Results of tests to remove fission gases, xenon and krypton, formed during the operation of a nuclear reactor.

Work required, proposed schedule, and an estimate of the costs for complete program to build first LMFR power plant.

Preliminary study to determine the technical and economic feasibility of a 315 eMW High-Temperature, Integral, Liquid Metal Fuel Reactor (HTIR).

Extensive experimental program undertaken to provide data on the operation and testing of a bismuth-to-bismuth dual-loop system.

Study of nuclear power plants incorporating the Spectral Shift Control Reactor (SSCR).

Liquid Metal Fuel Reactor Experiment program annual technical report.

Liquid Metal Fuel Reactor Experiment program quarterly technical report.

Liquid Metal Fuel Reactor Experiment program quarterly technical report.

Conceptual design of experimental liquid metal fuel reactor.

From abstract: "Croloy 2 - 1/4 was tested to determine the causes and effects of cavitation in dynamic liquid bismuth solutions."

From introduction: "Investigation of breeding potential and technical and economic feasibility of breeding in the Liquid Metal Fuel Reactor concept."

From abstract: "This work amplified previous design studies by considering accidents of greater severity, automatic limiting devices to preclude safety action, and more realistic parameters based on operating experience."

From abstract: "The economic factors of chemical processing of the fuel and blanket from liquid bismuth fuel reactors are described and evaluated."

From abstract: "A summary of work done by The Babcock & Wilcox Company to evaluate thorium fuels for the Heavy Water Organic Cooled Reactor (HWOCR)."

From introduction: "Complete exploitation of the advantages of thorium as a fertile material in thermal and particular resonant spectrum reactors has been inhibited by the lack of quantitative physical property data for thoria and thoria-urania fuels."

Quarterly technical report discussing progress and activities of the Liquid Metal Fuel Reactor Experiment.

Quarterly technical report discussing progress and activities of the Liquid Metal Fuel Reactor Experiment.

The purpose of this report is to describe the shielding calculations and techniques used in sizing the MMSR primary shield, the results obtained, and the resulting shield thicknesses. The present report covers many of the items scheduled for presentation in the final MMSR shield design report to be issued in November of 1958. The primary shield in the MMSR consists of the reflector, thermal shields, pressure vessel wall, a 33" water annulus and a layer of lead shielding at the exterior of the primary shield tank vary from 3" to 1" in thickness.

The general purpose of this report is to present the major characteristics and design of the Consolidated Edison Thorium Reactor (CETR) core

The pressurizer system and its related design and operating data are described. The philosophy and analytical procedures used in the design of the pressurizer for the Consolidated Edison Thorium Reactor are summarized

Experiments performed by WAPD and others have shown that with fuel in an oxide form, it is possible to continue to operate a nuclear plant with fuel rods that have developed defects with only a small increase in the radiation contamination problem

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.

A series of exponential experiments were performed using Consolidated Edison Thorium Reactor oxide type fuel pins in a light water lattice. These experiments were performed in a new facility where measurements were made at temperatures up to 468 F. In addition, boric acid was added to the system in various concentrations. The main objective of these experiments was to obtain the change in material buckling for the system as operating conditions were changed from ambient temperature to high temperature.

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