Author: Donald D. Lanning
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 80
Book Description
Startup Data Report for NRC/PNL Halden Assembly IFA-513
Experimental Support and Development of Single-rod Fuel Codes Program
Author: D. D. Lanning
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 64
Book Description
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 64
Book Description
NUREG/CR.
Author: U.S. Nuclear Regulatory Commission
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 180
Book Description
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 180
Book Description
Data Report for the Instrumented Fuel Assembly IFA-513
Author: E. R. Bradley
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 116
Book Description
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 116
Book Description
Energy Research Abstracts
Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 748
Book Description
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 748
Book Description
Data Report for the Instrumented Fuel Assembly IFA-513
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
This report presents the in-reactor data collected to date from the NRC/PNL Halden test assembly IFA-513. The irradiation test is part of an experimental program entitled 11 Experimental Support and Development of Single Rod Fuel Codes 11 sponsored by the Fuel Behavior Branch of the U.S. Nuclear Regulatory Commission (NRC). The purpose of this program is to reduce the uncertainties of predicting the thermal and mechanical behavior of an operating nuclear fuel rod. Fuel centerline temperatures, cladding elongation, internal fuel rod pressures, and local powers at the thermocouple positions are shown as a function of time for the irradiation period from November 1978 to January 1980. The local powers were derived from neutron detector readings while the other variables were measured directly. The general trends in the data as a function of burnup are presented and discussed. Detailed analysis of the data is not made, but topical reports discussing certain aspects of the data are referenced. Descriptions of the assembly, instrumentation and calibration, and data processing methods are also presented.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
This report presents the in-reactor data collected to date from the NRC/PNL Halden test assembly IFA-513. The irradiation test is part of an experimental program entitled 11 Experimental Support and Development of Single Rod Fuel Codes 11 sponsored by the Fuel Behavior Branch of the U.S. Nuclear Regulatory Commission (NRC). The purpose of this program is to reduce the uncertainties of predicting the thermal and mechanical behavior of an operating nuclear fuel rod. Fuel centerline temperatures, cladding elongation, internal fuel rod pressures, and local powers at the thermocouple positions are shown as a function of time for the irradiation period from November 1978 to January 1980. The local powers were derived from neutron detector readings while the other variables were measured directly. The general trends in the data as a function of burnup are presented and discussed. Detailed analysis of the data is not made, but topical reports discussing certain aspects of the data are referenced. Descriptions of the assembly, instrumentation and calibration, and data processing methods are also presented.
Energy Research Abstracts
Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 892
Book Description
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 892
Book Description
Data report for the NRC/PNL Halden assembly IFA-432
Author: C. R. Hann
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Reactor Safety Research Programs
Author: C. W. Dotson
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 180
Book Description
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 180
Book Description
Reactor Safety Research Programs
Author: Pacific Northwest Laboratory
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 180
Book Description
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 180
Book Description