This report discusses the causes and effects of dust storms in the Tri-Cities area.

This document provides the monthly reports of the Production Reactor Branch for the months of January 1970 through October 1970.

In this semiannual issued the single pass reactor and water plant data are shown for the six-months` period July through December, 1969 together with data for the three preceding six-months` periods.

The intent of this report is to record, in one place, the significant historical events associated with the Single Pass Reactors from initial startup through December 1969. Significant events are chronologically listed in Section 1 and specific programs are summarized in Section 2.

The purpose of this document is to discuss the flowsheet and the related processing equipment with respect to nuclear and chemical safety. The analyses presented are based on equipment utilization and revised piping as outlined in the design criteria. Processing of thorium and uranium-233 in the Purex Plant can be accomplished within currently accepted levels of risk with respect to chemical and nuclear safety if minor instrumentation changes are made. Uranium-233 processing is limited to a rate of about 670 grams per hour by equipment capacities and criticality safety considerations. The major criticality prevention problems result from the potential accumulation of uranium-233 in a solvent phase in E-H4 (ICU concentrator), TK-J1 (IUC receiver), and TK-J21 (2AF pump tank). The same potential problems exist in TK-J5 (3AF pump tank) and TK-N1 (3BU receiver), but the probabilities of reaching a critical condition are not as great. In order to prevent the excessive accumulation of uranium-233 in any of these vessels by an extraction mechanism, it is necessary to maintain the uranium-233 and salting agent concentrations below the point at which a critical concentration of uranium-233 could be reached in a solvent phase.

This report provides reactor output production information for calendar year 1969.

This report details activities of the Pacific Northwest Laboratory`s Division of Production and Hanford Plant Assistance Programs for the month of December 1969.

This memorandum was written to provide additional technical basis for preparing Process Standards. Fuel surface-tube outlet temperature data is also provided. These data will help establish dichromate concentration and coolant pH based on the outlet coolant temperatures of the hottest reactor process tubes.

This report recommends developing a statistical model to characterize the three-dimensionall pattern of thermal plumes, It indicates the danger of drawing detailed conclusions on the basis of a small number of observations, and emphasizes the need for proper interpretation of empirical measurements, Two reports, on the discharges (1) from the Dresden Power Station into the Illinois River and (2) from Waukegan Station into-Lake Michigan are analyzed. In conclusion, a plan for interpretation of temperature measurements is recommended.

We suggest the establishment of several large generalized National Environmental Laboratories (NELs), each containing interacting groups of natural and social scientists, engineers, and information specialists. The field of action is the whole environment, both urban and rural, both present and future. By their organization and outlook, NELs would take a different cut across the fabric of environmental problems than has been possible hitherto. However, we must realize that NELs will not per se create instant Paradise; all we propose are instrumentalities designed to match the true scope of problems and perhaps stimulate a willing and charitable spirit. The tasks hitherto separately considered -- the retrospective ones of restoring and preserving the environment and the prospective one of future technology assessment -- are joined in NELS, because (1) environmental restoration and preservation involve prior and present technology decisions; assessment of future technology is the forward equivalent; (2) one of the activities tends to be conservationist, the other expansionist, and the two provide useful balance. We believe that these structures and roles are what is really required to implement both the recommendations of the National Academy of Sciences Panel on Technology Assessment, and the requirements implicit in the National Environmental Policy Act.

The complete annual R & D report consists of this summary and two companion reports, one from DUN which covers reactors and another from ARHCO which covers separations. These companion reports are listed in the set of references in the back of this summary.

Thoria is irradiated in the Hanford reactors for the production of U-233. The product quality is acutely sensitive to the control of the unseparable contaminant isotopes U-232 and U-238. Recent discussions between personnel of ARCHO and DUN indicate that product quality of a forthcoming separations campaign can be significantly enhanced by analysis of data for which we solicit your support. This letter describes the necessary background and the required analysis. Virgin thoria lots are processed to required transient impurity levels by the National Lead Company of Ohio. They are subsequently shipped to DUN identified by this virgin lot number and are accompanied by the transient impurity levels and U-238 contaminant levels based on statistical samples and analytic chemistry results. Virgin NOL thoria lots consist of various tonnages or fractions thereof, and two or three such lots are typically combined into a single DUN thoria element lot. By weighted averages, the U-238 contaminant level of DUN thoria lots is thus accurately known. The range of U-238 contaminant in any given DUN lot was further controlled by establishing three categories, A, B, and C, with U-238 ranges of 0-1.99, 2.0-3.3, and 3.4-5.0, respectively, on a thoria basis. Thus when a DUN lot …

An earlier attempt to demonstrate our capability to produce medical-grade Pu-238 was discontinued because of unanticipated growth of the neptunium oxide-graphite matrix targets. It has since been established through a subsequent test discharged in February that the graphite matrix targets failed because of inadequate provisions for target expansion and not because of inadequacies in the graphite matrix targets could be used successfully to produce low impurity plutonium. A report on the graphite matrix growth analysis test will be completed by mid-June 1970.

In FY-1970, the former ten missions which had existed under the Richland Five-Year 02 Research and Development Program were consolidated into four program areas as follows: Basic Production; Product Flexibility; Environmental and Regulatory Technology; and Waste Management. Each program area has included one or more separate distinct programs, some of which were basic to sustaining and improving production operations while others were directed to broadening plant versatility for producing potentially marketable products. Midway through FY-1970, the shutdown of KW Reactor with subsequent curtailment of funding resulted in a substantial reduction in the level of effort in both of these directions. Consequently, during the balance of FY-1970 improvement effort has primarily been concentrated on N Reactor operation, and plant versatility effort was virtually stopped. The research and development reported herein represents progress made during the period January 1, 1970, through May 30, 1970, and, contrary to recent annual and semiannual reports, includes only that work primarily funded with 02 R&D funds. No process technology funded activities are included, these being reported regularly in Douglas United Nuclear Monthly Reports.

The scope of this research program is to study the structure of nuclei and the properties of the nuclear force, in particular its symmetries, using the tools of nuclear spectroscopy. To this end a unique set of instruments is at disposal, including curve crystal diffraction monochromators, high resolution beta spectrometers and Moessbauer spectrometers.

The EPR spectrum of single ions of /sup 143/Nd in a crystal of Neodymium Ethyl Sulfate, predominantly of isotope /sup 142/Nd, was observed under condition of very high Boltzmann factor, i.e., high fields and low temperatures. It was found that the interactions with neighboring ions displaced the hyperfine lines from uniform spacing, and that by measuring the deviation it was possible to find the nearest neighbor interaction. The departure from a purely magnetic dipolar interaction is smaller than previous measurements would indicate. It was found that EPR resonance at large values of H/T in magnetically concentrated crystals can yield accurate values of spin-spin interactions.

A study was performed of the correlation between fuel form stability and exposure environment of (temperature and atmosphere). 100% Tm/sub 2/O/sub 3/, 80% Tm/sub 2/O/sub 3//20% Yb/sub 2/O/sub 3/ and 100% Yb/sub 2/O/sub 3/ wafers were subjected to air, dynamic vacuum and static vacuum at temperatures to 2000/sup 0/C for times to 100 hours. Results showed the Tm/sub 2/O/sub 3//Yb/sub 2/O/sub 3/ cubic structure to be unaffected by elemental levels of iron, aluminum, magnesium and silicon and unaffected by the environmental conditions imposed on the wafers. A second task emphasized the optimization of the thermal, mechanical and chemical stability of Tm/sub 2/O/sub 3/ fuel forms. Enhancement was sought through process variable optimization and the addition of metal oxides to Tm/sub 2/O/sub 3/. CaO, TiO/sub 2/ and Al/sub 2/O/sub 3/ were added to form a grain boundary precipitate to control fines generation. The presence of 1% additive was inadequate to depress the melting point of Tm/sub 2/O/sub 3/ or to change the cubic crystalline structure of Tm/sub 2/O/sub 3//Yb/sub 2/O/sub 3/. Tm/sub 2/O/sub 3//Yb/sub 2/O/sub 3/ wafers containing CaO developed a grain boundary phase that improved the resistance to fines generation. The presence of Yb/sub 2/O/sub 3/ did not appear to …

None

A feasibility study was performed on encapsulated thulium-170 as an isotopic fuel for operation at temperatures to 1500/sup 0/C for 180 days. Effects of various combinations of fueled capsule design parameters were evaluated and compard to experimental data. A computer program was developed to predict dose rates through various thicknesses of aluminum, stainless steel, lead, tungsten and depleted uranium absorbers using thermoluminescent dosimetry techniques for experimental corroboration. A procedure for preparing Tm/sub 2/O/sub 3//Yb/sub 2/O/sub 3/ composites was evaluated. Melting points and solid-state transformations to the melting point of a composition series 100% Tm/sub 2/O/sub 3/ - 100% Yb/sub 2/O/sub 3/ were determined. The Tm/sub 2/O/sub 3/ - 100% Yb/sub 2/O/sub 3/ system remains cubic to the melting point. Solid-state reaction of candidate containment materials (Hastelloy X, Hastelloy C-276, Haynes-25, T-111, TZM, tungsten and zirconium) with Tm/sub 2/O/sub 3//Yb/sub 2/O/sub 3/ were studied. Containment for times to 10,000 hours at 1600/sup 0/C and to 500 hours at 2000/sup 0/C were demonstrated.

Radiation dose rates from three thulium-170 oxide sources (20.7, 10.0 and 5.0 thermal watts) were measured through three thicknesses (1/4, 1/2 and 1 inch) of absorber by thermoluminescent dosimetry techniques. Absorber materials used were aluminium, stainless steel, lead, tungsten and depleted uranium. Resultant radiation doses were measured at 19 and 100 cm. Comparison of theoretical dose rates calculated by computer with measured dose rates validated the calculation technique for lead, tungsten and uranium absorbers but not for aluminum and stainless steel. Use of infinite medium build-up factors (B/sub infinity/) was thus validated in computation of dose rates for lead, tungsten and uranium absorbers; use of B/sub infinity/ in computation of dose rates for aluminum and stainless steel absorbers overestimated dose rates vis-a-vis experimentally determined dose rates by an approximate factor of 2.

Proton hole states in the 1f/sub 7/2/ nuclei /sup 46/Ti, /sup 54/Fe, /sup 56/Fe, /sup 58/Ni, and /sup 60/Ni have been studied with the (p,2p) reaction with 46-MeV protons. The measured binding energies and angular correlations are consistent with the binding energies and orbital angular momentum assignments (1f/sub 7/2/, 2s/sub 1/2/, and 1d/sub 3/2/) obtained from proton pick-up reactions. 3 figures, 1 table.

The purpose of this analysis is to determine if the two piece flat head closure concept presently being considered by INC for the LOFT reactor vessel will meet the structural and fatigue requirements of Article 4 of Section III, ''Nuclear Vessels,'' of the ASME Boiler and Pressure Vessel Code, for the anticipated LOFT operational requirements. The analyses performed include stress analyses based on classical stress analysis methods and proven computer programs, fatigue analyses based on the fatigue criteria of Section III of the Code, and thermal analyses based on multi-dimensional computer programs.

An analytical parametric study was made of an infinitely long, cylindrical fuel capsule containing thulia (Tm/sub 2//sup 170/O/sub 3/) encapsulated in two different physical forms and in two different liner configurations. Diameters of wafers maintained at 0.060 inch thickness were varied between 0.6 and 3.0 inches. Radial temperature profiles were determined for thulia power densities ranging from 8 to 24 W/cc and fuel capsule surface temperatures ranging from 1000 to 2732/sup 0/F. Hastelloy-X, Haynes-25, T-222, tungsten, platinum and molybdenum are the liner materials investigated. Methods of calculation, (including computer codes), assumptions used, error analyses and results are presented and discussed.

This document presents a Preliminary Measurement Data Requirement List (MDRL), Data Item C-103, for the NERVA E-1 Ground Test Engine. The MDRL presents 628 parameters/channels for non-nuclear engine hardware. An estimate of 472 parameters/channels for NSS hardware was made jointly by ANSC/WANL, since detailed NSS requirements have not been defined to date. Therefore, the total engine parameters/channels is 1100. This is based on the ANSC Design Baseline Flight Engine defined by drawings 1137400C and 1137401D, since a baseline ground test engine has not yet been defined. This submittal is an extra scope item not included in the CY 1970 Contractual Work Statements, but will be used in conjunction with the Preliminary NERVA Operational Flight Engine MDRL, dated September 1970 which was in compliance with the Project 117 CY 1970 Contractual Work Statement paragraph f5d. This document provides initial definition of measurement system design requirements to provide direction for instrumentation and wiring harness design and to provide a baseline for performance of Measurement System design and analysis activities related to the ground test engines.