Correlation of Critical Heat Flux Data for Application to Boiling Water Reactor Conditions
Title | Correlation of Critical Heat Flux Data for Application to Boiling Water Reactor Conditions PDF eBook |
Author | |
Publisher | |
Pages | 138 |
Release | 1981 |
Genre | Boiling water reactors |
ISBN |
Correlation of critical heat flux data for application to boiling water reacrot conditions
Title | Correlation of critical heat flux data for application to boiling water reacrot conditions PDF eBook |
Author | J. E. Hench |
Publisher | |
Pages | 0 |
Release | 1981 |
Genre | |
ISBN |
Design Basis for Critical Heat Flux Condition in Boiling Water Reactors
Title | Design Basis for Critical Heat Flux Condition in Boiling Water Reactors PDF eBook |
Author | J. M. Healzer |
Publisher | |
Pages | 76 |
Release | 1966 |
Genre | Boiling water reactors |
ISBN |
An Empirical Correlation of Critical Boiling Heat Flux in Forced Flow Upward Through Uniformly Heated Tubes
Title | An Empirical Correlation of Critical Boiling Heat Flux in Forced Flow Upward Through Uniformly Heated Tubes PDF eBook |
Author | U. Von Glahn |
Publisher | |
Pages | 32 |
Release | 1962 |
Genre | Heat flux |
ISBN |
A Critical Heat Flux Correlation for Advanced Pressurized Light Water Reactor Application
Title | A Critical Heat Flux Correlation for Advanced Pressurized Light Water Reactor Application PDF eBook |
Author | Mario Dalle Donne |
Publisher | |
Pages | 90 |
Release | 1982 |
Genre | Pressurized water reactors |
ISBN |
REPP
Title | REPP PDF eBook |
Author | R. M. Hiatt |
Publisher | |
Pages | 196 |
Release | 1969 |
Genre | Boiling water reactors |
ISBN |
REPP, a digital computer method for designing pressure water and boiling water reactor cores within specified heat transfer and fuel centerline temperature limits is presented. The method incorporates the Westinghouse W-2 and W-3 empirical correlations and a theoretical hot channel model to predict burnout conditions in a rod bundle. Two geometries are considered; rods in a triangular array and rods in a square lattice. The heat transfer problem solved is a one-dimensional analysis. Pressure drop is considered for four types of fuel-pin spacers. Variable heat generation rate through the fuel-pin and sintering in low density fuels are also included.
A Study of Wet Steam as a Reactor Coolant
Title | A Study of Wet Steam as a Reactor Coolant PDF eBook |
Author | U.S. Atomic Energy Commission |
Publisher | |
Pages | 60 |
Release | 1961 |
Genre | |
ISBN |