The Accelerator Production of Tritium Materials Test Program

  title={The Accelerator Production of Tritium Materials Test Program},
  author={Stuart Andrew Maloy and Walter F. Sommer and Michael R. James and Tobias J. Romero and Manuel L{\'o}pez and Eugene L. Zimmermann and James M. Ledbetter},
  journal={Nuclear Technology},
  pages={103 - 114}
A materials qualification program has been developed to irradiate and test candidate materials (alloy 718, Type 316L, and Type 304L stainless steel, modified Fe9Cr-1Mo(T91), Al-6061-T6, and Al-5052-O) for use in the Accelerator Production of Tritium (APT) target and blanket. The irradiations were performed in prototypic proton and neutron spectra at prototypic temperatures (50 to 160°C). The study used the 800-MeV, 1.0-mA proton accelerator at the Los Alamos Neutron Science Center, which… Expand
6 Citations
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Abstract As part of the accelerator production of tritium and the spallation neutron source programs, the tensile properties of annealed 304L, 316LN and 316L stainless steel have been measured afterExpand
Performance of a Clad Tungsten Rod Spallation Neutron Source Target
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The high temperature three point bend testing of proton irradiated 316L stainless steel and Mod 9Cr–1Mo
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Pitfalls of tungsten multileaf collimator in proton beam therapy.
Tungsten seems to be not an optimal material for MLC in proton beam therapy, which may create unnecessary risks associated with the secondary neutrons and induced radioactivity for patients and staff depending on the patient load. Expand


Thermal analysis of the APT materials irradiation samples
The accelerator production of tritium (APT) project proposes to use a 1.7 GeV, 100 mA proton beam to produce neutrons from an Inconel 718 clad tungsten target. The neutrons are multiplied andExpand
Radiation damage calculations for the APT materials test program
A materials irradiation was performed at the Los Alamos Neutron Science Center (LANSCE) in the fall of 1996 and spring of 1997 in support of the Accelerator Production of Tritium (APT) program.Expand
Progress report on the accelerator production of tritium materials irradiation program
The Accelerator Production of Tritium (APT) project is developing an accelerator and a spoliation neutron source capable of producing tritium through neutron capture on He-3. A high atomic weightExpand
Low-temperature irradiation creep of fusion reactor structural materials
Abstract Irradiation creep has been investigated in the Oak Ridge Research Reactor in an assembly spectrally tailored to achieve a He : dpa ratio of 12–14:1 appm/dpa in austenitic stainless steels.Expand
Mechanical property changes in ferritic steels by 14 MeV neutron bombardment
Abstract Mechanical property changes induced in seven kinds of 9 Cr-2 Mo type mono- and dual-phase steels by 14 MeV neutron irradiation were investigated by means of post-irradiation mechanicalExpand
Specimen size effects on mechanical properties of 14 MeV neutron irradiated metals
Mechanical property changes induced in 9Cr2Mo dual-phase steels, pure-molybdenum and pure-vanadium by 14 MeV neutron irradiation in RTNS-II at LLNL were investigated by means of postirradiationExpand
Accelerator transmutation studies at Los Alamos with LAHET, MCNP, and CINDER`90
Versions of the CINDER code have been used over three decades for determination of reactor fuel inventories and aggregate neutron absorption and radioactive decay properties. The CINDER`90 code, anExpand
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