Development of a custom block of radiation thermal creep and radiation growth of zirconium alloys in ANSYS computer code

Published 2018 | Version v1

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no abstract available

Additional details

Original title (Russian): Разработка пользовательского блока радиационно-термической ползучести и радиационного роста циркониевых сплавов в PK ANSYS

Publisher: AO IRM
Imprint Place: Ekaterinburg (Russian Federation)
ISBN: 978-5-9909054-5-0
Imprint Title: Inter-industry scientific and technical conference #Left-Pointing Double Angle Quotation Mark#Reactor materials of nuclear energy#Right-Pointing Double Angle Quotation Mark#. Abstracts
Imprint Pagination: 87 p.
Journal Page Range: p. 15-16

Title: Inter-industry scientific and technical conference on reactor materials of nuclear energy
Original Conference Title: Mezhotraslevaya nauchno-tekhnicheskaya konferentsiya «Reaktornye materialy atomnoj ehnergetiki»
Dates: 17-21 Sep 2018
Place: Sochi (Russian Federation)

Country of Publication: Russian Federation
Country of Input or Organization: Russian Federation
INIS RN: 51064062
Subject category: S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
Resource subtype / Literary indicator: No Abstract, Conference
Descriptors DEI: COMPUTER CODES; CREEP; FUEL ASSEMBLIES; RADIATION PROTECTION; SAFETY ANALYSIS; WWER TYPE REACTORS; ZIRCONIUM ALLOYS
Descriptors DEC: ALLOYS; ENRICHED URANIUM REACTORS; MECHANICAL PROPERTIES; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Notes: Imprint:Mezhotraslevaya nauchno-tekhnicheskaya konferentsiya #Left-Pointing Double Angle Quotation Mark#Reaktornye materialy atomnoj ehnergetiki#Right-Pointing Double Angle Quotation Mark#. Tezisy dokladov