Author:
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 138
Book Description
Correlation of Critical Heat Flux Data for Application to Boiling Water Reactor Conditions
Author:
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 138
Book Description
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 138
Book Description
Correlation of critical heat flux data for application to boiling water reacrot conditions
Author: J. E. Hench
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Design Basis for Critical Heat Flux Condition in Boiling Water Reactors
Author: J. M. Healzer
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 76
Book Description
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 76
Book Description
An Empirical Correlation of Critical Boiling Heat Flux in Forced Flow Upward Through Uniformly Heated Tubes
Author: U. Von Glahn
Publisher:
ISBN:
Category : Heat flux
Languages : en
Pages : 32
Book Description
Publisher:
ISBN:
Category : Heat flux
Languages : en
Pages : 32
Book Description
A Critical Heat Flux Correlation for Advanced Pressurized Light Water Reactor Application
Author: Mario Dalle Donne
Publisher:
ISBN:
Category : Pressurized water reactors
Languages : de
Pages : 90
Book Description
Publisher:
ISBN:
Category : Pressurized water reactors
Languages : de
Pages : 90
Book Description
Boiling Water Reactor Technology Status of the Art Report
Author: P. A. Lottes
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 194
Book Description
Information on heat transfer and hydraulics pertinent to the design and operation of boiling water reactor power plants is presented. The following areas of discussion are covered: heat transfer, two-phase density studies, two-phase pressure drop, critical heat flux and burnout, boiling stability, calculation procedures for boiling systems, and thermal-hydraulic design procedures for boiling water reactors.
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 194
Book Description
Information on heat transfer and hydraulics pertinent to the design and operation of boiling water reactor power plants is presented. The following areas of discussion are covered: heat transfer, two-phase density studies, two-phase pressure drop, critical heat flux and burnout, boiling stability, calculation procedures for boiling systems, and thermal-hydraulic design procedures for boiling water reactors.
REPP
Author: R. M. Hiatt
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 196
Book Description
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.
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 196
Book Description
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
Author: U.S. Atomic Energy Commission
Publisher:
ISBN:
Category :
Languages : en
Pages : 60
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 60
Book Description
A Critical Heat Flux Correlation for Advanced Pressurized Light Water Reactor Application
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Critical Heat Flux for Flow Boiling of Water at Low Pressure on Smooth and Micro-Structured Zircaloy Tube Surfaces (KIT Scientific Reports ; 7627)
Author: Christoph Haas
Publisher: KIT Scientific Publishing
ISBN: 3866449232
Category :
Languages : en
Pages : 186
Book Description
Publisher: KIT Scientific Publishing
ISBN: 3866449232
Category :
Languages : en
Pages : 186
Book Description