ASTM E521-23 PDF
Standard Practice for Investigating the Effects of Neutron Radiation Damage Using Charged-Particle Irradiation
Standard Practice for Investigating the Effects of Neutron Radiation Damage Using Charged-Particle Irradiation
- Статус документа:
- Действующий
- Формат:
- Электронный (PDF)
- Количество страниц:
- 22
- Дата публикации:
- 1 июня 2023 г.
- Издание:
- E521
- ICS:
- 27.120.10
SIGNIFICANCE AND USE 4.1 A characteristic advantage of charged-particle irradiation experiments is the 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 that may occur in materials exposed to environments which do not currently exist, such as in first wall materials used in 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 materials. 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. SCOPE 1.1 This practice provides guidance on performing charged-particle irradiations of metals and alloys, although many of the methods may also be applied to ceramic materials. It is generally confined to studies of microstructural and microchemical changes induced by 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 Where it appears, the word “simulation” should be understood to imply an approximation of the relevant neutron irradiation environment for the purpose of elucidating damage mechanisms. 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) 11 – 12 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, health, and environmental practices and determine the applicability of regulatory limitations prior to use. 1.6 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.
Abstract
Overview
ASTM E521-23: Standard Practice for Investigating the Effects of Neutron Radiation Damage Using Charged-Particle Irradiation sets forth recommended procedures for simulating neutron radiation effects by using charged-particle irradiation techniques. Developed by ASTM Committee E10, this standard enables researchers to approximate neutron-induced damage in metals and alloys, and, in certain cases, ceramics. By controlling key variables such as dose, dose rate, temperature, and environmental conditions, charged-particle irradiation offers a precise, flexible, and efficient way to study radiation-induced microstructural and microchemical changes. This supports the evaluation of candidate materials for nuclear energy systems, including those for fusion reactor research, where real neutron environments may not be accessible.
Key Topics
- Irradiation Control: Charged-particle experiments allow for independent control of dose, dose rate, temperature, and gas environment, supporting targeted research on material responses to radiation.
- Specimen Preparation: Detailed guidance is provided for pre-irradiation characterization, including elemental analysis, heat treatment, plastic deformation measurements, and surface preparation to ensure relevant and reproducible results.
- Helium Injection: Utilizes alpha particles to simulate helium accumulation from neutron transmutation, with techniques for quantifying and distributing helium within specimens.
- Damage Calculation: Discusses methodologies for calculating displacement rates and correlating charged-particle data with neutron-induced damage using the displacements per atom (dpa) metric.
- Postirradiation Examination: Covers recommended examination procedures for assessing microstructural and chemical changes, supporting the establishment of fundamental damage-response relationships.
Applications
The ASTM E521-23 standard is vital in applications where materials are destined for service environments subject to high radiation fields, especially when:
- Accelerated Testing: Researchers need to replicate years’ worth of neutron-induced material damage in a matter of hours, expediting material qualification and design processes.
- Fusion Reactor Materials: Enables assessment of candidate first wall and structural materials for next-generation fusion environments not yet realized in operating reactors.
- Fundamental Mechanism Studies: Supports investigation into radiation damage mechanisms, facilitating improved understanding of defect formation, swelling, embrittlement, and helium effects.
- Simulative Studies: Where direct neutron irradiation is impractical or unavailable, charged-particle methods provide a controllable and less hazardous alternative.
It is important to note that while ASTM E521-23 is a powerful research tool, it is not intended for certifying or qualifying materials for actual service environments; rather, its primary value lies in research, material development, and comparative studies.
Related Standards
For comprehensive evaluation and simulation of radiation effects, ASTM E521-23 references and complements several other standards, including:
- ASTM E821: Practice for Measurement of Mechanical Properties During Charged-Particle Irradiation
- ASTM E910: Test Method for Application and Analysis of Helium Accumulation Fluence Monitors for Reactor Vessel Surveillance
- ASTM E942: Guide for Investigating the Effects of Helium in Irradiated Metals
- ASTM C859: Terminology Relating to Nuclear Materials
- ASTM E170: Terminology Relating to Radiation Measurements and Dosimetry
International references include ICRU 60 and ICRU 85a for standardized quantities and units in ionizing radiation, facilitating global consistency in reporting and analysis.
By following the practices outlined in ASTM E521-23, the nuclear research community can produce meaningful, comparable data to enhance the development and understanding of materials for future nuclear applications, while adhering to global standards for accuracy and safety.
Технические детали
- Технический комитет
- E10 - Nuclear Technology and Applications
- SKU
- ASTM E521-23
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