Results 131 to 140 of about 779 (168)

Simulation of high fluence fast neutron damage with heavy ion bombardment

Radiation Effects, 1971
Abstract 316 stainless steel has been irradiated with 5 MeV Cu ions to a fluence of 2 × 1016 ions/cm2 at 500°C. Transmission electron microscopy of this sample reveals that 6 × 1015 voids/cm2 of average diameter equal to 180 A were produced. A method for correlating the fluence of ions with equivalent neutron fluences is described. This method predicts
G. L. Kulcinski, J. J. Laidler, D. G. Doran   +2 more
openaire   +1 more source

Magnetic parameters of Kh16N15M3B steel irradiated to a high fast-neutron fluence

Soviet Atomic Energy, 1988
Austenitic stainless steels are widely used in fast-reactor cores; they represent metastable solid solutions. They work at high fast-neutron fluxes and elevated temperatures, which accelerate the decomposition substantially [I]. The decomposition produces segregations of carbide, nitride, intermetallide, and other phases [2], which largely determine ...
Yu. G. Chukalkin, V. V. Petrov, V. R. Shtirts, V. I. Barsanov, B. N. Goshchitskii   +4 more
openaire   +1 more source

Electrical and optical analysis of low fluence fast neutron damage to JFETs

1999 Fifth European Conference on Radiation and Its Effects on Components and Systems. RADECS 99 (Cat. No.99TH8471), 2003
The effects of fast neutron irradiation (30 MeV) on silicon n-channel JFETs are studied. Electrical parameters of the gate-channel junction are analyzed at several fluences using a custom software. Electrical parameter changes are attributed to bulk semiconductor defects.
S. Forster, A. Hoffmann, J.-P. Charles, S.E. Kerns, D.V. Kerns, M. de la Bardonnie, P. Mialhe   +6 more
openaire   +1 more source

A new Recoil Proton Telescope for energy and fluence measurement of fast neutron fields

2015 4th International Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA), 2015
The spectrometer ATHENA (Accurate Telescope for High Energy Neutron metrology Applications), is being developed at the IRSN / LMDN (Institut de Radioprotection et de SUrete nucleaire / Laboratoire de Metrologie et de dosimetrie des neutrons) and aims at characterizing energy and fluence of fast neutron fields.
M. Bachaalany, L. Lebreton, D. Husson, S. Higueret   +3 more
openaire   +1 more source

Spectral fluence rates of the fast reactor neutron beam MedApp at FRM II

Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 2008
Abstract The MedApp facility at the research reactor FRM II supplies a beam of fast neutrons created by thermal fission of 235 U. It can be used for medical applications like the irradiation of human cancer, for radiography and tomography in non-destructive material characterisation as well as for the irradiation of technical and biological ...
Harald Breitkreutz, Franz M. Wagner, Anton Röhrmoser, Winfried Petry   +3 more
openaire   +1 more source

On the performance of ENDF/B-VII.0 data for fast neutron fluence calculations

Annals of Nuclear Energy, 2008
The newest release of the Evaluated Nuclear Data File, ENDF/B-VII.0, has recently become available, along with the announcement of its significant advances over previous versions. The older ENDF/B releases, however, have been assessed for numerous applications in the past and, as such, currently find wide application in the nuclear industry.
Vasiliev, A., Kolbe, E., Ferroukhi, H., Zimmermann, M. A., Chawla, R.   +4 more
openaire   +2 more sources

New NEA Benchmarks for Calculating Fast Neutron Fluence in the Reactor Pressure Vessel

2001
For proving the precision achievable today in predicting the neutron fluence for reactor pressure vessels, the OECD/NEA initiated a new international benchmark exercise as a blind test, where the measured results are not known in advance. To validate two- and three-dimensional radiation transport codes, high precision measurements at the VENUS critical
G Hehn, BC Na
openaire   +1 more source

Neutron Fluence Limit Determinations for Some Fast Flux Test Facility Components

1970
This paper describes the analytical procedures that have been developed at Battelle-Northwest Laboratory (BNWL) and Westinghouse Advanced Reactors Division (ARD) to determine neutron fluence limits for certain components of the Fast Flux Test Facility (FFTF), namely the core barrel, core support structure, and the reactor vessel.
RA Moen, JC Tobin, KC Thomas
openaire   +1 more source

Examination of the Irradiated Metal of WWER-Type Reactor Internals after 45 Years of Operations: Part 2. Calculation-Based and Experimental Determination of the Fluence of Fast Neutrons and Damage Dose

Inorganic Materials: Applied Research, 2021
Margolin B Z
exaly  

Monitoring Fast Neutron Fluence

Instruments and Experimental Techniques
A. R. Belozerova, V. V. Pavlov, S. A. Enin, T. I. Chernysheva   +3 more
openaire   +1 more source