7,362 Matching Results

Search Results

Advanced search parameters have been applied.

in subjects: "Computer Codes"

open access

Parametric HECTR calculations of hydrogen transport and combustion at N Reactor

This report describes a limited number of parametric calculations of hydrogen transport and combustion in the N Reactor confinement for selected accident sequences. The calculations are performed using the HECTR computer code, which is a lumped-parameter code developed specifically for evaluating hydrogen behavior in reactor containments. A number of parameters are evaluated in this study, including hydrogen source rate, spray effects, and source location. The calculations indicate that mixing … more

Date: June 1, 1987

Creator: Payne, A. C., Jr. & Camp, A. L.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

FLOWTRAN-TF v1. 2 source code

The FLOWTRAN-TF code development effort was initiated in early 1989 as a code to monitor production reactor cooling systems at the Savannah River Plant. This report is a documentation of the various codes that make up FLOWTRAN-TF.

Date: February 1, 1993

Creator: Aleman, S. E.; Cooper, R. E.; Flach, G. P.; Hamm, L. L.; Lee, S. & Smith, F. G., III

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Geoecology: a county-level environmental data base for the conterminous United States

The Geoecology Data Base represents a unique compilation of computerized environmental data for research and development needs. Environmental assessment and planning for energy development require rapid access to data at appropriate spatial and temporal scales. In the Environmental Sciences Division (ESD) at Oak Ridge National Laboratory (ORNL), we have developed an integrated data base of diverse environmental resource information from extant sources. Data are stored at the county level of res… more

Date: September 1, 1980

Creator: Olson, R. J.; Emerson, C. J. & Nungesser, M. K.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Rapid seepage of contaminants through the highwall of a uranium mill tailings pit. [MIGRAT]

A computer code (MIGRAT) is used to quantify the migration of moisture and multiple retarded contaminants in the unsaturated zone and assess the impact of open mine disposal of uranium mill tailings. The model is applied to a generic uranium mill tailings. The model is applied to a generic uranium mill tailings pit constructed with a clay-lined bottom and steep unlined sidewalls. The migration of a two contaminant system is modeled assuming that neither contaminant decays and only one contamina… more

Date: January 1, 1984

Creator: Pin, F.G.; Witten, A.J.; Sharp, R.D. & Long, E.C.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

RESFEN: A residential fenestration performance design tool

This paper describes the development of a prototype PC-based computer program called RESFEN. The program calculates the heating and cooling energy performance and costs of residential fenestration systems. Regression analysis of a data base of DOE-2 building energy simulations of single- and two-story residential buildings was used to develop algrbraic expressions that form the basis of the calculation procedure. The user can vary geographic location, electricity and gas cost, infiltration and … more

Date: August 1, 1991

Creator: Sullivan, R.; Chin, B.; Arasteh, D. & Selkowitz, S.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Bounding burnout risk power limits for the K-14 cycle

This document discusses burnout risk (BOR) power limits which are designed to protect the reactor from a significant release of fission products, due to critical heat flux (CHF) burnout of fuel and target assemblies. At expected operating power levels for the reactor restart, approximately 50% of historical full power, the risk of CHF and attendant burnout is negligible. Flow instability power limits will restrict reactor operation, and flow instability will always occur before CHF. BOR power l… more

Date: October 1, 1990

Creator: Shadday, M.A. Jr.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Scaling Study for SP-100 Reactor Technology

In this study, we explored several ways of extending SP-100 reactor technology to higher power levels. One approach was to use the reference SP-100 pin design and increase the fuel pin length and the number of fuel pins as needed to provide higher capability. The impact on scaling of a modified and advanced SP-100 reactor technology was also explored. Finally, the effect of using alternative power conversion subsystems, with SP-100 reactor technology was investigated. One of the principal conce… more

Date: January 1, 1989

Creator: Marshall, A.C.; McKissock, B. & National Aeronautics and Space Administration

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Seismic Safety Margins Research Program: Phase II program plan (FY 83-FY 84)

The Seismic Safety Margins Research Program (SSMRP) is an NRC-funded, multiyear program conducted by Lawrence Livermore National Laboratory (LLNL). Its goal is to develop a complete, fully coupled analysis procedure (including methods and computer codes) for estimating the risk of an earthquake-caused radioactive release from a commercial nuclear power plant. The analysis procedure is based upon a state-of-the-art evaluation of the current seismic analysis and design process and explicitly incl… more

Date: August 2, 1982

Creator: Bohn, M. P.; Bernreuter, D. L.; Cover, L. E.; Johnson, J. J.; Shieh, L. C.; Shukla, S. N. et al.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Final report on Development of a model and computer code to describe solar grade silicon production processes

Models and computer codes which may be used to describe flow reactors in which high purity, solar grade silicon is produced via reduction of gaseous silicon halides are described. A prominent example of the type of process which may be studied using the codes developed in this program is the SiCl/sub 4//Na reactor currently being developed by the Westinghouse Electric Corp. During this program two large computer codes were developed. The first is the CHEMPART code, an axisymmetric, marching cod… more

Date: December 1, 1979

Creator: Gould, R K & Srivastava, R

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Radwaste inventories and projections: an overview. [Integrated Data Base]

The Integrated Data Base program was set up to provide fully integrated and reconciled inventories, characteristics, and projections for spent nuclear fuel and all categories of radioactive waste. Eight summary papers, six of which were presented at an ANS special session in Los Angeles in June 1982, are included in this report: data base needs and functions: national planning; integrated data base for spent fuel and radwaste: inventories; integrated data base projections; RAWSYM: radioactive w… more

Date: July 1, 1982

Creator: Notz, K.J. (ed.)

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Summary of thermal-hydraulic calculations for a pressurized water reactor

The results of two transients involving the loss of a steam generator in a single-pass, steam generator, pressurized water reactor have been analyzed using a state-of-the-art, thermal-hydraulic computer code. Computed results include the formation of a steam bubble in the core while the pressurizer is solid. Calculations show that continued injection of high pressure water would have stopped the scenario. These are similar to the happenings at Three Mile Island.

Date: May 1, 1980

Creator: Bolstad, J.W. & Haarman, R.A.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Trace Metal Speciation in Saline Waters Affected by Geothermal Brines. [GEOCHEM]

A description is given of the chemical equilibrium computer program GEOCHEM, which has been developed to calculate trace element speciation in soil, irrigation, drainage, or Salton Sea waters affected by geothermal brine. GEOCHEM is applied to irrigation water-brine mixtures and to Salton Sea water-brine mixtures in order to compute the chemical speciation of the elements Cd, Cu, Hg, Ni, Pb, and Zn, along with the oxyanions of As and B. The results suggest that the computer simulation can have … more

Date: November 1, 1977

Creator: Sposito, G. & Page, A. L.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

TRAC analysis and support of Oconee-1 PTS studies. [Pressurized thermal shock following overcooling transients]

This paper describes the overall pressurized thermal shock (PTS) program at Los Alamos with emphasis on TRAC-PF1 calculations of severe overcooling transients for the Oconee-1 pressurized water reactor (PWR). A summary of results for several calculations are presented for the Oconee-1 PWR along with detailed discussions of two of the most severe overcooling transients predicted (main steam-line break and turbine-bypass valve (TBV) failures). The calculations performed were plant specific in tha… more

Date: January 1, 1983

Creator: Ireland, J.R.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Depressurized core heatup accident scenarios in advanced modular high temperature gas cooled reactors

The decay heat removal by a passive air colling system from a modular high tempeature gas cooled reactor during depressurized core heatup accident scenarios was analyzed. The effects of several design and operating parameters on the peak fuel and vessel temperatures were established. The results indicate that fuel and vessel temperatures remain well below failure levels and that significant safety margins exist in the key variables of decay heat and core thermal conductivities.

Date: January 1, 1988

Creator: Kroeger, P. G.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Theoretical and numerical studies of constitutive relations for frictional granular flow

The purpose of this report is to propose a suitable constitutive relationship for the three dimensional frictional flow of a cohesionless granular material and to incorporate at least a qualitatively similar constitutive relationship in the computer program TEACH. TEACH is a hydrodynamic code developed by Dr. A.D. Gosman at Imperial College, London, for the simulation of incompressible two dimensional steady duct flows. Simulations performed for this report assumed that the material was flowing… more

Date: January 1, 1991

Creator: Gray, D.; Stiles, J.M. & Celik, I.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Impact of new K Area geotechnical parameters on K Reactor restart response spectra

This report provides a description of a study performed to evaluate the impact of recently obtained soils parameters on the 105-K Reactor using Soil-Structure Interaction (SSI) analysis. This study includes: the frequency check of the reactor building based on the fixed base analysis; the modification of the computer model to reflect actual building properties and building frequencies; The live load impact on seismic analysis; The comparison of soil spectrum at elev. {minus}50 ft with 60% of RG… more

Date: August 1, 1991

Creator: Amin, J. A.; Chen, R. C. & Mulliken, J. S.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

FLUOMEG: a planar finite difference mesh generator for fluid flow problems with parallel boundaries. [In FORTRAN IV]

A two- or three-dimensional finite difference mesh generator capable of discretizing subrectangular flow regions (planar coordinates) with arbitrarily shaped bottom contours (vertical dimension) was developed. This economical, interactive computer code, written in FORTRAN IV and employing DISSPLA software together with graphics terminal, generates first a planar rectangular grid of variable element density according to the geometry and local kinematic flow patterns of a given fluid flow problem… more

Date: May 1, 1980

Creator: Kleinstreuer, C. & Patterson, M.R.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Solar-thermal central-receiver research study. Interim report

A performance analysis and economic study has been completed of a cavity-type line central receiver and single-axis parabolic cylinder focusing heliostat array for generation of steam for electrical power. A solar thermal power plant was sized to produce 100 MWe at 2:00 p.m. of winter solstice. The system concept is presented. Using the cavity once-through receiver with boiler tubes having an absorptivity of 0.9 and an emissivity of 0.7, it was calculated that total busbar cost in 1976 dollars … more

Date: February 1, 1977

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Modeling requirements for full-scope reactor simulators of fission-product transport during severe accidents

This paper describes in the needs and requirements to properly and efficiently model fission product transport on full scope reactor simulators. Current LWR simulators can be easily adapted to model severe accident phenomena and the transport of radionuclides. Once adapted these simulators can be used as a training tool during operator training exercises for training on severe accident guidelines, for training on containment venting procedures, or as training tool during site wide emergency tra… more

Date: January 1, 1990

Creator: Ellison, P.G.; Monson, P.R. (Westinghouse Savannah River Co., Aiken, SC (United States)) & Mitchell, H.A. (Concord Associates, Inc., Knoxville, TN (United States))

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

The importance of natural convection in in-vessel melt coolability

In the event of a core meltdown accident, one of the accident progression paths is fuel relocation to the lower reactor plenum. In the Heavy Water New Production Reactor (NPR-HWR) design, the reactor cavity is flooded with water. In such a design, decay heat removal to the water in the reactor cavity and thence to the containment may be adequate to keep the reactor vessel temperature below failure limits. If this is the case, the accident progression can be arrested by retaining a coolable cori… more

Date: January 1, 1992

Creator: Tzanos, C.P.; Tan, M.J. & Cho, D.H.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Validity of Hansen-Roach cross sections in low-enriched uranium systems

Within the nuclear criticality safety community, the Hansen-Roach 16 group cross section set has been the standard'' for use in k{sub eff} calculations over the past 30 years. Yet even with its widespread acceptance, there are still questions about its validity and adequacy, about the proper procedure for calculating the potential scattering cross section, {sigma}{sub p}, for uranium and plutonium, and about the concept of resonance self shielding and its impact on cross sections. This paper at… more

Date: January 1, 1991

Creator: Busch, R.D. (New Mexico Univ., Albuquerque, NM (United States)) & O'Dell, R.D. (Los Alamos National Lab., NM (United States))

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Theoretical studies of Cerro Prieto brines chemical equilibria

A chemical equilibrium model is used, implemented in a compact FORTRAN package called HITEQ, to investigate possible mineral deposition related to prereinjection treatment of Cerro Prieto brines for silica removal. Large saturation ratios of the treated brines with respect to several minerals are indicated by these computations. As a remedy, an inexpensive CO/sub 2/ removal scheme aimed at inhibiting carbonate mineral precipitation is proposed. This scheme is quantitatively discussed with the a… more

Date: February 1, 1980

Creator: Iglesias, E.R. & Weres, O.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Analysis of unscrammed events in PRISM. [Advanced Liquid Metal Reactors (ALMR)]

The PRISM reactor is presently under pre-application licensing review by the NRC, with Brookhaven National Laboratory (BNL) providing technical assistance. The purpose of this paper is to review the current PRISM design and describe the results from the SSC Code calculations performed at BNL, for a series of unscrammed accidents. 3 refs., 5 figs.

Date: January 1, 1990

Creator: Slovik, G.C. & Van Tuyle, G.J.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Analysis of natural convection in a waste glass melter

Laminar natural convection is a two-dimensional cavity with a line heat sink at the top boundary is investigated numerically. The fluid in the cavity is a high Prandtl number fluid with volumetric heat source. Parametric study is conducted to find the effect of variations in Rayleigh number, aspect ratio, sink location, and volumetric heat source on the flow and temperature field. 5 refs.

Date: January 1, 1989

Creator: Choi, Inn Gui.

Item Type: Article

Partner: UNT Libraries Government Documents Department