Technical Briefs

Materials Databases and Knowledge Management for Advanced Nuclear Technologies

[+] Author and Article Information
Wolfgang Hoffelner

Department of Nuclear Energy and Safety, Paul Scherrer Institute, CH-5232 Villigen PSI, Switzerlandwolfgang.hoffelner@psi.ch

J. Pressure Vessel Technol 133(1), 014505 (Jan 21, 2011) (4 pages) doi:10.1115/1.4002262 History: Received February 15, 2010; Revised July 20, 2010; Published January 21, 2011; Online January 21, 2011

International collaborations like the generation IV initiative have the aim to create the technical basis for design and operation of advanced nuclear plants. Materials data shall be created in joint international materials projects. Data will be aggregated in databases like the “Generation IV Materials Handbook.” Mechanical data, and microstructural information and information concerning materials production shall be included. This information will be used to create or amend code rules, to provide a basis for life-time analysis, damage assessments, and for safety analyses. Such considerations need not only raw materials data but also tools for data analysis and evaluation. Multiscale modeling, establishing constitutive equations, development of advanced life-time prediction methods, quantitative correlation of mechanical properties with microstructure, quantification of environmental effects, tools for nondestructive evaluation, and condition based monitoring are important analysis techniques needed for safe design and operation of advanced plants. These needs led the author to ask the question if current databases could not be enlarged by data evaluation and methods tools, which could even end some day in the availability of web-based design codes and safety analyses. The database could also be used as a web-based discussion and development space. It could become then a powerful tool for knowledge management. This paper will discuss this concept based on some examples.

Copyright © 2011 by American Society of Mechanical Engineers
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Figure 6

Possible structure of a future knowledge based working space

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Figure 5

Web-based communication for joint cooperation

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Figure 4

Multiscale modeling and experimental validation methodologies. The arrow across the diagonal contains the modeling methodologies and refers to larger length and time scales when moving from the bottom-left corner to the top-right corner. Below the diagonal are types of experimental equipment that can be used at the different modeling scales: (1) synchrotron irradiation facility; (2) beamline; (3) TEM with triple-beam irradiation; (4) irradiation facility, Tandem accelerator; (5) in situ irradiation creep facility; (6) future X-ray free electron laser facility, Paul Scherrer Institute, Switzerland; (7) future Gen IV reactor (NGNP). The figures above the diagonal show types of results that can be compared with the modeling method in that column, such as the following: (8) fatigue, (9) channeling, (10) chemical composition of clusters, (11) TEM samples, and (12) magnetic domain patterning (after (12))

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Figure 3

100,000 h stress rupture strength of the superalloy IN617. The curves and the triangles are a copy of literature data (9). The open circles were determined by the author with a stress rupture parametrization described in Ref. 10. The evaluation was exclusively based on data points, which were digitized from literature data (11).

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Figure 2

A possible basic structure for an advanced database (knowledge base)

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Figure 1

Materials science and its relation to engineering and design needs



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