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Tuesday, May 12, 2020 | History

2 edition of PR-EDB, power reactor embrittlement data base, version 1 found in the catalog.

PR-EDB, power reactor embrittlement data base, version 1

Friedemann Stallmann

PR-EDB, power reactor embrittlement data base, version 1

program description

by Friedemann Stallmann

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  • 6 Currently reading

Published by Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission in Washington, DC .
Written in English

    Subjects:
  • Nuclear pressure vessels -- Defects -- Computer programs.,
  • Steel -- Embrittlement -- Computer programs.

  • Edition Notes

    Other titlesPower reactor embrittlement data base, version 1.
    Statementprepared by F.W. Stallmann, F.B.K. Kam, B.J. Taylor.
    ContributionsKam, F. B. K., Taylor, B. J., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering., Oak Ridge National Laboratory.
    The Physical Object
    Pagination1 v. (loose-leaf) :
    ID Numbers
    Open LibraryOL15362220M


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PR-EDB, power reactor embrittlement data base, version 1 by Friedemann Stallmann Download PDF EPUB FB2

Version 1 of the Embrittlement Data Base (EDB) [I] is such a comprehensive collection of such data resulting from the merging of the Power Reactor Embrittlement Data Base (PR-EDB) [2] and the Test Reactor Embrittlement Data Base (TR-EDB) [3].

Fracture toughness data were also integrated into Version 1 of the EDB. Technical Report: PR-EDB: Power Reactor Embrittlement Data Base, Version 2. Revision 2, Program description. Get this from a library. PR-EDB, power reactor embrittlement data base, version 1: program description. [Friedemann Stallmann; F B K Kam; B J Taylor; U.S.

Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering.; Oak Ridge National Laboratory.]. Power Reactor Embrittlement Database (PR-EDB) The TR-EDB also includes some annealing Charpy data.

The latest version, PR-EDB Version 3, contains test results of HAZ materials, weld materials and base materials, including plates, 35 forgings and three correlation monitor materials that were irradiated in capsules from.

Power Reactor Embrittlement Database (PR-EDB) The embrittlement database (EDB) (Wang and Subramani, ) is a database of ‘raw’ material embrittlement test data compiled from US power reactor surveillance capsule test results and from experiments in material test reactors. The NRC funds Oak Ridge National Laboratory (ORNL) to maintain the Author: M.

Tomimatsu, T. Hirota, T. Hardin, P. Todeschini. The results indicate that this new embrittlement predictor achieved about 66% and 53% reductions, respectively, in the uncertainties for the update General Electric (GE) Boiling Water Reactor (BWR) plate and weld data compared to the Nuclear Regulatory Commission (NRC) Regulatory GuideRev.

2 (RG/R2).Cited by: 2. Fracture Mechanics Data Deduced From Thermal-Shock and Related Experiments With LWR Pressure Vessel Material Annual Book of ASTM Standards, ASTM, West Conshohocken, PA, E Wang, J.

A., and. Subramani, R.,“ PR-EDB: Power Reactor Embrittlement Database Version 3,” Oak Ridge National Laboratory, Oak Ridge, TN, ORNL/TM Cited by: 4. Version 1 of the Embrittlement Data Base (EDB) is such a comprehensive collection of data resulting from merging version 2 of the Power Reactor Embrittlement Data Base (PR-EDB).

The purpose of this paper is to review the lessons learnt on the use of advanced materials on the design and operation of components in fission reactors and to Cited by: 3. [Show full abstract] resulting from the merging of the Power Reactor Embrittlement Data Base (PR-EDB) [2] and the Test Reactor Embrittlement Data Base (TR.

Integrity of Reactor Pressure Vessels in Nuclear Power Plants: Assessment of Irradiation Embrittlement Effects in Reactor Pressure Vessel Steels - Free ebook download as PDF File .pdf), Text File .txt) or read book online for free.

Integrity of Reactor Pressure Vessels in Nuclear Power Plants: Assessment of Irradiation Embrittlement Effects in Reactor Pressure Vessel Steels.

PR-EDB: Power Reactor Embrittlement Database - Version 3. SciTech Connect. Wang, Jy-An John; Subramani, Ranjit. The aging and degradation of light-water reactor pressure vessels is of particular concern because of their relevance to plant integrity and the magnitude of the expected irradiation embrittlement.