Pressurized water reactor loss-of-coolant accident phenomena are being simulated with a series of experiments in the U-2 loop of the National Research Universal Reactor at Chalk River, Ontario, Canada. The first of these experiments includes up to 45 parametric thermal-hydraulic tests to establish the relationship between the reflood delay time of emergency coolant, the reflooding rate, and the resultant fuel rod cladding peak temperature. This document contains both experiment proposal and assembly proposal information. The intent of this document is to supply information required by the Chalk River Nuclear Laboratories (CRNL), and to identify the planned procedures and data that will be used both to establish readiness to proceed from one...
In case of Loss-Of-Coolant accident (LOCA) in a Boiling Water Reactor (BWR), heat generated in the n...
A simulated loss-of-coolant accident was performed with a full-length test bundle of pressurized wat...
SIGLEAvailable from British Library Lending Division - LD:4371.323(CFD--84/3) / BLDSC - British Libr...
Pressurized water reactor loss-of-coolant accident (LOCA) phenomena are being simulated with a serie...
A loss of Coolant Accident (LOCA) simulation program is evaluating the thermal-hydraulic and mechani...
A loss-of-coolant accident (LOCA) simulation program is evaluating the thermal-hydraulic and mechani...
Quick-look test results are reported for the initial test series of the Loss-of-Coolant Accident (LO...
"PNL-3765.""NUREG/CR-1735, Addendum 1.""NRC FIN B2277.""Date published: September 1981.""Pacific Nor...
A summary of studies conducted on the pressurizedwater reactor loss-of- coolant accident is presente...
Critical experiments are described, and the hazards attpendant to these experiments are evaluated fo...
Study on understanding of the complexities of boiling in the narrow channel which was occured in a s...
Critical experiments are described, and the hazards attendant to these experiments are evaluated for...
Abstract During the operation lifetime of a Nuclear Research Reactors, the frequency of occurrence...
This document summarizes the work performed by Pacific Northwest Laboratory (PNL) from January 1 thr...
One of the most severe accidents for a nuclear power plant is loss-of-coolant. To demonstrate inhere...
In case of Loss-Of-Coolant accident (LOCA) in a Boiling Water Reactor (BWR), heat generated in the n...
A simulated loss-of-coolant accident was performed with a full-length test bundle of pressurized wat...
SIGLEAvailable from British Library Lending Division - LD:4371.323(CFD--84/3) / BLDSC - British Libr...
Pressurized water reactor loss-of-coolant accident (LOCA) phenomena are being simulated with a serie...
A loss of Coolant Accident (LOCA) simulation program is evaluating the thermal-hydraulic and mechani...
A loss-of-coolant accident (LOCA) simulation program is evaluating the thermal-hydraulic and mechani...
Quick-look test results are reported for the initial test series of the Loss-of-Coolant Accident (LO...
"PNL-3765.""NUREG/CR-1735, Addendum 1.""NRC FIN B2277.""Date published: September 1981.""Pacific Nor...
A summary of studies conducted on the pressurizedwater reactor loss-of- coolant accident is presente...
Critical experiments are described, and the hazards attpendant to these experiments are evaluated fo...
Study on understanding of the complexities of boiling in the narrow channel which was occured in a s...
Critical experiments are described, and the hazards attendant to these experiments are evaluated for...
Abstract During the operation lifetime of a Nuclear Research Reactors, the frequency of occurrence...
This document summarizes the work performed by Pacific Northwest Laboratory (PNL) from January 1 thr...
One of the most severe accidents for a nuclear power plant is loss-of-coolant. To demonstrate inhere...
In case of Loss-Of-Coolant accident (LOCA) in a Boiling Water Reactor (BWR), heat generated in the n...
A simulated loss-of-coolant accident was performed with a full-length test bundle of pressurized wat...
SIGLEAvailable from British Library Lending Division - LD:4371.323(CFD--84/3) / BLDSC - British Libr...