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Showing 1 to 20 of 73 for “"Neutronic"”.
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Neutronic evaluation of GCFR core diluents and reflectors
… are superior in all respects, considering only neutronic performance, the following appear worthy of further investgation: Metallic fuel diluents or matrices (eg. CERMET or METMET): Zr, Ti, V, Ba2Pb; High temperature fuel diluents or matrices (eg, CERMET, CERCER): SiC, BaS Cladding: Fe alloys …
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Evaluation of the Relative Neutronic Risk of Alternative Fusion Fuels
The radiological risk profiles of a variety of fusion fuels were assessed, to aid understanding of the influence of fuel choice on the safety and cost of future commercial fusion power plants. Shielding thickness and activation dose rates were modeled for five fusion fuels consisting of …
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Neutronic Analysis of Horizontal-Compact High Temperature Gas-cooled Reactor
… goal of 2 years cycle length. Overall, the neutronics assessment of HC-HTGR core met the initial safety and design requirements.
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Application of nodal equivalence theory to the neutronic analysis of PWRS
Thesis (Ph.D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1982.
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Neutronic design of a fission converter-based ephithermal beam for neutron capture theory
Thesis (Nucl. E.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1996.
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Developing a fresh core neutronic model at 300K for a VVER-1000 reactor type using MCNP6
A steady state neutronics model for a fresh core Voda Voda Energo Reaktor (VVER)-1000 reactor type is developed using an internationally recognised code, Monte Carlo N-Particle, version 6 (MCNP6). This research study is based on a VVER type of pressurized water reactor (PWR), which is of Russian …
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Neutronic Characteristics of Using Zirconium Diboride and Gadolinium in a Westinghouse 17 X 17 Fuel Assembly
<p>There has been a trend by the utilities to extend the operating cycle of their power reactors in the production of electricity. In order to achieve this, variations in fuel composition, fuel pin arrangement, and burnable absorber distribution have been proposed. Burnable absorbers are materials …
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Neutronic analysis of selected fuel assemblies of the MIT BEAVRS benchmark using HEADE collision probability code
Neutronic models for fresh core fuel assemblies of the MIT BEAVRS benchmark are developed using the HEADE collision probability code which is a module of the OSCAR-4 code used for research reactor calculations. This research study is based on the MIT BEAVRS benchmark, which is a specification of a …
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Neutronic feasibility assessment of full-core applications of evolutionary mixed-oxide fuels in pressurized water reactors
Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1998.
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LEU+ Fuel Cycle Investigation of the BWRX-300 Design Using Neutronic and Two-Phase Thermal Hydraulic Analyses
… of modeling tools available to represent neutronic and thermal hydraulic conditions respectively. When performing coupled calculations between these two codes, large computational cost is seen, especially in neutronic burnup calculations in three dimensions. The main challenge when …
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The Neutronic Design and Performance of the Indiana University Cyclotron Facility (IUCF) Low Energy Neutron Source (LENS)
… neutron intensity from the system. The TMR and neutronic modeling have been well characterized and the source design is flexible, such that it is possible for LENS to serve as an effective test bed for future work in neutronic development. Suggestions for improvements to the design that would …
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Sensitivity studies of the neutronic design of a fission converter-based ephithermal beam for boron neutron capture therapy
Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1997.
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Neutronic characterization of a Molybdenum-99-producing CANDU fuel bundle and implications for reactivity-device worth and refuelling strategies
… of MPB needs to be supplemented by additional neutronic evaluations. This study therefore evaluates the neutronic characteristics of the MPB relevant to transient behaviour and refuelling, and compares the results to those of the SCB. This includes derivation of reactivity coefficients, …
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Neutronic-Thermal Simulation of Micro Reactor Designs for the Purpose of Analyzing the Impact of Thermal Expansion and Hydrogen Migration in Metal Hydride Moderator
… smaller core dimensions to perform steady state neutronic-thermal coupled simulation with the inclusion of an additional physics system. This work accomplishes this, by adding thermal expansion and zirconium hydride-based hydrogen diffusion to the neutronic-thermal simulation of multiple heat …
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Neutronic Performance and Thermal Hydraulic Analysis of the MIT Reactor Fission Converter Experimental Facility Using High-Density U-10Mo Low-Enriched Uranium Fuel Elements
… fuel as part of the MITR LEU conversion project. Neutronics and thermal hydraulics analysis of the renovated facility have been performed using the codes MCNP5 and STAT7, respectively. This analysis quantified the FC’s k_eff, power distribution, multi-group neutron flux, and conditions which cause …
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Design Space Exploration for Salt Cooled Reactor Systems
… concept. It explored the thermal-hydraulic and neutronic design space of a number of AGR-like FHR assembly options covering combinations of three fuel geometries: 1) solid pin, 2) annular pin and 3) plate type fuel; three coolant options: 1) FLiBe 2) FLiNaK and 3) NaF-ZrF4, and three fuel forms: …
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Nuclear reactor multi-physics simulations with coupled MCNP5 and STAR-CCM+
… by water, consists of 9,984 CFD cells and 7,489 neutronic cells. The second model is a 3 x 3 PWR lattice model, consisting of 89,856 CFD cells and 67,401 neutronic cells. Fission energy deposition (fission and prompt gamma heating) is tallied over all UO2 cells in the models using the F7:N tally …
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Stability analysis of natural circulation in BWRs at high pressure conditions
… Channel thermal-hydraulic stability, coupled neutronics region-wide out-of-phase stability and core-wide in-phase stability. Using frequency domain methods, the three types of DWO stability characteristics of the NCBWR and their sensitivity to the operating parameters and design features have …
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Study on specifics of thermalhydraulics and neutronics of pressure-channel supercritical water-cooled reactors (SCWRs)
… study on specifics of the thermalhydraulics and neutronics of a pressure-tube SCWR based on an understanding of the supercritical water phenomena and their impacts on reactor design and operation. This thesis investigates the impact of several thermalhydraulic modeling parameters on fuel and …
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Conceptual design of a breed & burn molten salt reactor
… in design of the BBMSR fuel is balancing the neutronic requirement of large fuel volume fraction for B$\&$B mode with the thermal-hydraulic requirements for safe and economically competitive reactor operation. Natural convection of liquid fuel within the tubes aids heat transfer to the …
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