Report containing "the results of a study which was directed at providing additional experimental loop irradiation space for the AEC-DRD testing program. It was a premise that the experiments allocated to this reactor were those that could not be accommodated in the MTR, ETR or in existing commercial test reactors" (p. 5).

Report concerning the technical feasibility of induction welding for use in remote maintenance at the Liquid Metal Fuel Reactor Experiment. Includes descriptions of the device used, test procedures, and results.

Report describing parametric studies of eleven fast reactor fuel systems undertaken to determine the design and economic factors for producing electricity. The methods used for making the parametric studies are described, as well as the results of these studies. Appendices begin on page 103.

Report describing the Enrico Fermi Atomic Power Plant, its fast breeder reactor, and heat transport systems.

Specifications including detail dimension, materials, fabrication steps, acceptance criteria, and final assembly steps for the swaged uranium dioxide, 19-rod cluster Plutonium Recycle Test Reactor fuel element.

Report documenting the Halogen Collector Test program, which was undertaken to provide "methods of removing trace quantities of radioactive iodine from an air stream" (p. 1). The report includes designs of the program and the test facility, test results, analysis of these results, and encountered problems. Appendices begin on page 38.

Data book to used as an aid in calculations on physical properties and flow characteristics of air.

From introduction: "Evaluation of the present economic and technological status of power reactors that are cooled and moderated by heavy water and fueled with natural uranium."

Abstract: Irradiated fuel elements from the Organic Moderated Reactor Experiment (OMRE) first core loading have been examined and evaluated to determine: (1) the stability of the floating plate fuel element design, (2) the stability of the stainless steel clad UO2 - stainless steel cermet core fuel plates under irradiation and exposure to the organic coolant, (3) the extent and nature of deposits on the fuel element services, and (4) the distribution of burnup in the fuel elements.

Abstract: This report describes an advanced sodium-cooled, graphite-moderated nuclear power plant which utilizes high-pressure, high-temperature steam to generate electricity at a high thermal efficiency.

Abstract: It has been proposed that a fuel element containing porous uranium be used for moderately high temperature applications. In an effort to determine the structural integrity of this type of fuel body, thermal cycling tests have been conducted on porous uranium.

From foreword: This report presents the preliminary design of a gamma irradiator intended for use as an experimental hospital sterilizer.

From abstract: The PT-750 is designed to be used in conjunction with a production tester which requires automatic recording of test data. This manual provides a source of procedures and reference material necessary in automatic recording and in use of the PT-750.

Abstract: An element by element reactivity check for SM-1 Core II fuel elements and control rod absorber sections was performed and the burnable nuclear poison loading in the SM-1 Core II stationary fuel elements was established. An approach to criticality of the SM-1 Core II was performed by the inverse multiplication method and the critical rod bank position obtained as a function of fuel loading up to the full SM-1 Core II loading. Maximum and minimum core reactivity measurements were obtained by selective loading of stationary fuel elements and the total "excess K" for the core established. Power distribution measurements in the region of the core-reflector interface and the fuel-absorber interface in the control rod assemblies were performed. The effectiveness of europium flux suppressors in the top of control rod fuel elements and the power peaking in stationary elements adjacent to water gaps in control rod assemblies were measured. Survey measurements established the worth of spiking cold clean SM-1 cores with SM-2 elements, and of water holes in the SM-1 core which might be utilized as flux traps for materials irradiation.