Search Constraints

Start Over
Filtering by: Subject Nuclear reactors -- Computer programs Remove constraint Subject: Nuclear reactors -- Computer programs

Search Results

  • A computer control algorithm for a nuclear reactor support system

    Creator:
    Kosorok, John Roger
    Abstract:
    The High Temperature Lattice Test Reactor (HTLTR) at Richland, Washington, operates at temperatures up to 1000°C. Its low nuclear power requires a 384 kilowatt electrical heating system, that is divided into four circuits, to attain the high temperatures in the ten-foot cube of moderating graphite. This thesis describes the design...
    Resource Type:
    Dissertation
    Full Text:
    A computer control algorithm for a nuclear reactor support

  • Computer routines for nuclear reactor after-heat research

    Creator:
    Lewallen, Marvin Adam
    Resource Type:
    Masters Thesis
    Full Text:
    department) (Date) Title: COMPUTER ROUTINES FOR NUCLEAR REACTOR. AFTER-HEAT RESEARCH Abstract approved

  • COBRA-OSU : a fast running computer code for coupled kinetic-thermal hydraulic analysis of nuclear reactor cores

    Creator:
    Kaya, Sadi
    Abstract:
    COBRA-OSU computer code is a fast running computer code for coupled Kinetic-Thermal Hydraulic Analysis of nuclear reactor cores. This code which is based on the standard version of COBRA-IV[superscript (3)] has two major improved features. First, the COBRA-OSU computer code uses Gaussian elimination method instead of Gauss-Siedel iteration for crossflow...
    Resource Type:
    Masters Thesis
    Full Text:
    Fast Running Computer Code for Coupled Kinetic-Thermal Hydraulic Analysis of Nuclear Reactor Cores

  • Development of an object-oriented expert system for PWR core reload

    Creator:
    Greek, Kevin J.
    Abstract:
    Reactor refueling is a computationally intensive problem solving process that requires automation since significant resources are expended upon the search for an optimal core loading. Without imposing some constraints upon the configurations investigated, an extremely large number of prototype loadings may be generated without discovery of an improved loading. As...
    Resource Type:
    Dissertation
    Full Text:
    Nuclear Engineering presented on December 12, 1989. Title: Development of an Object-Oriented Expert

  • PERT-IV, a two-dimensional perturbation theory code for fast reactors

    Creator:
    Hardie, Ralph Wayne
    Abstract:
    A two-dimensional perturbation theory computer code, PERT-IV, has been developed that will calculate reactivity coefficients, the delayed neutron fraction, and the neutron generation time. The program uses the output flux and adjoint flux from either a diffusion theory or transport theory program. A discussion and derivation of the perturbation equation...
    Resource Type:
    Masters Thesis
    Full Text:
    nuclear reactor. This is necessary, for example, in the operational calculations of a reactor such as

  • A comparative study of nodal course-mesh methods for pressurized water reactors

    Creator:
    Bukar, Kyari Abba
    Abstract:
    Several computer codes based on one and two-group diffusion theory models were developed for SHUFFLE. The programs were developed to calculate power distributions in a two-dimensional quarter core geometry of a pressurized power reactor. The various coarse-mesh numerical computations for the power calculations yield the following: the Borresen's scheme applied...
    Resource Type:
    Masters Thesis
    Full Text:
    nuclear reactor core analysis are (1) calculating flux distribution and (2) determining criticality

  • Quantified PIRT and uncertainty quantification for computer code validation

    Creator:
    Luo, Hu
    Abstract:
    This study is intended to investigate and propose a systematic method for uncertainty quantification for the computer code validation application. Uncertainty quantification has gained more and more attentions in recent years. U.S. Nuclear Regulatory Commission (NRC) requires the use of realistic best estimate (BE) computer code to follow the rigorous...
    Resource Type:
    Dissertation
    Full Text:
    by the nuclear industry as the standard approach to employ BE computer codes for reactor safety

  • Study of interfacial condensation in a nuclear reactor core makeup tank

    Creator:
    Ma, Chang Chun
    Abstract:
    Steam interfacial condensation in a core makeup tank was simulated using the code RELAP5/MOD3 version 8.0 to predict the violent pressure oscillation phenomena in a core makeup tank. Six base cases were carried out to study the effects of back pressure and of vacuum conditions produced in the core makeup...
    Resource Type:
    Masters Thesis
    Full Text:
    Study of interfacial condensation in a nuclear reactor

  • Modeling and analysis of a heat transport transient test facility for space nuclear systems

    Creator:
    Wheeler, Adam
    Abstract:
    The purpose of this thesis is to design a robust test facility for a small space nuclear power system and model its physical behavior under different scenarios. The test facility will be used to simulate a 1-10kWe nuclear reactor, its electrical generation, and heat removal capabilities. This simulator will be...
    Resource Type:
    Masters Thesis
    Full Text:
    different scenarios. The test facility will be used to simulate a 1-10kWe nuclear reactor, its electrical

  • Modeling the Oregon State University TRIGA Reactor Using the Attila Three-Dimensional Deterministic Transport Code

    Creator:
    Keller, S. Todd
    Abstract:
    Attila is a state-of-the-art radiation transport based code that is efficient, accurate and straightforward to use. Geometric information is input to the code as CAD drawings. Material property information is input as a cross section library. The user has full control over standard transport options and output reports. In phase...
    Resource Type:
    Masters Thesis
    Full Text:
    In order to design, license and operate a nuclear reactor in a safe and efficient manner, the