Cooling parameters for some of the SRS reactor internal components are computed using the Transient Reactor Analysis Code, TRAC.'' In order to benchmark the code, the Safety Analysis Group of SRL requested an experiment to provide measurements of cooling parameters in a well defined physical system utilizing SRS reactor component(s). The experiment selected included a short length of septifoil with both top and bottom fittings containing five simulated control rods in an unseated'' configuration. Power level to be supplied to the rods was targeted at 2.5 kilowatts per foot. The septifoil segment was to be operated with no forced flow in order to evaluate thermal-hydraulic cooling. Parameters to be measured for comparison with code predictio...
This study investigated the importance of heating processes within a nuclear power plant. The applic...
Pressurized water reactor loss-of-coolant accident phenomena are being simulated with a series of ex...
The Secure Transportable Autonomous Reactor (STAR) concept under development at Argonne National Lab...
The problem addressed in this experimental study is the measurement of critical or dryout heat flux ...
Following a hypothetical Loss of Coolant Accident (LOCA) the moderator level in the reactor tank wou...
Study on understanding of the complexities of boiling in the narrow channel which was occured in a s...
A novel full scale production reactor fuel assembly model was designed and built to study thermal-hy...
International audienceDuring an hypothetical reactivity initiated accident in the core of a nuclear ...
The primary safety concern at a nuclear reactor is to maintain water inventory inside the reactor co...
In order to focus on the ability of the TRAC code to predict critical discharge flowrates and water ...
Blowdon cooling heat transfer is an important process that occurs early in a hypothetical large brea...
Graduation date: 2017The Direct Reactor Auxiliary Cooling System (DRACS) is a passive safety system ...
This paper summarizes the results of TRAC-PF1/MOD3 calculations of Mark-22 fuel assembly of loss-of-...
The Transient Reactor Analysis Code (TRAC) being developed at Los Alamos National Laboratory provide...
The study of the physical phenomenon of natural circulation is of importance for the development of ...
This study investigated the importance of heating processes within a nuclear power plant. The applic...
Pressurized water reactor loss-of-coolant accident phenomena are being simulated with a series of ex...
The Secure Transportable Autonomous Reactor (STAR) concept under development at Argonne National Lab...
The problem addressed in this experimental study is the measurement of critical or dryout heat flux ...
Following a hypothetical Loss of Coolant Accident (LOCA) the moderator level in the reactor tank wou...
Study on understanding of the complexities of boiling in the narrow channel which was occured in a s...
A novel full scale production reactor fuel assembly model was designed and built to study thermal-hy...
International audienceDuring an hypothetical reactivity initiated accident in the core of a nuclear ...
The primary safety concern at a nuclear reactor is to maintain water inventory inside the reactor co...
In order to focus on the ability of the TRAC code to predict critical discharge flowrates and water ...
Blowdon cooling heat transfer is an important process that occurs early in a hypothetical large brea...
Graduation date: 2017The Direct Reactor Auxiliary Cooling System (DRACS) is a passive safety system ...
This paper summarizes the results of TRAC-PF1/MOD3 calculations of Mark-22 fuel assembly of loss-of-...
The Transient Reactor Analysis Code (TRAC) being developed at Los Alamos National Laboratory provide...
The study of the physical phenomenon of natural circulation is of importance for the development of ...
This study investigated the importance of heating processes within a nuclear power plant. The applic...
Pressurized water reactor loss-of-coolant accident phenomena are being simulated with a series of ex...
The Secure Transportable Autonomous Reactor (STAR) concept under development at Argonne National Lab...