Liquid Metal Fuel Reactor Experiment Annual Technical Report: 1958 (open access)

Liquid Metal Fuel Reactor Experiment Annual Technical Report: 1958

Annual report of the Liquid Metal Fuel Reactor Experiment describing progress during calendar year 1958 and as well as an evaluation of progress and plans for future work.
Date: March 25, 1959
Creator: Babcock & Wilcox Company
System: The UNT Digital Library
Lynchburg Test Reactor:  Critical Experiment, Hazard Evaluation (open access)

Lynchburg Test Reactor: Critical Experiment, Hazard Evaluation

This report summarizes the hazards associated with the operation of the Lynchburg Test Reactor (LTR) critical experiments. The LTR critical experiment program is outlined and the design of the experiment is described. The experiments will provide basic data to check two-dimensional calculational methods and provide information needed in the design of the LTR.
Date: November 1959
Creator: Engelder, T. C. & Schutt, P. F.
System: The UNT Digital Library
Liquid Metal Fuel Reactor Experiment:  Dynamic Utility Test Loop (open access)

Liquid Metal Fuel Reactor Experiment: Dynamic Utility Test Loop

This report provides an overview of the creation of the Liquid Metal Fuel Reactor Experiment program. It furthers the work by constructing a single loop to test all the components required for the 16 loop reactor. This utility loop was also constructed to provide a facility for testing various components such as valves and flow meters.
Date: May 5, 1959
Creator: Baker, O. H.
System: The UNT Digital Library
Liquid Metal Fuel Reactor Experiment, Cavitation by Bismuth (open access)

Liquid Metal Fuel Reactor Experiment, Cavitation by Bismuth

From abstract: "Croloy 2 - 1/4 was tested to determine the causes and effects of cavitation in dynamic liquid bismuth solutions."
Date: December 1959
Creator: Hovanec, F. L.
System: The UNT Digital Library
Transient Flow Performance in a Multi-Loop Nuclear Reactor System (open access)

Transient Flow Performance in a Multi-Loop Nuclear Reactor System

The method present can be used to determine fluid flow and coolant pump speed transients in a nuclear reactor system. Included are transients due to power failure, starting pumps in idle loops, and the opening of an active pump's discharge. Parallel pumps in the system may be analysed independently of each other. Typical cases are presented for the N.S. Savannah (NMSR) and Consolidated Edison Thorium Reactor (CETR).
Date: December 1959
Creator: Boyd, George M., Jr.; Rosser, Ralph M. & Cardwell, Bennett B., Jr.
System: The UNT Digital Library