Data taken on radiation traverse of the Mark 1 control rod were analyzed. Future radiation levels for all SRE control and safety rods were predicted from this. The shielding necessary to ship a complete rod and that necessary to protect a person doing maintenance work on these rods were calculated. The unshielded gamma dose rate 1 cm from the surface of the most highly activated portion of the control rod was calculated to be 5.0 x 10/sup 4/ r/hr 14 days after shutdown following an extended power run of 90 days duration. (M.C.G.)

Several theories of metal creep and radiation damage are studied, in order to determine whether creep rates under various conditions of irradiation can be predicted theoretically. It is found that if the creep is of the recovery type, and if the diffusion coefficient for radiationinduced vacancies is large enough, creep rates may be increased within a limited temperature range. Otherwise, radiation has no effect on creep rates. (T.F.H.)

Geologic and radiometric investigations of the CuzcoAyaviri region in southern Peru were made in a search for geologic features or structures which might be favorable for the occurrence of uranium. Outcrops consist of Lower Paleozoic sedimentary and metamorphic rocks; Permian to Carboniferous volcanic flows, tuffs, breccia and agglomerate, together with sedimentary rocks; and Cretaceous and sedimentary rocks. Cretaceous to Tertiary igneous rocks are acidic intrusives and extrusive rhyolite, dacite and trachyte. Tertiary to Quaternary volcanic tuffs, breccias and agglomerates are also present. Although no anomalous radioactivity was observed, favorable geologic features for the occurrence of uranium were noted at two localities. (auth)

Static overpressure and dynamic pressure versus time over surfaces processing different physical properties were measured on two tower shots, 6 and 12. On Shot 12, three surfaces were provided: the natural desert, a water surface consisting of a flooded area, and an asphalt surface. On Shot 6, desert and asphalt areas only were available. There were 123 channels of instrumentation installed for Shot 12, and 24 for Shot 6. From the data, a system of wave-form classification was devised for overpressure and dynamic-pressure- versus-time measurements. Incorporation of this system into data analysios indicates that it is possible for an ideal peak pressure to be identified with a nonideal wave form. Introducing both variables, wave form and peak pressure, into analyses reduces ambiguioties associoated with comparing results of different nuclear tests. The data show the effect of the nature of the surface upon airblast phenomena from a nuclear explosion. The effects of surface conditions upon shock phenomena are made more understandable by a review of temperature computatioons, using shock wave parameters in addition to an analysis based upon the arrioval time of the thermal pulse. A phenomenological discussion of precursor formation is presented, and comparisons are made using data from all …

In 1957 a radiometric examination of rock outcrops in the Ayabaca and Huancabamba areas of northwestern Peru was made in conjunction with a geologic search for structures favorable for the occurrence of uranium minerals. No anomalous radioactivity was detected, and the geologic setting is believed to be generally unfavorable for uranium mineralization. (auth)

This document contains information on special filter samples of Hanford Process Effluent Gases. The filters are identified by code numbers only. Included in this paper are tables explaining the sample code numbers, sampling locations, and process conditions during sampling. Also included, is a copy of the monthly and quarterly average results for Regional Monitoring's routine stack program for the fourth quarter of 1956.

Data were obtained to evaluate the attenuation of photons, emitted from a fallout field, due to the surface roughness of the terrain. A study was made to determine the effect of the shot tower on the fallout material. Particles for comparison were collected from two detonations of equal scaled height, one tower supported and the other balloon supported. Data on time-dependent phenomena were recorded, as were physical characteristics of the fallout material. The use of small balloons as instrument platforms and a new fallout collector were evaluated for field use. No conclusions or recommendations can be made at this time.

This report has been prepared in answer to the request from the AEC contained in the letter of October 1, 1957, from A. T. Gifford, HOO to A. B. Greninger. As requested, the report is of a summary nature and a more complete discussion of many of the points considered will be found in the references listed. The report is directed primarily at C reactor but some discussion of the other reactors is also included. A description of the proposed utilization of I E slugs in C reactor together with the associated power increase schedule is presented below. The reasons for changing to the I E element are presented together with a comparison of solid and I E slugs in the C reactor. The changes being made in C reactor under CG 600 are described. The operational characteristics of the C reactor using solid and I E elements are compared and finally the nuclear safety status of all of the Hanford reactors assuming I E loadings is reviewed.

This report describes the operation of the fuels preparation department for the month of August, 1957. Manufacturing, employee relations, process development, plant improvements, and financial operations are described.

An engineering flowsheet has been prepared for the conversion of an aqueous slurry of cesium-zinc-ferrocyanide into a dry cesium chloride product by the calcination process. Flowsheet No. 1 defines a six-step batch-type calcination operation for processing the slurry into a dry powder for offsite shipment in bulk containers. Some of the advantages to this process are as follows: Product losses are expected to be small, estimated to be less than 0.03 percent; the equipment required to process a given number of curies per batch appears to be relatively small, compact, and simple; the process does not impose severe requirements for materials of construction; and requirements for process control and instrumentation are expected to be simple. There are two disadvantages to this process. First, the cesium-zinc-ferrocyanide precipitate is not considered economically filterable, hence, the separation of solids from liquids is encumbered. Second, the process, as outlined, if potentially hazardous because of the possible nitrate carry-over with the influent slurry. This nitrate may cause a rapid reaction in the calcination step. It is concluded that this flowsheet offers a satisfactory scheme for isolating radiocesium if the process is modified to preclude the possibility of nitrates or other unwanted oxidants from reaching the …

The pilot charging of I & E fuel elements has been implemented at C-Reactor under Production Test IP-19-A. It was necessary to provide adequate tube protection against flow interruption by establishing proper trip setting on the Panellit pressure gauges. the administration of these Panellit trip settings is done by trip-before- boiling tube outlet temperature limits, which are similar in principle to the current instability limits. Trip-before-boiling limits for C-Reactor I & E fuel elements loadings are presented in this document.

This report is written to provide information concerning the status of the Hot Semiworks facility as it is placed in stand-by on July 1, 1957. The plant was constructed in 1951 and early 1952. It vas operated on Redox type investigations until the last of 1953. The plant was then converted to the Purex flowsheet under Project CA 513 D. Operations on the Purex type investigations were started in early 1955 and continued until early in 1956. At that time a maintenance program for plant improvement and repair was initiated. This program was completed on July 1, 1957. Statements are contained in this report which pertain to the present status of physical equipment and facilities and the adequacy, operating experience, recommendations for improvement, previous work, and future considerations of the plant. However, the primary intent of the report is to provide pertinent information to personnel associated with a future start-up. For this reason, certain parts of the report are quite detailed. Only statements concerning the existing or previous state of the facility and equipment are factual. Others are opinions or experiences of plant operating personnel. Emphasis has also been placed on the faults encountered rather than the good features of …

This document summaries the amounts of radioactive contamination discharged to ground from separation facilities through December 1956. Detailed data for individual disposal sites is presented on a month basis for the period of July through December 1956. Previous publications of this series may be referred to for specific information on measurements and radioactivity totals prior to July 1956. Tables I and II list the major disposal sites in separation facilities, total volume of waste discharged to each location, and the gross amounts of plutonium and beta particle emitters discharged to ground since startup. Tables III through XXXVI present this same data on a month to month basis and also include information on the source of the waste stream and the settling facility used. Isotopic data are included for all disposal sites from which the waste was analyzed for specific contaminants. Estimates of contamination and volumes discharged to the swamps are also included.

This is the monthly report for the Hanford Laboratories Operation, September, 1957. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

This report describes the operation of the fuels preparation department for the month of September, 1957. Manufacturing employee relations, process development, plant improvements and financial operations are described.

The loss of cooling water from a Hanford production reactor has serious implications because of the accompanying reactivity transient. It is imperative that the time dependence of this transient be determined in order to evaluate properly some aspects of reactor safety. A previous experiment has been done however it was primarily in the nature of an exploratory run leading to the present experiment. The experiments described below cover a much wider range of conditions and have been used as a basis for analog computations to determine the adequacy of the present safety systems from a response standpoint.

Since the installation of Ball 3X equipment on the older reactors, several inadvertent ball drops have been experienced, many of which have required considerable recovery time. Furthermore, it is very probable that these recovery times be significantly increased subsequent to the proposed installation of air accelerated vertical safety rods. Because of this, interest has been expressed by reactor operations personnel toward provision of a ball recovery system which would substantially reduce these outages.

Equipment required to provide production capacity of 525 tons per month of I & E fuel elements ``O,`` ``C,`` and ``K`` sizes in the 313 Building is specified in this document.

For some time, it has been considered that cycling natural uranium fuel elements through the {alpha}-{beta} transformation point (approx. 662 C) is a contributing factor in split type ruptures. This hypothesis is based upon the fact that the transition temperature, a one percent increase in volume occurs. It is reasoned that as the uranium hardens under irradiation, it becomes progressively less able to adjust to the severe stresses imposed by the volume change as the material cycles through the {alpha}-{beta} transformation point. Failure finally occurs by a splitting of the core. The IPD is now interested in evaluating some of the effects of reactor operation upon fuel performance. It appears that the life of solid fuel elements may be prolonged if sudden changes in reactor operation can be minimized. It is the purpose of this report to bring to the attention of FPD management the new ideas being developed in the IPD on split type failures and to point out the effect such thinking may have on future fuel element development activities. Based on a discussion with personnel in PID, there is reasonable hope that the performance of solid fuel elements will not be limited by the {alpha}-{beta} transformation, and …

This document details activities of the Irradiation Processing Department for the month of February 1957. (FI)

The September, 1957 monthly report for the Chemical Processing Department of the Hanford Atomic Products Operation includes information regarding research and engineering efforts with respect to the Purex and Redox process technology. Also discussed is the production operation, finished product operation, power and general maintenance, financial operation, engineering and research operations, and employee operation.

This section of the Engineering-and Design History presents a comprehensive account of the planning and extensive evaluation of the problems involved in reaching basic decisions for the design and installation of power facilities at the Savannah River Plant. The problems were complicated by the urgency of Pro. viding early start-up of facilities at a time when critical material shortages were acute, combined with basic requirements for reliable operation and unusual degrees of flexibility to meet a variety of production demands. Part I describes in detail the steam and water facilities, alternative schemes, and other considerations which were evaluated as a prelude to the final design of equipment and facilities. Included are discussions relating to steam boiler installations, electric power generation, diesel engine plants, mater supply for cooling, process and domestic use, and the numerous water treatment procedures employed for specific application. A comprehensive description of the development and design of electric power facilities is presented in Part II of this volume.

None

This bibliography is a compilation of reports on production tests performed in the 300 Area from May 1944 to February 1957. It includes all tests covering engineering and physics experiments in the Hanford Test Reactor development; fabrication and subsequent irradiation of fuel elements and melt plant (slug fabrication) procedures. Subject, author and report number indexes are included. Addendum 1 gives the reactor production test number under which the fuel elements were irradiated.