A study of the dynamic behavior of the Merchant Ship Reactor Pressurized Water Loop was made using the Reactor Controls Analog Facility. Computer curves show the predicted response of the loop temperatures to normal load changes and component failure accidents. Except for complete flow stoppage, which was not investigated here, the safety system was shown to be adequate in curbing loop temperature excursions due to postulated accidents. (auth
In nuclear power plants the design extension conditions are more complex and severe than those postu...
One of the key safety issues currently addressed by the Pressurized Water Reactor (PWR) industry is ...
To simulate the mode of the RCP starting in an earlier inoperative loop, KORSAR/GP, a code supportin...
A study was conducted on the safety aspects of foreseeable accident types in connection with the Nuc...
Initial experimental and analog results have been obtained from a study of the effect of shipboard d...
An annlog computer study of the ORR gas-cooled loop was made. The effects on fuel and gas temperatur...
The assumptions and equations used to conduct reactor plant load trnnsient studies on the analog com...
This thesis demonstrates a method of analog simulation of a Pressurized-Water Reactor (PWR) using si...
Graduation date: 1986This study addresses the application of a full\ud reactor system computer code ...
Six experiments from the fields of reactor engineering, heat transfer, and dynamics are presented to...
OTS. Heating and cooling tests were made on the ORR HN-1 in-pile loop mockup 0-l-20 to test the oper...
An integrated model that estimates loop flow rate, heat removal, and stability parameters for the Ge...
An extensive transient analysis was made of the NS Savannah power plant using analog computer techni...
Experiments were conducted to study natural circulation behaviour in the PACTEL facility, a medium-s...
A pressurized water loop constructed in the Oak Ridge Research Reactor for use in the Maritime React...
In nuclear power plants the design extension conditions are more complex and severe than those postu...
One of the key safety issues currently addressed by the Pressurized Water Reactor (PWR) industry is ...
To simulate the mode of the RCP starting in an earlier inoperative loop, KORSAR/GP, a code supportin...
A study was conducted on the safety aspects of foreseeable accident types in connection with the Nuc...
Initial experimental and analog results have been obtained from a study of the effect of shipboard d...
An annlog computer study of the ORR gas-cooled loop was made. The effects on fuel and gas temperatur...
The assumptions and equations used to conduct reactor plant load trnnsient studies on the analog com...
This thesis demonstrates a method of analog simulation of a Pressurized-Water Reactor (PWR) using si...
Graduation date: 1986This study addresses the application of a full\ud reactor system computer code ...
Six experiments from the fields of reactor engineering, heat transfer, and dynamics are presented to...
OTS. Heating and cooling tests were made on the ORR HN-1 in-pile loop mockup 0-l-20 to test the oper...
An integrated model that estimates loop flow rate, heat removal, and stability parameters for the Ge...
An extensive transient analysis was made of the NS Savannah power plant using analog computer techni...
Experiments were conducted to study natural circulation behaviour in the PACTEL facility, a medium-s...
A pressurized water loop constructed in the Oak Ridge Research Reactor for use in the Maritime React...
In nuclear power plants the design extension conditions are more complex and severe than those postu...
One of the key safety issues currently addressed by the Pressurized Water Reactor (PWR) industry is ...
To simulate the mode of the RCP starting in an earlier inoperative loop, KORSAR/GP, a code supportin...
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