Data report for the NRC/PNL Halden assembly IFA-432 PDF Download
Are you looking for read ebook online? Search for your book and save it on your Kindle device, PC, phones or tablets. Download Data report for the NRC/PNL Halden assembly IFA-432 PDF full book. Access full book title Data report for the NRC/PNL Halden assembly IFA-432 by C. R. Hann. Download full books in PDF and EPUB format.
Author: C. R. Hann
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Get Book Here
Book Description
Author: C. R. Hann
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Get Book Here
Book Description
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Get Book Here
Book Description
The report presents the in-reactor data collected from the NRC/PNL Halden Assembly IFA-432 as a part of the program entitled ''Experimental Vertification of Steady State Fuel Codes, '' sponsored by the Fuel Behavior Research Branch of the USNRC. The purpose of this program is to reduce the uncertainties of calculating the thermal stored energy in an operating nuclear fuel rod. The report presents fuel centerline thermocouple readings, cladding elongation monitor readings, rod internal pressure readings, and neutron detector readings. The neutron detector readings were corrected to represent rod local powers at the thermocouple locations. These data are presented in the form of plots of the variables versus time during the portion of the irradiation period from December 1975 to January 1978. Also included are descriptions of the test rationale, assembly and rod designs, test facility, instrument array and calibration, and data processing methods. Topical reports discussing specific aspects and results of the data analysis are referenced. As of May 1978, the assembly burnup had reached its design goal of 20,000 MWd/MTM. However, it has been decided to leave the assembly in core to collect high burnup fission gas release data. The xenon-filled Rod 4 was replaced with the non-instrumented Rod 8 (Rod 1 design) after the first cycle. Six of the twelve original thermocouples, four of the six cladding elongation monitors, all SPND'S and all pressure transducers remain operable at this writing.
Author: E. R. Bradley
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 126
Get Book Here
Book Description
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 6
Get Book Here
Book Description
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Get Book Here
Book Description
This report presents the in-reactor data collected from the U.S. Nuclear Regulatory Commission (NRC)/Pacific Northwest Laboratory (PNL) Halden test assembly IFA-432 for the period from April 1978 through May 1980. The irradiation test is part of an experimental program entitled 11 Experimental Support and Development of Single-Rod Fuel Codes" sponsored by the Fuel Behavior Research Branch of the 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 (TC) positions are shown as a function of time. The local powers were derived from neutron detector readings while the other variables were measured directly. 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.
Author: Donald D. Lanning
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 80
Get Book Here
Book Description
Author: E. R. Bradley
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 96
Get Book Here
Book Description
Author: C. Nealley
Publisher:
ISBN:
Category : Irradiation
Languages : en
Pages : 214
Get Book Here
Book Description
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Get Book Here
Book Description
The report presents the in-reactor data collected from the NRC/PNL Halden Assembly IFA-431 as a part of the program entitled ''Experimental Verification of Steady State Fuel Codes, '' sponsored by the Fuel Behavior Research Branch of the USNRC. The purpose of this program is to reduce the uncertainties of calculating the thermal stored energy in an operating nuclear fuel rod. The report presents fuel centerline thermocouple readings, cladding elongation monitor readings, rod internal pressure readings, and neutron detector readings. The neutron detector readings were corrected to represent rod local powers at the thermocouple locations. These data are presented in the form of plots of the variables versus time during the irradiation period from June 1975 to February 1976. Also included are descriptions of the test rationale, assembly and rod designs, test facility, instrument array and calibration, and data processing methods. Topical reports discussing specific aspects and results of the data analysis are referenced.
Author:
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 1060
Get Book Here
Book Description
