You are being redirected because this document is part of your ASTM Compass® subscription.
    This document is part of your ASTM Compass® subscription.

    If you are an ASTM Compass Subscriber and this document is part of your subscription, you can access it for free at ASTM Compass

    The Neutron Irradiation Effect on the Mechanical Properties and Structure of Beryllium

    Published: 01 January 1999

      Format Pages Price  
    PDF (564K) 15 $25   ADD TO CART
    Complete Source PDF (24M) 1120 $164   ADD TO CART

    Cite this document

    X Add email address send
      .RIS For RefWorks, EndNote, ProCite, Reference Manager, Zoteo, and many others.   .DOCX For Microsoft Word


    The results of an investigation into the effects of neutron irradiation on the mechanical properties and structure of beryllium are presented. Irradiation was performed in the BOR-60 reactor up to doses of 0.7–1.1 × 1022 n/cm2 (E > 0.1 MeV) at irradiation temperatures of 350°C, 400°C, 520°C, 780°C. Two modifications of RF beryllium, i.e. DShG-200 and TShG-56, were chosen for investigation.

    For irradiation at temperatures of 350 – 400°C Be hardening due to the accumulation of radiation defect complexes. Hardening is accompanied with a sharp drop in plasticity at Ttest ≤ 300°C. The fracture of samples is of brittle, mainly transcrystallite, type. High-temperature irradiation (Tirr = 780°C) gives rise to large helium pores over the grain boundaries and smaller pores in the grain body. Fracture is brittle and intercrystalline at Ttest ≥ 600°C. Helium embrittlement is also accompanied with a drop in the Be mechanical properties. The conclusion is made that the irradiation temperature range, where irradiated beryllium has a satisfactory level of properties, is rather narrow: 300°C ≤ T ≤500°C.

    Author Information:

    Fabritsiev, SA
    Head of Laboratory, D.V. Efremov Scientific Research Institute, St. Petersburg,

    Pokrovsky, AS
    Principal Scientist, Scientific Research Institute of Atomic Reactors, Dimitrovgrad,

    Bagautdinov, RM
    Engineer, Scientific Research Institute of Atomic Reactors, Dimitrovgrad,

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP13920S