Startup Data Report for NRC/PNL Halden Assembly IFA-513

Startup Data Report for NRC/PNL Halden Assembly IFA-513 PDF Author: Donald D. Lanning
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 80

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Startup Data Report for NRC/PNL Halden Assembly IFA-513

Startup Data Report for NRC/PNL Halden Assembly IFA-513 PDF Author: Donald D. Lanning
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 80

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Experimental Support and Development of Single-rod Fuel Codes Program

Experimental Support and Development of Single-rod Fuel Codes Program PDF Author: D. D. Lanning
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 64

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NUREG/CR.

NUREG/CR. PDF Author: U.S. Nuclear Regulatory Commission
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 180

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Data Report for the Instrumented Fuel Assembly IFA-513

Data Report for the Instrumented Fuel Assembly IFA-513 PDF Author: E. R. Bradley
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 116

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Energy Research Abstracts

Energy Research Abstracts PDF Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 748

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Data Report for the Instrumented Fuel Assembly IFA-513

Data Report for the Instrumented Fuel Assembly IFA-513 PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

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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

Energy Research Abstracts PDF Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 892

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Data report for the NRC/PNL Halden assembly IFA-432

Data report for the NRC/PNL Halden assembly IFA-432 PDF Author: C. R. Hann
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ISBN:
Category :
Languages : en
Pages : 0

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Reactor Safety Research Programs

Reactor Safety Research Programs PDF Author: C. W. Dotson
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 180

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Reactor Safety Research Programs

Reactor Safety Research Programs PDF Author: Pacific Northwest Laboratory
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 180

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