The assumptions and equations used to conduct reactor plant load trnnsient studies on the analog computer are presented. The study was performed to determine the magnitude of reactor cooling water temperature and volume variations caused by secondary plant load transients, and to establish the size of the pressurizer which would be capable of limiting the cooling water pressure variations caused by the volume surges. (auth
Graduation date: 1981In this study a method has been demonstrated by which\ud the departure from nuc...
Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1982.MICROFICHE ...
"Bettis Atomic Power Laboratory, Pittsburgh, Pennsylvania, operated for the U.S. Atomic Energy Commi...
Six experiments from the fields of reactor engineering, heat transfer, and dynamics are presented to...
This thesis demonstrates a method of analog simulation of a Pressurized-Water Reactor (PWR) using si...
A digital computer model has been developed to simulate the kinetic response of a thermal pressurize...
A study of the dynamic behavior of the Merchant Ship Reactor Pressurized Water Loop was made using t...
A parametric study of pressurized light water reactor cores was undertaken, in which "both heat...
The performance of a reactor coolant pump should be modeled accurately so that it made be used in a ...
A computer program is being developed for the solution of general system flow problems. As a complem...
A digital computer program FLARE was developed for calculating the core reactivity and power distrib...
The steady-state and dynamlc characterlstics of the Pathfinder systems were simulated on a dual-cons...
Up to this time, the design of Pressurizers in Nuclear Power Plants has been quite empirical due to ...
The purpose of the test was to determine the responses of the plant when subjected to load transient...
Pressurizer modeling for predicting the dynamic pressure of the PIUS system is presented. The transi...
Graduation date: 1981In this study a method has been demonstrated by which\ud the departure from nuc...
Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1982.MICROFICHE ...
"Bettis Atomic Power Laboratory, Pittsburgh, Pennsylvania, operated for the U.S. Atomic Energy Commi...
Six experiments from the fields of reactor engineering, heat transfer, and dynamics are presented to...
This thesis demonstrates a method of analog simulation of a Pressurized-Water Reactor (PWR) using si...
A digital computer model has been developed to simulate the kinetic response of a thermal pressurize...
A study of the dynamic behavior of the Merchant Ship Reactor Pressurized Water Loop was made using t...
A parametric study of pressurized light water reactor cores was undertaken, in which "both heat...
The performance of a reactor coolant pump should be modeled accurately so that it made be used in a ...
A computer program is being developed for the solution of general system flow problems. As a complem...
A digital computer program FLARE was developed for calculating the core reactivity and power distrib...
The steady-state and dynamlc characterlstics of the Pathfinder systems were simulated on a dual-cons...
Up to this time, the design of Pressurizers in Nuclear Power Plants has been quite empirical due to ...
The purpose of the test was to determine the responses of the plant when subjected to load transient...
Pressurizer modeling for predicting the dynamic pressure of the PIUS system is presented. The transi...
Graduation date: 1981In this study a method has been demonstrated by which\ud the departure from nuc...
Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1982.MICROFICHE ...
"Bettis Atomic Power Laboratory, Pittsburgh, Pennsylvania, operated for the U.S. Atomic Energy Commi...