The role of pressure vessel embrittlement in the long term operation of nuclear power plants

Ballesteros, A.; Ahlstrand, R.; Christiane, Bruynooghe; Estorff, U. von; Debarberis, L.

doi:10.1016/j.nucengdes.2011.12.005

Cited by 14 publications

(13 citation statements)

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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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“…Additionally, NOMAD focuses on the validation of the existing surveillance programs with respect to the actual vessel under LTO conditions, in terms of equivalence of radiation damage accumulation. These topics are of particular importance in terms of lifetime extension of existing operating reactors, the reactor pressure vessel (RPV) being considered the only part of the primary loop, which cannot be replaced [7,8].…”

Section: Nomadmentioning

confidence: 99%

Reactor performance, system reliability, instrumentation and control

Schumm

Rabung

Marque

et al. 2020

EPJ Nuclear Sci. Technol.

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We present a cross-cutting review of three on-going Horizon 2020 projects (ADVISE, NOMAD, TEAM CABLES) and one already finished FP7 project (HARMONICS), which address the reliability of safety-relevant components and systems in nuclear power plants, with a scope ranging from the pressure vessel and primary loop to safety-critical software systems and electrical cables. The paper discusses scientific challenges faced in the beginning and achievements made throughout the projects, including the industrial impact and lessons learned. Two particular aspects highlighted concern the way the projects sought contact with end users, and the balance between industrial and academic partners. The paper concludes with an outlook on follow-up issues related to the long term operation of nuclear power plants.

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“…Specifically, copper, phosphorous, and nickel content are the most influential parameters [9]. At present, requirements on materials with high strength and toughness are arising to increase the power generation capacity and operation life of nuclear power plants [13,22,29,56].…”

Section: Stage 1-1: Defining the Case Studymentioning

confidence: 99%

“…For the standard operating conditions of a nuclear reactor, chemical composition is more influential [45] on the process of neutron irradiation embrittlement than neutron flux [33] and irradiation temperature [28,41]. Specifically, copper, phosphorous, and nickel content are the most influential parameters [9]. At present, requirements on materials with high strength and toughness are arising to increase the power generation capacity and operation life of nuclear power plants [13,22,29,56].…”

Section: Stage 1-1: Defining the Case Studymentioning

confidence: 99%

An educational software to reinforce the comprehensive learning of materials selection

Rodríguez-Prieto

Camacho

Merayo

et al. 2017

Comp Applic In Engineering

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An educational software, called CalSev 1.0.2, has been developed for supporting the teaching in materials selection seminars. As a case study, a selection of materials for nuclear reactor pressure vessels has been chosen, because it is a representative example of the relationship between chemical composition, mechanical properties, and in-service behavior. This software has been developed to improve the students' understanding of the materials selection tasks, providing an interactive user-friendly platform that allows to modify-in real time-the content of chemical elements and mechanical requirements to obtain a materials performance evaluation. Due to its versatility, this informatics tool represents a great value for educational purposes, with special impact in blended and distance learning, by simplifying the arduous task of materials selection for a wide range of applications and promoting a collaborative working environment by easing the creation of small groups analyzing different study cases. Finally, to evaluate the functionality, interest, user-friendliness and the educational characteristics of CalSev 1.0.2, a survey among 36 undergraduate students has been carried out. K E Y W O R D Scomprehensive learning, computer-aided tool, educational support, materials selection, materialsEngineering is a practicing profession devoted to harnessing and modifying the three fundamental resources that humankind has available for the creation of all technology: energy, materials, and information [19]. In addition, nowadays, engineers need access to material attributes data and, since the quantity of data is large and the methods tedious to implement by hand, computer-based tools are necessary to enable the right selection of materials depending on the application [5].Selection of suitable materials for a given component is thus one of the hardest tasks to perform and hence, designers need to put their utmost effort in identifying the best materials with specific functionalities to fulfill the application requirements [39]. Design of components is associated with the Abbreviations: ASME B&PV, American society of mechanical engineers boiler and pressure vessels; JSME, Japanese society of mechanical engineers; KTA, Kerntechnischer Ausschuss (German nuclear commission); L e , experimental limit provided by key works; L s , standardized limit as described by the manufacturing codes; L s (Min) , minimum value of the standardized limits; L s (Max) , maximum value of the standardized limits; PWR, pressurized water reactors; RCC-MR, French code of nuclear design; RPV, reactor pressure vessels; SL/SLM, stringency level/stringency level methodology; SL (Max) , maximum stringency level; UTS, ultimate tensile strength (minimum required value); WORA, write once, run anywhere; XML, eXtensible markup language; Y p , yield point (minimum required value); σ max , maximum standard deviation.Comput Appl Eng Educ. 2018;26:125-140.wileyonlinelibrary.com/cae

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The role of pressure vessel embrittlement in the long term operation of nuclear power plants

Cited by 14 publications

References 13 publications

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

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

Reactor performance, system reliability, instrumentation and control

An educational software to reinforce the comprehensive learning of materials selection

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