Results of an investigation of fuel element outer annulus enthalpy imbalance are reported and analytical results of suggested methods to limit this imbalance are presented. Also included are comparisons of calculated and experimental enthalpy imbalance ratios along with other quantities. Results indicate that tightening fuel tolerances and clearances can substantially reduce the present outer annulus imbalance thereby increasing power capability. A basic pre-requisite to reduction of clearance between fuel support diameter and process tube diameter is a test establishment of the minimum allowable clearance compatible with charging requirements. Matching fuel elements to process tube diameters will also reduce the imbalance but is in general not feasible at the present time.

The thoria program at Hanford was initiated in response to an order placed by the Atomic Energy Commission for the production of uranium-233 from the irradiation of thorium or thorium oxide (thoria). The initial orders called for approximately 130 kg U-233 and subsequent orders have since increased this figure. This report provides a brief history of the thoria program, an analysis of the thoria target element failures which occurred during the irradiation phase, and the significant changes in the fabrication methods and inspection criteria and techniques which were made in response to the large number of failures that occurred in the early stages of the program. The thoria program has sustained 25 thoria target element failures. Eighteen of these failures are believed to have been caused as a result of water entry through fabrication defects in the closure weld. Two of the failures were attributable to water entry through the cladding as a result of charging machine damage, and the remaining five failures were caused by water entry in some undetermined manner. The majority of thoria element failures occurred in the early stages of the program. Upon determining the cause of failure, Production Fuels Section initiated programs to upgrade the …

This report gives an analysis of the audit data obtained during the last half of 1965 at eight transfer stations: L9 plutonium product, K6 uranium product, F15 salt waste, D5 dissolved feed, F18 utility waste, G8 organic wash waste, R8 organic wash waste, and U3 laboratory waste. Two ways of improving the Purex quality control program are described.

The power of some SRP fuel assemblies is limited by the burnout safety factor (BOSF) in some applications. This power limitation is unnecessarily restrictive, because the current conservatism in predicting film boiling burnout is unusually large compared to that in predicting unstable flow in fuel assemblies. In the past, most SRP fuel assemblies operated at the flow instability limit and were far enough removed from burnout that a convenient and very conservative burnout limit system could be used. If the same degree of safety was used for both burnout and flow instability, the power of BOSF-limited assemblies could be increased. This memorandum, which is part of the program to improve the system for protection against burnout, evaluates the probability and consequences of burnout at various BOSF levels.

A new concept for separation of the isotopes of uranium has been developed. The invention consists of a new process with essentially no moving parts. The new process is called the Ionized Vapor Process and is described in this report.

October performance of the plant production facilities was outstanding (915.2 tons U processed by Purex; 625.4 kg Pu separated by Redox/Purex). Redox processed three types of feed. Operation of incinerator furnace was resumed in Pu finishing processes. Capital cost estimates were prepared for several schemes for power reactor fuel reprocessing in Redox. Redox encased waste lines and line support system were found to be in good condition. H concentration in Redox dissolver off-gases occasionally exceeded lower flammable limits while sodium nitrate from high level waste storage tanks was used to suppress hydrogen.

This document summarizes the amounts of radioactive contamination discharged to ground from chemical separations and laboratory facilities through December 1965. Detailed data for individual disposal sites are presented on a month-to-month basis for the period of January through December 1965. Previous publications of this series are listed in the bibliography and may be referred to for specific information on measurements and radioactivity totals prior to January 1965. Several changes in crib nomenclature were made during 1965. These changes are noted on the individual tables so reference may be made to them in previous reports.

Heat discharged to the Columbia River in reactor cooling water is one of the more important pollutants from Hanford operations. The effect of this heat on river temperatures has been studied for several years, primarily because of the potential effect on the Columbia River fisheries. This document presents a summary of recent river temperature experience, with comparison data for a better perspective.

This document reports on: direct AEC sponsored programs (mainly Columbia River studies and exposure mechanisms), assistance to Douglas United Nuclear (production reactors), assistance to General Electric N-Reactor department, assistance to Isochem (processing), assistance to Hanford occupational health foundation, and technical assistance to Hanford Plant (environment, dosimetry).

Shipment of radioactive wastes in shielded transfer casks is a continuing practice between the 300 Area and the 200 Areas. However, the Waste Solidification Engineering Prototypes (WSEP) located in 324 Building, 300 Area, require the transfer of significant quantities of radioactive wastes. Two new 30-ton casks are being placed in service to accommodate the increased number of shipments. The purpose of this report is to document the design criteria, tests and calculations performed on the casks and modifications to the original cask design to insure its safe use. The design criteria was developed in January 1963 by an ad hoc committee comprised of representatives of the Chemical Processing Department, Hanford Laboratories, and Construction Engineering and Utilities of General Electric Company. The various tests, calculations and modifications of the cask were conducted by the Chemistry Department of Pacific Northwest Laboratory.

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This report provides preliminary design and specification information to fabricate a compact Weapons Effects Display System. The system is capable of calculating and displaying the effects of thermal flux, radiation, and blast pressure from a nuclear weapon. EG&G was asked to evaluate analog computer logic of an existing Weapons Effects Display System (WEDS), make the necessary changes and develop preliminary specifications to fabricate a more compacted system. Also included was to design any new circuits required to make the system more accurate, and design new circuits to provide additional features as specified by LRL. The WEDS consists of an analog computer to compute the effects of thermal flux, radiation and blast; a display system for displaying the pertinent digital information; and a map display system for presenting certain information on a map. The weapon effects are represented by equations taken from ``The Effects of Nuclear Weapons,`` by S. Glasstone, other nuclear weapon effects documents, and from individuals working in the nuclear weapon field. These equations are solved with the use of an analog computer. The equation results, along with pertinent input information, are displayed on a digital readout panel and as an overlay on a map display system. The compact …

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Direct AEC sponsored programs report that: a new mathematical simulation model to handle reactor effluent dispersion was started, final arrangements were concluded for the proposed test of the effectiveness of activated carbon for inorganic ion removal at the Richland Water Plant, the whole body counter used to measure the burdens of radionuclides in Richland school children is being calibrated for persons of small size and with different weight to height ratios; controlled intake of oysters that have accumulated zinc-65 is being used as one phase of this calibration. Assistance to Douglas United Nuclear is reported for missions 1, 10, 11, 13, and 14. Topics discussed here include: diffusion bonding of nickel-aluminium, PCTR experiments, code development, aluminium jacketed uranium fuel elements, and radiochemical analysis of radioarsenic in effluents. The General Electric N-Reactor department reports on:analysis and theoretical interpretation for ice and water, radiometallurgical examination on Al canned targets containing ceramic cores, inspection of irradiated zircaloy-2 clad fuel rods,resonance absorption cross section calculations, and visual inspection of Inconel steam generator tubes. Isochem reports on: dissolution of zircaloy studies, subcritical neutron interaction experiments, carbon monoxide disproportionation on exposure to bismuth oxide, dissolution rates of British alloys in nitric acid, Sr and rare earth …

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This report details activities of the N-Reactor Design Analysis Unit for the month of June 1966.

The purpose of this study is to provide budgetary data for modifying and monitoring the present water treatment process at B, C, D, KE, and KW reactor plants to effect a reduction in the activity of the reactor effluent water discharged to the Columbia River. The study is subdivided into three parts: facilities for sodium silicate addition at each reactor water plant, on-plant facilities for the manufacture and supply of sodium silicate, and instrumentation for monitoring the water treatment process for standardizing water quality in the water treatment plants. While the present concentrations of radionuclides discharged to the river are well below the maximum permissible concentrations established by the National Bureau of Standards, the proposed reduction is in the interest of providing greater protection from potential radiation exposure to people living downstream from the Hanford Plant where economically practicable.

Submitted herewith are source and special nuclear material composition of ending inventory reports for the month of November 1966. The depleted uranium, enriched uranium, plutonium, enriched lithium, U-233, normal uranium, neptunium 237, plutonium 238, deuterium, tritium, and thorium compositions are all broken down.

This report details 200 Area activities for the month of July 1966.

The Columbia River Cooling Program basically consists of effecting a reduction in river temperature at the Hanford site during the summer season. The implementation of this program in recent years has been accomplished through the selective and controlled discharge of waste water at Grand Coulee Dam. The purpose of this report is to describe the river cooling program conducted in CY-1965 by Facilities Engineering personnel, and present the program results.

Daily river temperature cycling has existed at reactor area river pumphouses from the beginning of operations. Of small account at first and due only to the daily air and solar radiation cycle, the phenomenon became significant with the initiation of daily river flow cycling at priest Rapids Dam to meet changing power generation requirements. The problem was compounded by the construction of the N reactor, placing a water intake and outfall at approximately half the previous distance between the K and D reactors. The decidedly non-uniform effluent distributions in the river at the shorter distances has caused apparent daily temperature swings at 181-D. This distribution was determined by the use of rhodamine B dye. Estimates of the relative contributions over a range of river flow to the temperature cycling at 181-N were made. A similar evaluation of the relative contributions at low river flow only at 181-D from K and N reactor operations has been requested by Douglas United Nuclear, Inc. This report is made to satisfy that request.

This document details activities of the Reactor Operation Branch during the months of January, 1966 through December, 1966.

This report discusses the objectives of the FFTF Fuel Handling and Radioactive Maintenance System Group which are: To remove and replace test components from the reactor core under a controlled environment to permit maximum acquisition and preservation of experimental data; to service and maintain the reactor core to enable maximum utilization of the irradiation capability of the facility; and to provide the radioactive maintenance capability consistent with the requirement for high plant factor and safety considerations.

The surveillance photography of underground nuclear detonations at NTS was engineered by EG&G to furnish the following information on unexpected venting: (1) establish when, with respect to zero time, the venting occurred; (2) record the point or points of emission of the venting gases; (3) show the colors, if any, of the venting gases; (4) the direction of cloud travel; and (5) dimensions and volume of the cloud as a function of time. In addition, the film records provide a color documentary film including a record of gross surface motion and a record of unexpected surface phenomenon (such as in Longshot). Surveillance coverage starts at minus 5 seconds and continues to plus 30 minutes. This report describes the typical photographic program setup, films used, and film processing.