نتایج جستجو برای: 233u fissile material
تعداد نتایج: 364460 فیلتر نتایج به سال:
Total photofission cross sections for 238U, 235U, 233U, 237Np, 232Th, and natPb have been measured simultaneously, using tagged photons in the energy range Egamma=0.17-3.84 GeV. This was the first experiment performed using the Photon Tagging Facility in Hall B at Jefferson Lab. Our results show that the photofission cross section for 238U relative to that for 237Np is about 80% over the entire...
Nuclear reactors have served as the antineutrino source for many fundamental physics experiments. The techniques developed by these experiments make it possible to use these very weakly interacting particles for a practical purpose. The large flux of antineutrinos that leaves a reactor carries information about two quantities of interest for safeguards: the reactor power and fissile inventory. ...
We have measured the neutron capture and fission cross section of 233U at the neutron time-of-flight facility n TOF at CERN in the energy range from 1 eV to 1 MeV with high accuracy by using a high performance 4π BaF2 Total Absorption Calorimeter (TAC) as a detection device. The method, based on the TAC energy response study, allowing to disentangle between γ’s originating from fission and capt...
The modification of the fuel composition in a molten salt reactor can cause the precipitation of fissile materials and thus the generation of fissile lumps moving within the system and introducing localized perturbations of multiplicativity. The problem of reactivity oscillations connected to this phenomenon in circulating fuel systems is addressed. The periodic behavior of such reactivity inse...
A strongly stratified water structure and a densely populated catchment make the Baltic Sea one of most polluted seas. Understanding its circulation pattern time scale is essential to predict dynamics hypoxia, eutrophication, pollutants. Anthropogenic 236U 233U have been demonstrated as excellent transient tracers in oceanic studies, but unclear input history inadequate long-term monitoring rec...
Valfells, Agust, "Preliminary design of a power generating system using a fissile gas " (1962). Retrospective Theses and Dissertations. 1962 Signature was redacted for privacy.
Abstract The IRMM-1027 Large-sized dried (LSD) spikes are certified reference materials applied to measure the uranium and plutonium content of dissolved fuel solutions using isotope dilution mass spectrometry. High quality starting metals produce a stock solution, which is dispensed into individual vials down. present mixtures typically 50 mg 20% enriched U 2 239 Pu as nitrates, conditioned in...
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