The purpose of this report is to present a conceptual design study on a low power electrical and heat generating plant powered by nuclear energy. The nuclear reactor used in this study is the homogeneous circulating fuel type.

A method of determining enclosure pressure in the event of a reactor rupture is presented and a sample calculation is shown. This method was used in calculating the design pressure of the Dresden Nuclear Power Station enclosure.

The General Electric Company is designing and building a 180,000 kilowatt nuclear power plant for the Commonwealth Edison Company at a site near the confluence of the Kankakee and Des Plaines Rivers in Grundy County, Illinois, about 47 miles southwest of Chicago. The plant will be known as the Dresden Nuclear Power Station, and will employ a nuclear reactor of the dual-cycle boiling water type.

A method for calculating the frequency response of weighted voids (proportional to reactivity of steam voids) as a function of reactor power is presented.

In this paper arbitrary limits of the general fission source gamma problem are set. Then, by assuming cooling of at least one day, it is shown that only twelve different fission product gamma sources need ever be considered.

In concurrent flow of two phase mixtures there exists a velocity difference between the vapor and liquid phases. This difference in velocity is known as the slip velocity. The prediction of slip is the subject of Part I. In boiling systems there is some heat transfer rate at which nucleste boiling becomes unstable. At this point the separate bubbles coalesce forming an insulating vapor film on the heat transfer surface resulting in the destruction, or burnout, of the heater. The prediction of the conditions causing burnout is the subject of Part II.

This report is submitted to the U. S. Atomic Energy Commission as a final summary safeguards and hazards evaluation of a proposed test reactor at its Vallecitos Atomic Laboratory in Alameda County of California. It is the purpose of this report to provide sufficient data to obtain an AEC facility license for the reactor.

Commonwealth Edison Company for the purpose of supplementing the license application for the Dresden Nuclear Power Station submits herewith Amendment No.1 to the portion of the Final Hazards Summary Report entitled Preliminary Hazards Summary Report.

The General Electric Company is designing and building a 180,000 kilowatt nuclear power plant for the Commonwealth Edison Company at a site 47 miles southwest of Chicago. The construction permit was issued on May 4, 1956 but is subject to submittal to the Commission of a final hazards summary report and a finding by the Commission that the final design provides reasonable assurances that the health and safety of the public will not be endangered by operation of the reactor in accordance with the specified procedures.

This report is the second amendment to the Preliminary Hazards Summary Report for the Dresden Nuclear Power Station (GEAP-1044) submitted to the United States Atomic Energy Commission on September 3, 1957.

GE is amending its application of 6/5/57 to construct and operate the Nuclear Test Reactor in order to incorporate changes in procedure and equipment.

Zircaloy-2 tubing was successfully joined to austenetic and ferritic stainless steel tubing by fusion bonding. Tungsten inert gas welding was employed to join a flange to a pressure tube. This work was performed to help determine the design of pressure tubes of a pressure tube reactor.

This report supersedes the similarly titled report dated December 31, 1958. It describes briefly features of the Dresden plant and proposes technical specifications.

This report is an amendment to the Preliminary Hazards Summary Report (1) and the Operating Procedures and Emergency Plans (5) for the Dresden Nuclear Power Station, submitted to the United States Atomic Energy Commission on September 3, 1957, and June 5, 1958, respectively.

This report presents the reactor description and safeguard evaluation for an open pool research and test reactor being supplied to the State College of Washington, Pullman, Washington, by the General Electric Company.

An investigation was made of the neutron and gamma flux distribution along the entire length of a withdrawn control rod in the SRE in order to determine heating, activation and dose rates produced by the streaming neutrons and gammas.

This report presents the description and safeguard evaluation of an open pool research and test reactor rated at one megawatt. The reactor is being proposed by the General Electric Company to the Rhode Island and Providence Plantation Atomic Energy Commission.

Experimental test loops have been used to study the problem of hydraulic stability. The oscillatory behavior of a single-phase and two-phase natural circulation loop has been examined at atmospheric pressures and oscillating modes of operation were studied in terms of heat input.

Three edge loaded thoria-urania nuclear fuel samples were assembled into a capsule, irradiated and examined. This irradiation was the first of a series to develop thoria-urania fuel for high heat flux, specific power and burn-up operation in a sodium graphite reactor.

This report summarizes the radiation and shielding analysis for a 30,000 SHP natural circulation boiling water reactor for ship propulsion. The reactor is proposed for installation in a 60,000 DWT, 18 knot tanker of the T-7 class.

This is a preliminary report on the investigation of the N.S. Savannah replacement fuel rod vibration amplitude when excited by water flowing parallel to the axis of the fuel rod. Methods of calculating the fuel rod frequency in air were verified by experiment. Work is continuing to establish the validity of methods of calculating natural frequencies in water and to confirm the correlation of flow induced vibration amplitude found in reference (1).

Methods for analyzing chemical impurities in sodium metal samples are presented. Chemical analysis was used to determine the following impurities: Calcium, Carbon, Chromium, Iron, Lithium, Nickel, Oxygen, Potassium, and Zirconium. Spectrographic analysis was used to determine many other impurities. Sodium samples obtained from experimental apparatus operated as part of the work being conducted for Atomics International were analyzed by these methods.

From introduction: "The purpose of the report is to set forth the development philosophy, objectives and expected results of the AEC-GE Nuclear Superheat Project."

The effect of the (n, 2n) and (n, o<) reactions on the neutron economy of a beryllium moderated reactor is investigated.