Author: E. R. Bradley
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 120
Book Description
Data Report for the Instrumented Fuel Assembly IFA-513
Author: E. R. Bradley
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 120
Book Description
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 120
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.
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
Final Data Report for the Instrumented Fuel Assembly (IFA)-432
Author: E. R. Bradley
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 96
Book Description
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 96
Book Description
Experiment Data Report for Instrumented Fuel Assembly IFA-226
Author: Judith A. Ramsthaler
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 606
Book Description
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 606
Book Description
End-of-irradiation Data Report for the Instrumented Fuel Assembly (IFA)-527
Author: M. E. Cunningham
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 132
Book Description
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 132
Book Description
Beginning-of-life Data Report for the Instrumented Fuel Assembly (IFA)-527
Author: D. D. Lanning
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Startup Data Report for NRC/PNL Halden Assembly IFA-513
Author: Donald D. Lanning
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 80
Book Description
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 80
Book Description
Precharacterization Report for Instrumented Fuel Assembly (IFA)-527
Author: M. E. Cunningham
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 120
Book Description
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 120
Book Description
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