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Evaluation of Thorium Fuels for the Heavy Water Organic Cooled Reactor
From abstract: "A summary of work done by The Babcock & Wilcox Company to evaluate thorium fuels for the Heavy Water Organic Cooled Reactor (HWOCR)."
Date:
July 1966
Creator:
unknown
System:
The UNT Digital Library
1000-MWe LMFBR Follow-On Study, Task I Report: Volume 4, Concept III System Description
From introduction: "The third of four designs to be developed by Babcock & Wilcox (B&W), Concept III observes ground rules established under the LMFBR Follow-On Program and is based on the estimated state of technology in 1980."
Date:
July 1967
Creator:
Goulding, B. J.
System:
The UNT Digital Library
Consolidated Edison Thorium Reactor Critical Experiments with Oxide Fuel Pins
This report describes the critical experiments with pin-type oxide fuel elements for the Consolidated Edison Thorium Reactor (CETR). This report also describes the measurements and gives a brief interpretation of the results in some cases
Date:
July 1960
Creator:
Batch, M. L. & Snidow, N. L.
System:
The UNT Digital Library
Consolidated Edision Thorium Reactor Physics Design
The nuclear characteristics of the CETR are described. Core operating lifetime, control-rod worth, and power density distribution are discussed in relation to maximizing the core operating life. Other objectives of nuclear design are to minimize the power-density variation and to assure control of the reactor.
Date:
July 1960
Creator:
Barringer, H. S.; Flickinger, R. B. & Spetz, S. W.
System:
The UNT Digital Library
Consolidated Edison Thorium Reactor: Reactor Vessel Internal Components Design
The design functions and fabrication details for internal components of the CETR are presented and pertinent analytical stress studies are summarized. Functions of the internal components include proper orientation and support for the fuel elements, proper distribution of primary coolant within the reactor vessel, and the establishment of guide channels for the control rods.
Date:
July 1960
Creator:
Ficor, J.; Collings, D. M.; Sandrock, R. J. & Kalen, D. D.
System:
The UNT Digital Library
Control Blade Worth by Partial Water Height and Soluble Boron Methods
The series of experiments described in this paper was performed to determine reactivity values of various patterns of fully inserted cruciform control blades. The experiments yielded the worth of fully inserted blade patterns in terms of their holddown characteristics.
Date:
July 1960
Creator:
MacKinney, Arland L. & Ball, Russell M.
System:
The UNT Digital Library
Preliminary Hazards Summary Report: Babcock & Wilcox Test Reactor
This preliminary Hazards Summary Report presents to the Atomic Energy Commission (AEC), Division of Licensing and Regulation, a description of the Nuclear Development Center, the characteristics of the proposed site, and an evaluation of the potential hazards associated with operating the test reactor at this location.
Date:
July 1962
Creator:
Babcock & Wilcox Company
System:
The UNT Digital Library
Thermal and Hydraulic Design of the Consolidated Edison Thorium Reactor
This report presents the thermal and hydraulic analyses, both steady state and transient, for the CETR. Methods of calculations are discussed and results of analyses are presented. Steady state analyses are included for: pressure drops, flow distribution, orificing, burnout, fuel central melting, local boiling, and bulk boiling. Transient analyses are performed for several loss of forced coolant flow incidents.
Date:
July 1960
Creator:
Ferrell, J. K. (James K.); Flora, H. E.; Hostetler, D. R.; Stanek, L. J. & Vannoy, W. M.
System:
The UNT Digital Library