The initial physics tests on the Shield Test Experiment reactor and the precriticality rod-drop test data are presented. (auth)

None

Fabrication of internal reflector pieces for the SNAP-8 core is described. These reflectors were made of BeO, with and without the addition of Sm/sub 2/O/sub 3/ as a nuclear poison. Because of the high density and dimensional tolerance requirements, the complexity of shapes, and the comparatively modest number of parts to be produced (approximately 1000), the blanks were hot pressed and subsequently machined with diamond wheels and cores. In almost all cases, the specified density of 98% of theoretical was achieved. The low eutectic temperature in the BeO--Sm/sub 2/O/sub 3/ system of about 1420 deg C necessitated special pressing parameters, which were arrived at by experimentation. A rather coarse grit size (80) was used for the diamond wheels, which resulted in very little wear to the wheels, and an extremely low dimensional rejection rate on the blanks. Because of the toxicity of BeO, all equipment was enclosed, and was held under negative pressure. (auth)

This document details activities of the irradiation processing department during the month of June, 1963. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; and Financial Operation.

This document details activities of the Irradiation Processing Department during the month of June, 1964. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; Employee Relations Operation; and Financial Operation.

This report details activities of the Fuels Development Operation for the months of April, May, and June 1961.

This is the monthly report for the Hanford Laboratories Operation, June 1963. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

The program`s objective is to develop the technical foundation for use of projection fuel elements through an accelerated testing program. Two types of projection fuel elements are being considered (1) Self-supported fuel elements for use in ribless aluminum or zirconium process tubes; and (2) Bumper fuel elements for use in ribbed process tubes. A further objective of the program is to determine the most desirable method of fabrication and type of support for projection fuel elements. The program must develop the self-supported concept in time to meet the proposed ribless zirconium process tube installation schedule. Parallel development of the bumper fuel element is an interim program to realize immediate gains in reduced hot spot rupture tendency, during the change over to zirconium tubes. The appended charts indicate the proposed accelerated testing and development schedules being followed. Testing of the self-support concept has indicated that the collapsible supports are adequate to maintain fuel centering, do not introduce additional corrosion problems resulting from the supports, and do in fact greatly reduce the incidence of hot-spot flow patterns. Reductions in rupture potential of at least a factor of 30 have been demonstrated at the 95% confidence level. Bumper fuel testing has indicated that …

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Waggoner Carr, regarding a legal question submitted for clarification: Whether a corporation may, through a non-lawyer, seek a writ of sequestration in a Justice of the Peace Court, or in a Small Claims Court.

This document details activities of the irradiation processing department during the month of June 1960. A general summary is included at the start of the report, after which the report is divided into the following sections: research and engineering operations; production and reactor operations; facilities engineering operation; employee relations operation; and financial operation.

This monthly report details reactor and materials technology activities during the month of June 1965.

The monthly report for the Hanford Laboratories Operation, June 1961. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, and physics and instrumentation research, operations research and synthesis operation, programming, laboratory auxiliaries operation, and professional placement and relations practices are discussed.

The demonstrated operating efficiency performance which has resulted from poison spline usage forces an economic decision concerning the self-supported and bumper fuel element programs. As originally conceived the projection fuel elements would preclude the insertion of a spline under the fuel charge; thus it is very important that means be devised either to make poison spline usage compatible with future pile loadings or to demonstrate that some other supplementary control system, which is compatible with future pile loadings, can approximate the effect the splines have an operating efficiency. This report shows the appreciable performance improvement which has been achieved at KE Reactor through the application of the poison spline system.

Submitted herewith are source and special nuclear material composition for the month of June, 1966. Normal uranium, depleted uranium, enriched uranium, plutonium, thorium, uranium-233, deuterium, enriched lithium, neptunium-237, plutonium-238, and tritium are accounted.

Abstract: This report describes the fabrication of elements for the OMRE third core loading.

Introduction: On November 14, 1961, an environmental test program commenced on the first SNAP 10A system structure, S10A-PSM-1.

Abstract: this report discusses and summarizes all stress analysis done on the SNAP 10A system; it also mentions many of the structural tests which were accomplished.

Abstract: This report presents the results of the structural tests which were performed on the S10A-PSM-1A system to qualify the basic structural design for the anticipated launch environment.

Progress report for the Piqua Reactor Operations Analysis Program describing observations and analyses at the Piqua Nuclear Power Facility (PNPF). The program goals are to monitor operations and collect data in order to ensure that the plant's operation is safe, to improve design and performance, to evaluate the performance and lifetime of the plant's components and systems, to evaluate plant safety and safeguards, and to disseminate all information to the scientific community.

Scope. This specification covers ingots of zirconium alloy designated as Zircaloy-2, and intended for the production of reactor components.

Scope. This specification covers Zircaloy-2 wire material for reactor use where high integrity and satisfactory corrosion resistance at elevated temperatures are required.

Scope. This specification covers Zircaloy-2 tubing, both seamless and welded, for reactor fuel rod sheathing where high integrity, and satisfactory corrosion resistance at elevated temperatures ae required.

Scope. This specification covers Zircalogy-2 sheet and strip material for reactor use where high integrity and satisfactory corrosion resistance at elevated temperatures are quired.

From abstract: The principal efforts during the final period were concerned with plant testing, modifications to the plant to enable it to produce full design load at high ambient temperatures, the compilation and evaluation of plant performance data, preparation of documents and transfer of the plant to the AEC and final resolution of all outstanding contract scope items.