Lessons Learned From Developing Reactor Pressure Vessel Steel Embrittlement Database

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Description

Materials behaviors caused by neutron irradiation under fission and/or fusion environments can be little understood without practical examination. Easily accessible material information system with large material database using effective computers is necessary for design of nuclear materials and analyses or simulations of the phenomena. The developed Embrittlement Data Base (EDB) at ORNL is this comprehensive collection of data. EDB database contains power reactor pressure vessel surveillance data, the material test reactor data, foreign reactor data (through bilateral agreements authorized by NRC), and the fracture toughness data. The lessons learned from building EDB program and the associated database management activity regarding ... continued below

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Wang, Jy-An John August 1, 2010.

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Materials behaviors caused by neutron irradiation under fission and/or fusion environments can be little understood without practical examination. Easily accessible material information system with large material database using effective computers is necessary for design of nuclear materials and analyses or simulations of the phenomena. The developed Embrittlement Data Base (EDB) at ORNL is this comprehensive collection of data. EDB database contains power reactor pressure vessel surveillance data, the material test reactor data, foreign reactor data (through bilateral agreements authorized by NRC), and the fracture toughness data. The lessons learned from building EDB program and the associated database management activity regarding Material Database Design Methodology, Architecture and the Embedded QA Protocol are described in this report. The development of IAEA International Database on Reactor Pressure Vessel Materials (IDRPVM) and the comparison of EDB database and IAEA IDRPVM database are provided in the report. The recommended database QA protocol and database infrastructure are also stated in the report.

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  • Report No.: ORNL/TM-2010/20
  • Grant Number: DE-AC05-00OR22725
  • DOI: 10.2172/985285 | External Link
  • Office of Scientific & Technical Information Report Number: 985285
  • Archival Resource Key: ark:/67531/metadc1013989

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  • August 1, 2010

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  • Oct. 14, 2017, 8:36 a.m.

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Wang, Jy-An John. Lessons Learned From Developing Reactor Pressure Vessel Steel Embrittlement Database, report, August 1, 2010; United States. (digital.library.unt.edu/ark:/67531/metadc1013989/: accessed November 23, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.