Author:
Joly S.,Voignier J.,Grenier G.,Drake D.M.,Nilsson L.
Cited by
16 articles.
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1. The Advancement of Neutron Shielding Materials for the Storage of Spent Nuclear Fuel;Science and Technology of Nuclear Installations;2021-05-07
2. Pulse-width analysis for neutron capture cross-section measurement using an NaI(Tl) detector;Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment;2014-11
3. A facility for measurements of (n,γ) cross-sections of a nucleus in the range 0.008≤En<20MeV;Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment;2010-06
4. Neutron Cross Section Measurements;Handbook of Nuclear Engineering;2010
5. Calculation and Analysis ofn+180,182,183,184,186,natW Reactions in theEn≤ 250 MeV Energy Range;Nuclear Science and Engineering;2007-09