ASTM E521 - 96(2009)e1

    Standard Practice for Neutron Radiation Damage Simulation by Charged-Particle Irradiation

    Active Standard ASTM E521 | Developed by Subcommittee: E10.08

    Book of Standards Volume: 12.02


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    Significance and Use

    4.1 A characteristic advantage of charged-particle irradiation experiments is precise, individual, control over most of the important irradiation conditions such as dose, dose rate, temperature, and quantity of gases present. Additional attributes are the lack of induced radioactivation of specimens and, in general, a substantial compression of irradiation time, from years to hours, to achieve comparable damage as measured in displacements per atom (dpa). An important application of such experiments is the investigation of radiation effects in not-yet-existing environments, such as fusion reactors.

    4.2 The primary shortcoming of ion bombardments stems from the damage rate, or temperature dependences of the microstructural evolutionary processes in complex alloys, or both. It cannot be assumed that the time scale for damage evolution can be comparably compressed for all processes by increasing the displacement rate, even with a corresponding shift in irradiation temperature. In addition, the confinement of damage production to a thin layer just (often 1 μm) below the irradiated surface can present substantial complications. It must be emphasized, therefore, that these experiments and this practice are intended for research purposes and not for the certification or the qualification of equipment.

    4.3 This practice relates to the generation of irradiation-induced changes in the microstructure of metals and alloys using charged particles. The investigation of mechanical behavior using charged particles is covered in Practice E821.

    1. Scope

    1.1 This practice provides guidance on performing charged-particle irradiations of metals and alloys. It is generally confined to studies of microstructural and microchemical changes carried out with ions of low-penetrating power that come to rest in the specimen. Density changes can be measured directly and changes in other properties can be inferred. This information can be used to estimate similar changes that would result from neutron irradiation. More generally, this information is of value in deducing the fundamental mechanisms of radiation damage for a wide range of materials and irradiation conditions.

    1.2 The word simulation is used here in a broad sense to imply an approximation of the relevant neutron irradiation environment. The degree of conformity can range from poor to nearly exact. The intent is to produce a correspondence between one or more aspects of the neutron and charged particle irradiations such that fundamental relationships are established between irradiation or material parameters and the material response.

    1.3 The practice appears as follows:

     

    Section

    Apparatus

      4

    Specimen Preparation

      5-10

    Irradiation Techniques (including Helium Injection)

     1112

    Damage Calculations

     13

    Postirradiation Examination

     14-16

    Reporting of Results

     17

    Correlation and Interpretation

     18-22


    1.4 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.

    1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.


    2. Referenced Documents (purchase separately) The documents listed below are referenced within the subject standard but are not provided as part of the standard.

    ASTM Standards

    C859 Terminology Relating to Nuclear Materials

    E170 Terminology Relating to Radiation Measurements and Dosimetry

    E821 Practice for Measurement of Mechanical Properties During Charged-Particle Irradiation

    E910 Test Method for Application and Analysis of Helium Accumulation Fluence Monitors for Reactor Vessel Surveillance, E706 (IIIC)

    E942 Guide for Simulation of Helium Effects in Irradiated Metals


    ICS Code

    ICS Number Code 27.120.10 (Reactor engineering)

    UNSPSC Code

    UNSPSC Code 26141700(Dosimetry equipment)


    DOI: 10.1520/E0521-96R09E01

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