].…”

Section: Introductionmentioning

confidence: 99%

“…The operating temperature of LWRs (∼ 290 • C) is well above the DBTT for A508 steels at the beginning of operation. However, neutron irradiation leads to an upward shift of the DBTT [1], thus requiring monitoring through dedicated surveillance programs [5,6] for structural integrity assessment. Neutron embrittlement of RPV steels can be assessed through impact tests on Charpy V-Notch (CVN) specimens or fracture toughness tests on pre-cracked specimens.…”

Section: Introductionmentioning

confidence: 99%

“…Neutron embrittlement of western RPV steels is due to irradiation-induced hardening resulting from the presence of solute clusters and matrix defects [1,20]. Non-hardening embrittlement related to segregation of alloying elements like phosphorus at grain boundaries under irradiation can be observed in specific conditions, i.e., VVER RPV steels [21], which are not considered here.…”

Section: Introductionmentioning

confidence: 99%

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