The nuclear characteristics of a variety of small reactors composed of thoria -urania fuel in heavy water were determined in a program of critical experimentation. The fuel element consisted of ceramic ThO/sub 2/-U/sup 235/ O/ sub 2/ pellets stacked to a height of 1.5 m within 0.787-cm-OD aluminum tubing. The pellets used most frequently were of 0.587-cm diameter and had a Th/U/sup 235/ atom ratio of 25. Rods containing similar pellets with only half as much U/sup 235/ were used to achieve small changes in the U/sup 235/ content of the cores. Some cores were assembled with 0.660-cm-diameter pellets having an atom ratio of 15. All cores were located in a 2-m-diameter tank containing D/sub 2/O. Three distinct core structures were used, allowi...
A series of critical experiments were performed with 4.31 wt % /sup 235/U enriched UO/sub 2/ fuel ro...
In this paper, the use of thorium in pressurized water reactor fuel assemblies is investigated. The ...
With the aim of investigating the technical feasibility of fuelling a conventional BWR (Boiling Wate...
The fourth in a series of Nuclear Regulatory Commission funded criticality experiments have provided...
A series of criticality experiments with undermoderated (1.6 water-to-fuel volume ratio) 2.35 wt% an...
A series of critical experiments were completed from 1962–1965 at Oak Ridge National Laboratory’s (O...
Declassified 29 Aug 1973. Critical experiments were performed with fuel elements for the Project Rov...
The RB reactor was designed as a natural-uranium, heavy water, nonreflected critical assembly in the...
The RB reactor was designed as a natural-uranium, heavy water, nonreflected critical assembly in the...
A program to provide experimental data for validating calculational techniques and nuclear data used...
Calculations are reported relating to the uniform lattice critical experiments performed in the ZPR-...
In this paper, the use of thorium in pressurized water reactor fuel assemblies is investigated. The ...
AbstractThe research carried out on thorium-based fuels indicates that these fuels can be considered...
The results obtained in a criticality experiments program performed for British Nuclear Fuels, Ltd. ...
With the aim of investigating the technical feasibility of fuelling a conventional BWR (Boiling Wate...
A series of critical experiments were performed with 4.31 wt % /sup 235/U enriched UO/sub 2/ fuel ro...
In this paper, the use of thorium in pressurized water reactor fuel assemblies is investigated. The ...
With the aim of investigating the technical feasibility of fuelling a conventional BWR (Boiling Wate...
The fourth in a series of Nuclear Regulatory Commission funded criticality experiments have provided...
A series of criticality experiments with undermoderated (1.6 water-to-fuel volume ratio) 2.35 wt% an...
A series of critical experiments were completed from 1962–1965 at Oak Ridge National Laboratory’s (O...
Declassified 29 Aug 1973. Critical experiments were performed with fuel elements for the Project Rov...
The RB reactor was designed as a natural-uranium, heavy water, nonreflected critical assembly in the...
The RB reactor was designed as a natural-uranium, heavy water, nonreflected critical assembly in the...
A program to provide experimental data for validating calculational techniques and nuclear data used...
Calculations are reported relating to the uniform lattice critical experiments performed in the ZPR-...
In this paper, the use of thorium in pressurized water reactor fuel assemblies is investigated. The ...
AbstractThe research carried out on thorium-based fuels indicates that these fuels can be considered...
The results obtained in a criticality experiments program performed for British Nuclear Fuels, Ltd. ...
With the aim of investigating the technical feasibility of fuelling a conventional BWR (Boiling Wate...
A series of critical experiments were performed with 4.31 wt % /sup 235/U enriched UO/sub 2/ fuel ro...
In this paper, the use of thorium in pressurized water reactor fuel assemblies is investigated. The ...
With the aim of investigating the technical feasibility of fuelling a conventional BWR (Boiling Wate...