Sample records for THERMOHYDRAULIK (thermal hydraulics)
from WorldWideScience.org

Sample records 1 - 20 shown. Select sample records:



4

Tube Bundle Detailed Thermal Hydraulics on GR 16 Sodium Experiment

Berthoux, M.; Menant, B.; American Nuclear Society; Thermal Hydraulics Division
1992-01-01

German National Library of Science and Technology (GetInfo) (German)

15

The important role of thermal hydraulics in 50 years of nuclear power applications

Levy, S.; American Nuclear Society; French Section; American Nuclear Society; Thermal Hydraulics Division
1994-01-01

German National Library of Science and Technology (GetInfo) (German)

17

The effect of grid assembly mixing vanes on critical heat flux values and azimuthal location in fuel assemblies

De Crecy, F.; American Nuclear Society; French Section; American Nuclear Society; Thermal Hydraulics Division
1994-01-01

German National Library of Science and Technology (GetInfo) (German)

43

Model for Single-Droplet Thermal Fragmentation

Darbord, I.; Berthoud, G.; American Nuclear Society; Thermal Hydraulics Division
1997-01-01

German National Library of Science and Technology (GetInfo) (German)

45

Jet Mixer Pump Testing in Hanford Tank 241-SY-101

Stewart, C. W.; American Nuclear Society; Thermal Hydraulics Division
1994-01-01

German National Library of Science and Technology (GetInfo) (German)

48

Interfacial measurements in horizontal stratified flow patterns

Shi, J.; Kocamustafaogullari, G.; American Nuclear Society; French Section
1994-01-01

German National Library of Science and Technology (GetInfo) (German)

51

Improved Models for Predicting Heat Transfer from a Molten Pool

Rempe, J. L.; Allison, C.; American Nuclear Society; Thermal Hydraulics Division
1995-01-01

German National Library of Science and Technology (GetInfo) (German)

54

Hanford Gas Dispersion Analysis

Fujita, R. K.; Travis, J. R.; American Nuclear Society
1994-01-01

German National Library of Science and Technology (GetInfo) (German)

56

Fluid-structure coupling between a vibrating cylinder and a narrow annular flow

Perotin, L.; American Nuclear Society; French Section; American Nuclear Society; Thermal Hydraulics Division
1994-01-01

German National Library of Science and Technology (GetInfo) (German)

57

Flow instabilities in boiling channels of pressure-tube-type reactor

Mochizuki, H.; American Nuclear Society; French Section; American Nuclear Society; Thermal Hydraulics Division
1994-01-01

German National Library of Science and Technology (GetInfo) (German)

81
82

Assessment of the CATHARE ID pump model

Geffraye, G.; Bestion, D.; American Nuclear Society; French Section
1994-01-01

German National Library of Science and Technology (GetInfo) (German)

85

Analytic Benchmarks for BWR Stability Codes

Newman, N.; American Nuclear Society; Thermal Hydraulics Division
1993-01-01

German National Library of Science and Technology (GetInfo) (German)

87

Analysis of UPTF downcomer tests with the CATHARE multidimensional model

Dor, I.; American Nuclear Society; French Section; American Nuclear Society; Thermal Hydraulics Division
1994-01-01

German National Library of Science and Technology (GetInfo) (German)

91

A new approach to the MDNBR concept

De Crecy, F.; American Nuclear Society; French Section; American Nuclear Society; Thermal Hydraulics Division
1994-01-01

German National Library of Science and Technology (GetInfo) (German)