Uranium dioxide is the most common fuel used in commercial light water nuclear reactors. The fission of the fuel generates fission products (FPs) and minor actinides (MAs), which affects the thermo-physical properties...
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In order to properly design a mobile system to validate and verify the presence of special nuclear materials for non-proliferation and safeguards applications, accurate modeling of source materials is imperative. In t...
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ISBN:
(纸本)9781622763894
In order to properly design a mobile system to validate and verify the presence of special nuclear materials for non-proliferation and safeguards applications, accurate modeling of source materials is imperative. In this work, models were developed for use in design assessments based on an AL-R8 SNM standardized container specification to determine the radioactive signatures for both highly enriched uranium (HEU) and weapons plutonium (WGPu) special nuclear materials (SNM) housed in the containers. Intrinsic gamma boundary leakage currents were evaluated for this system, performed using 3D fixed-source deterministic SN photon transport (PENTRAN) as well as with stochastic Monte Carlo methods (MCNP5). Group-dependent leakage radiation terms were calculated at two "source box" interfaces within the models, one directly surrounding the SNM source, and one immediately surrounding the canister. Analysis showed good agreement between the two models for energy groups of interest, based on a 24 group gamma library established for HEU and WGPu gamma signatures of interest. Intrinsic and neutron induced gamma leakage was determined using Monte Carlo calculations, and the combined gamma signatures were then treated as a net gamma leakage to be used in subsequent photon transport calculations. Neutron leakage based on the BUGLE-96 47 group structure was determined using Monte Carlo calculations for the WGPu canisters. These results will be used to evaluate the source term from stored nuclear materials and augment our efforts to design a detection system to validate the presence of these materials for safeguards purposes.
Thin film gallium nitride (GaN) scintillators have been produced by MOCVD and made neutron-sensitive by applying an enriched lithium-6 fluoride ( 6LiF) conversion layer. The 6Li(n,α) reaction produces both alpha and ...
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The internationally circulated Pool Critical Assembly (PCA) Pressure Vessel Benchmark was analyzed using the PENTRAN Parallel Sn code system for the geometry, material, and source specifications as described in the PC...
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ISBN:
(纸本)9781622763894
The internationally circulated Pool Critical Assembly (PCA) Pressure Vessel Benchmark was analyzed using the PENTRAN Parallel Sn code system for the geometry, material, and source specifications as described in the PCA Benchmark documentation. This research focused on utilizing the BUGLE-96 cross section library and accompanying reaction rates, while examining both adaptive differencing on a coarse mesh basis as well as Directional Theta Weighted Sn differencing in order to compare the calculated PENTRAN results to measured data. The results show good comparison with the measured data as well as to the calculated results provided from TORT for the BUGLE-96 cross sections and reaction rates, which suggests PENTRAN is a viable and reliable code system for calculation of light water reactor neutron shielding and dosimetry calculations.
We have recently reported the significant reduction of radiation product diffusion by the incorporation of clay nanoparticles into dichromate gel (DCG) dosimeters. In this work, we investigate the influence of the nan...
We have recently reported the significant reduction of radiation product diffusion by the incorporation of clay nanoparticles into dichromate gel (DCG) dosimeters. In this work, we investigate the influence of the nanoclay addition and gelation on the MRI R1 (1/T1) image response of the dichromate dosimeter to the therapeutic carbon ion beam (12C6+ 290 MeV/u). The MRI R1 distribution in the aqueous dichromate solution well reproduces physical dose-depth distribution with a high linear-energy-transfer (LET) efficiency. The nanoclay DCG dosimeters, on the other hand, exhibit composition-dependent LET efficiency degradation, while a sharp Bragg peak can still be detected. These results indicate that the nanocomposite gel addition may induce change in the radiation-induced reaction mechanism.
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