Erscheinungsjahr
Medientyp
Datenquelle
Format
Lizenz
Sprache
Synonyme wurden verwendet für: Nuclear Power • Nuclear Power Plants • Plants
Suche ohne Synonyme: keywords:(Nuclear Power Plants)
Verwendete Synonyme:
- atomenergie
- atomic energy
- atomkernenergie
- atomkraft
- kernenergie
- kernkraft
- nuclear energy
- nukleare energie
- nuklearenergie
Verwendete Synonyme:
- atomkraftwerk
- atomkraftwerke
- kernkraftwerk
- kernkraftwerke
Verwendete Synonyme:
- flora
- landpflanzen
- pflanze
- pflanzen
- pflanzendecke
- pflanzenkleid
- vegetation
- vegetationsdecke
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Venus- a Two-Dimensional Coupled Neutronics-Hydrodynamics Computer Program for Fast-Reactor Power Excursions
NTIS | 1970|Schlagwörter: Reactor Engineering & Nuclear Power Plants -
Design, Research, and Development Implications of Metal Swelling in Fast Reactors
NTIS | 1971|Schlagwörter: Reactor Engineering & Nuclear Power Plants -
Multidomain Multiphase Fluid Mechanics
NTIS | 1976|Schlagwörter: Reactor Engineering & Nuclear Power Plants -
Development of a Computer Program for Reactor Core Thermal Hydraulics: Finite Differencing in a 3-D Staggered Mesh Suitable for Irregular Boundary Applications
NTIS | 1976|Schlagwörter: Reactor Engineering & Nuclear Power Plants -
Bubble Dynamics in a Superheated Liquid
NTIS | 1977|Schlagwörter: Reactor Engineering & Nuclear Power Plants -
Numerical Results Obtained from the Three Dimensional Transient Single Phase Version of the COMMIX Computer Code
NTIS | 1977|Schlagwörter: Reactor Engineering & Nuclear Power Plants -
Numerical Results Obtained from the Three Dimensional Transient Single Phase Version of the COMMIX Computer Code
NTIS | 1977|Schlagwörter: Reactor Engineering & Nuclear Power Plants -
Summary of Methods Used in Rod-Bundle Thermal-Hydraulic Analyses
NTIS | 1978|Schlagwörter: Reactor Engineering & Nuclear Power Plants -
New Approach for Rod-Bundle Thermal-Hydraulic Analysis
NTIS | 1978|Schlagwörter: Reactor Engineering & Nuclear Power Plants -
Numerical Results for a Hexagonal Fuel Assembly with a Planar Blockage Using the COMMIX-1A Computer Code
NTIS | 1978|Schlagwörter: Reactor Engineering & Nuclear Power Plants, Nuclear fuel assemblies -
Numerical Results for a Hexagonal Fuel Assembly with a Planar Blockage Using the COMMIX-1A Computer Code
NTIS | 1978|Schlagwörter: Reactor Engineering & Nuclear Power Plants -
COMMIX-1: A Three-Dimensional Transient Single-Phase Component Computer Program for Thermal-Hydraulic Analysis
NTIS | 1978|Schlagwörter: Reactor Engineering & Nuclear Power Plants -
Pretest Prediction of the W-1 SLSF Experiment Using the COMMIX-1A Computer Code
NTIS | 1979|Schlagwörter: Reactor Engineering & Nuclear Power Plants, Nuclear fuel assemblies, Nuclear reactor accidents -
Some Numerical Results with the COMMIX-2 Computer Code
NTIS | 1979|Schlagwörter: Reactor Engineering & Nuclear Power Plants, Nuclear reactor safety, Nuclear reactor accidents -
Rod-Bundle Thermal-Hydraulic Analysis Using Boundary-Fitted Coordinate System
NTIS | 1979|Schlagwörter: Reactor Engineering & Nuclear Power Plants -
An Overview of Rod-Bundle Thermal-Hydraulic Analysis
NTIS | 1980|Schlagwörter: Reactor Engineering & Nuclear Power Plants, Nuclear fuel assemblies -
Computational Results for a 7-Pin Hexagonal Fuel Assembly during a Flow Rundown Transient Using the COMMIX-1A Computer Code
NTIS | 1980|Schlagwörter: Nuclear reactor safety, Reactor Engineering & Nuclear Power Plants, Nuclear fuel assemblies -
Simulation of a Thermohydraulic Transient in a Pipe Using the COMMIX-1A Computer Code
NTIS | 1980|Schlagwörter: Reactor Engineering & Nuclear Power Plants, Nuclear reactor safety -
Foundations of Rational Multiphase Flow and Heat-Transfer Field Equations
NTIS | 1981|Schlagwörter: Reactor Engineering & Nuclear Power Plants, Nuclear power plants -
BODYFIT-1FE: A Computer Code for Three-dimensional Steady-state/Transient Single-phase Rod-bundle Thermal-Hydraulic Analysis
NTIS | 1981|Schlagwörter: Reactor Engineering & Nuclear Power Plants, Nuclear fuel rods, Nuclear reactor safety, Nuclear fuel claddings -
Simulation of Steady-State and Transient Sodium Boiling Experiments in a Seven-Pin Bundle under Flow Rundown Conditions by Using BODYFIT-1FE Code
NTIS | 1981|Schlagwörter: Nuclear fuel pins, Reactor Engineering & Nuclear Power Plants, Nuclear fuel rods -
Three-Dimensional Simulation of Diversion Cross-Flow Between Two Parallel Channels Connected by a Narrow Lateral Slot Using the COMMIX-1A Computer Program
NTIS | 1981|Schlagwörter: Reactor Engineering & Nuclear Power Plants -
Numerical Simulation of Combined Natural and Forced Convection During Thermal-Hydraulic Transients
NTIS | 1981|Schlagwörter: Reactor Engineering & Nuclear Power Plants -
COMMIX-2: A Steady/Unsteady Single-Phase/Two-Phase Three-Dimensional Computer Program for Thermal-Hydraulic Analysis of Reactor Components
NTIS | 1981|Schlagwörter: Reactor Engineering & Nuclear Power Plants, Nuclear reactor safety, Nuclear reactor coolants, Nuclear reactor accidents -
EBR-II In-Vessel Natural-Circulation Analysis
NTIS | 1982|Schlagwörter: Nuclear research and test reactors, Reactor Engineering & Nuclear Power Plants -
Local Volume-Averaged Transport Equations for Multiphase Flow in Regions Containing Distributed Solid Structures
NTIS | 1982|Schlagwörter: Reactor Engineering & Nuclear Power Plants, Nuclear reactors -
Multidimensional Numerical Modeling of Heat Exchangers
NTIS | 1982|Schlagwörter: Reactor Engineering & Nuclear Power Plants -
Simulation of Thermal-Transient-Induced-Pipe-Flow Stratification Using COMMIX-2
NTIS | 1982|Schlagwörter: Reactor Engineering & Nuclear Power Plants -
COMMIX-1A Three-Dimensional In-Vessel Simulation of the FFTF Transient Thermal Hydraulics
NTIS | 1982|Schlagwörter: Nuclear research and test reactors, Reactor Engineering & Nuclear Power Plants -
COMMIX-1A Three-Dimensional In-Vessel Simulation of the FFTF Thermal Hydraulics
NTIS | 1982|Schlagwörter: Reactor Engineering & Nuclear Power Plants -
3-D Solution of Flow in an Infinite Square Array of Circular Tubes by Using Boundary-Fitted Coordinate System
NTIS | 1982|Schlagwörter: Reactor Engineering & Nuclear Power Plants -
Thermal-Hydraulic Posttest Analysis for the ANL/MCTF 360 exp 0 Model Heat-Exchanger Water Test under Mixed Convection (LMFBR)
NTIS | 1982|Schlagwörter: Reactor Engineering & Nuclear Power Plants -
Recent Advances in the COMMIX and BODYFIT Codes
NTIS | 1983|Schlagwörter: Reactor Engineering & Nuclear Power Plants, Power reactors -
COMMIX-1A: A Three-Dimensional Transient Single-Phase Computer Program for Thermal Hydraulic Analysis of Single and Multicomponent Systems. Volume 1. Users Manual
NTIS | 1983|Schlagwörter: Nuclear reactors, Reactor Engineering & Nuclear Power Plants, Nuclear reactor accidents -
COMMIX-1A: A Three-Dimensional Transient Single-Phase Computer Program for Thermal Hydraulic Analysis of Single and Multicomponent Systems. Volume 2. Assessment and Verification
NTIS | 1983|Schlagwörter: Nuclear reactors, Reactor Engineering & Nuclear Power Plants, Nuclear reactor accidents -
Critical Heat Flux Predictions Based on the BODYFIT-2PE Computer Code and Columbia University CHF Correlation (PWR;BWR)
NTIS | 1983|Schlagwörter: Reactor Engineering & Nuclear Power Plants -
CHF Prediction of GE 3 X 3 Rod Bundle Based on BODYFIT-2PE (BWR)
NTIS | 1983|Schlagwörter: Reactor Engineering & Nuclear Power Plants -
In-Vessel Thermal-Hydraulic Analysis
NTIS | 1983|Schlagwörter: Reactor Engineering & Nuclear Power Plants -
Turbulence Modeling of Thermal and Fluid Mixing in PWR'S During High-Pressure Coolant Injection Using COMMIX-1B
NTIS | 1983|Schlagwörter: Reactor Engineering & Nuclear Power Plants -
COMMIX-1A Analysis of Fluid and Thermal Mixing in a Model Cold Leg and Downcomer of a PWR
NTIS | 1983|Schlagwörter: Reactor Engineering & Nuclear Power Plants -
Three-Dimensional Analysis of Thermal and Fluid Mixing in Cold Leg and Downcomer of PWR Geometries
NTIS | 1983|Schlagwörter: Reactor Engineering & Nuclear Power Plants -
New Implicit Numerical Solution Scheme in the COMMIX-1A Computer Program
NTIS | 1984|Schlagwörter: Reactor Engineering & Nuclear Power Plants, Nuclear reactors -
Comparison of BIASI and Columbia CHF Correlations Using BODYFIT-2PE
NTIS | 1984|Schlagwörter: Reactor Engineering & Nuclear Power Plants -
Time- and Volume-Averaged Conservation Equations for Multiphase Flow. Part 1. System without Internal Solid Structures
NTIS | 1984|Schlagwörter: Reactor Engineering & Nuclear Power Plants -
COMMIX-1A Analysis of Fluid and Thermal Mixing in a Model Cold Leg and Downcomer of a PWR
NTIS | 1984|Schlagwörter: Selected Studies In Nuclear Technology, Reactor Engineering & Nuclear Power Plants -
Analysis of Oconee Unit 1 Downcomer and Lower Plenum Thermal-Mixing Tests Using COMMIX-1A. Final Report
NTIS | 1984|Schlagwörter: Reactor Engineering & Nuclear Power Plants -
Turbulence Modeling in the Commix Computer Code
NTIS | 1984|Schlagwörter: Reactor Engineering & Nuclear Power Plants -
Assessment of Biasi and Columbia University CHF Correlations with GE 3X3 Rod Bundle Experiment
NTIS | 1984|Schlagwörter: Reactor Engineering & Nuclear Power Plants, Selected Studies In Nuclear Technology -
Numerical Simulation of Heat Exchanger
NTIS | 1985|Schlagwörter: Reactor Engineering & Nuclear Power Plants, Selected Studies In Nuclear Technology -
BODYFIT-2PE-HEM: LWR Core Thermal-Hydraulic Code Using Boundary-Fitted Coordinates and Two-Phase Homogeneous Equilibrium Model. Volume 2: User's Manual
NTIS | 1985|Schlagwörter: Reactor Engineering & Nuclear Power Plants
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