Response of structural materials to radiation environments
An evaluation of proton and neutron damage to aluminum, stainless steel, nickel alloys, and various aluminum alloys has been performed. The proton studies were conducted at energies of 200 MeV, 800 MeV, and 23.5 GeV. The proton studies consisted of evaluation and characterization of proton-irradiated window/target materials from accelerators and comparison to nonirradiated archival materials. The materials evaluated for the proton irradiations included 99.9999 wt% aluminum, 1100 aluminum, 5052 aluminum, 304 stainless steel, and inconel 718. The neutron damage research centered on 6061 T-6 aluminum which was obtained from a control-rod follower from the Brookhaven National Laboratory`s (BNL) High Flux Beam Reactor (HFBR). This material had received thermal neutron fluence up to {approximately}4 {times} 10{sup 23} n/cm{sup 2}. The possible effects of thermal-to-fast neutron flux ratios are discussed. The increases in tensile strength in the proton-irradiated materials is shown to be the result of atomic displacements. These displacements cause interstitials and vacancies which aggregate into defect clusters which result in radiation hardening of the materials. Production of gas (helium) in the grain boundaries of proton irradiated 99.9999 wt% aluminum is also discussed. The major factor contributing to the mechanical-property changes in the neutron-irradiated 6061 T-6 aluminum is the production of transmutation products formed by interactions of the aluminum with thermal neutrons. The metallurgical and mechanical-property evaluations for the research consisted of electron microscopy (both scanning and transmission), tensile testing, and microhardness testing.
- Research Organization:
- Brookhaven National Lab., Upton, NY (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 555563
- Report Number(s):
- BNL--64952; CONF-970201--; ON: DE98001629; BR: DP0404012
- Country of Publication:
- United States
- Language:
- English
Similar Records
Corrosion Testing in Support of the Accelerator Production of Tritium Program
The Accelerator Production of Tritium Materials Test Program
Thermal analysis of the APT materials irradiation samples
Conference
·
Mon Nov 06 23:00:00 EST 2000
·
OSTI ID:767284
The Accelerator Production of Tritium Materials Test Program
Journal Article
·
Sun Oct 15 00:00:00 EDT 2000
· Nuclear Technology
·
OSTI ID:20822207
Thermal analysis of the APT materials irradiation samples
Conference
·
Wed Dec 30 23:00:00 EST 1998
·
OSTI ID:325773