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Showing 1 to 20 of 74 for “"neutronics"”.

  1. The "virtual density" theory of neutronics

    … Our solution is the "virtual density" theory of neutronics, which alters material density (isotropically or anisotropically) instead of explicitly changing geometry. While geometry is discretized, material densities occupy a continuous domain; this allows density changes to obviate the greatest …

    mit Repository record for The "virtual density" theory of neutronics (opens in a new tab)

  2. Neutronics analysis for cylindrical assembly using Green's functions

    When designing a reactor a preliminary design is done in order to obtain a rough estimate of various reactor properties. These properties include the neutron flux, criticality condition, or distribution of material in the assembly. It is possible to obtain an analytic solution for the neutron flux …

    uiuc Repository record for Neutronics analysis for cylindrical assembly using Green's functions (opens in a new tab)

  3. Space-Time Neutronics Applied to Fast Reactor Disassembly Calculations

    Made available in DSpace on 2014-12-14T06:25:58Z (GMT). No. of bitstreams: 1 7616216.pdf: 4296525 bytes, checksum: 2ee10e2ad4bf78a3664513e4ac49ad7f (MD5) Previous issue date: 1976

    uiuc Repository record for Space-Time Neutronics Applied to Fast Reactor Disassembly Calculations (opens in a new tab)

  4. Computational neutronics analysis of TRIGA reactors during power pulsing

    Training, Research, Isotopes, General Atomics (TRIGA) reactors have the unique capability of generating high neutron flux environments with the removal of a transient control rod, creating conditions observed in fast fission reactors. Recently, several TRIGA reactors have had issues with the …

    mit Repository record for Computational neutronics analysis of TRIGA reactors during power pulsing (opens in a new tab)

  5. Tritium-Tritium Fusion: Neutronics, Photonics and Power Plant System Analysis

    Made available in DSpace on 2017-07-06T18:58:51Z (GMT). No. of bitstreams: 3 Smith_Jonathan_E_MS.pdf: 42379371 bytes, checksum: 742f8f04019a0129f5c016f299f537ff (MD5) Smith_Jonathan_E_MS_ABS.pdf: 523444 bytes, checksum: 7e444c8c85947bb702f5d0881b9ab5ae (MD5) license.txt: 4813 bytes, checksum: …

    uiuc Repository record for Tritium-Tritium Fusion: Neutronics, Photonics and Power Plant System Analysis (opens in a new tab)

  6. Tightly coupled neutronics and thermal-hydraulics using open-source software

    … The ITC method is verified using two 1.5-D (1-D neutronics and 2-D thermal-hydraulics) examples: a symmetric unit cell and an asymmetric unit cell. The mesh of the tightly integrated computation is 25 % and 12 % coarser than the loosely coupled one for the symmetric case and the asymmetric case, …

    uiuc Repository record for Tightly coupled neutronics and thermal-hydraulics using open-source software (opens in a new tab)

  7. Resonance region neutronics of unit cells in fast and thermal reactors.

    Thesis. 1977. Ph.D.--Massachusetts Institute of Technology. Dept. of Nuclear Engineering.

    mit Repository record for Resonance region neutronics of unit cells in fast and thermal reactors. (opens in a new tab)

  8. Moderator displacers for reducing coolant void reactivity in CANDU reactors: a neutronics scoping study.

    When the coolant is voided in a CANDU lattice, the net reactivity change is positive, due primarily to the fact that the coolant and moderator are separated and the coolant volume is much smaller than the moderator volume. The modest loss in moderation occurring when coolant is lost does not offset …

    uoit Repository record for Moderator displacers for reducing coolant void reactivity in CANDU reactors: a neutronics scoping study. (opens in a new tab)

  9. Economics of nuclear fuel cycles : option valuation and neutronics simulation of mixed oxide fuels

    In most studies aiming at the economic assessment of nuclear fuel cycles, a primary concern is to keep scenarios economically comparable. For Uranium Oxide (UOX) and Mixed Oxide (MOX) fuels, a traditional way to achieve this is to evaluate both fuels on the deterministic premise that the fuel will …

    mit Repository record for Economics of nuclear fuel cycles : option valuation and neutronics simulation of mixed oxide fuels (opens in a new tab)

  10. 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 …

    uoit Repository record for Study on specifics of thermalhydraulics and neutronics of pressure-channel supercritical water-cooled reactors (SCWRs) (opens in a new tab)

  11. Neutronics and thermal-hydraulics analysis of transatomic power molten salt reactor (TAP MSR) core under load following operations

    This work analyzed the neutronics and thermal-hydraulics behavior of the Transatomic Power Molten Salt Reactor (TAP MSR) core under load-following operations using a Monte Carlo code, Serpent 2, as well as a UIUC-developed MOOSE-based code, Moltres. A simulation method was developed to determine …

    uiuc Repository record for Neutronics and thermal-hydraulics analysis of transatomic power molten salt reactor (TAP MSR) core under load following operations (opens in a new tab)

  12. CAD-Based Geometry Representations for Monte Carlo Fusion Neutronics Methods and CSG vs. DAGMC Performance Tradeoffs in OpenMC

    … transport methods have become standard in fusion neutronics due to their ability to handle energy and angular variables continuously. However, manual modeling of complex fusion geometries with traditional constructive solid geometry (CSG) methods remains labor-intensive, prompting the integration …

    mit Repository record for CAD-Based Geometry Representations for Monte Carlo Fusion Neutronics Methods and CSG vs. DAGMC Performance Tradeoffs in OpenMC (opens in a new tab)

  13. Parallel, asynchronous ray-tracing for scalable, 3D, full-core method of characteristics neutron transport on unstructured mesh

    … realized. Predictive reactor physics needs both neutronics calculations and full-core, 3D coupled multiphysics simulations (e.g., neutronics, fuel performance, fluid mechanics, structural mechanics). Therefore, new reactor physics tools should harness supercomputers to enable full-core reactor …

    mit Repository record for Parallel, asynchronous ray-tracing for scalable, 3D, full-core method of characteristics neutron transport on unstructured mesh (opens in a new tab)

  14. Stability analysis of a natural circulation lead-cooled fast reactor

    … higher azimuthal modes is used to model the neutronics part of the system. A reduced order model is used in this work for the thermal-hydraulics. Consistent with the number of heat exchangers (HXs), the reactor core is divided into four equal quadrants. Each quadrant has its corresponding …

    uiuc Repository record for Stability analysis of a natural circulation lead-cooled fast reactor (opens in a new tab)

  15. Multi-physics and technical analysis of high-temperature gas-cooled reactors for hydrogen production

    … down the analysis into three parts: stand-alone neutronics, stand-alone thermal-fluids, and coupled neutronics/thermal-fluids. Regarding stand-alone neutronics, several analyses compare the results calculated by Moltres and Serpent on an MHTGR-350 model. The first analysis studies the energy …

    uiuc Repository record for Multi-physics and technical analysis of high-temperature gas-cooled reactors for hydrogen production (opens in a new tab)

  16. Efficient Multiphysics Coupling for Fast Burst Reactors in Slab Geometry

    … coupled multiphysics algorithm of diffusion neutronics and linear. An implicit-explicit (IMEX) algorithm was used to follow the dynamical time-scale of the problem. However, as noted by him and his co-authors, the diffusion model does not adequately represent the neutronics of the system due …

    unm Repository record for Efficient Multiphysics Coupling for Fast Burst Reactors in Slab Geometry (opens in a new tab)

  17. 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 …

    nwu-za Repository record for Developing a fresh core neutronic model at 300K for a VVER-1000 reactor type using MCNP6 (opens in a new tab)

  18. The effect of ICRF and LHCD waveguide and launcher location on tritium breeding ratio and radiation damage in fusion reactors

    … will also affect important aspects of the neutronics of the tokamak fusion design, i.e. how the 14.1 MeV neutrons born out of the deuterium-tritium (D-T) fusion reaction interact with the surrounding blanket and structures. The goal of this thesis is to assess the dependence of RF launcher …

    mit Repository record for The effect of ICRF and LHCD waveguide and launcher location on tritium breeding ratio and radiation damage in fusion reactors (opens in a new tab)

  19. Physics-Based 3D Multi-Directional Reloading Algorithm for Deep Burn HTR Prismatic Block Systems

    … operation constraints utilizing a high fidelity neutronics model developed for this dissertation. The high fidelity automated neutronics model allows design flexibility and metric tracking in spatial and temporal dimensions. Reduction of TRUs in DB-VHTRs utilizing full vectors of TRUs from light …

    tdl Repository record for Physics-Based 3D Multi-Directional Reloading Algorithm for Deep Burn HTR Prismatic Block Systems (opens in a new tab)

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