The Richland 02 Five-Year Process Development Program has been divided into 10 missions. The missions by title were: Basic Production; Coproduct; Transplutonium; Pu-238; Other Isotopes; Enriched Fuel Processing Target Space Enhancement Nuclear Safety; Waste Management; and Columbia River Studies. Although in general most of the same efforts are incorporated, the mission concept is being dropped, and the following designations for programs have been adopted: Basic Production; Product Flexibility; Waste Management; and Environmental and Regulatory Technology. The programs to be carried out are described in this document. The reports are brief, but as per AEC-RL instructions, additional details can be found in the annual documents issued at the beginning of the fiscal year and the semiannual research and development reports issued in January of each year. In some instances it is anticipated that the level of funding will be supplemented by process technology funds.

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This report itemizes the irradiations performed by Testing and Irradiation Services for Battelle-Northwest. It lists the material being irradiated, awaiting disposition and material shipped during the report period.

A review of the present state-of-the-art in the areas of gas chromatography, radiochemical counting and inert cover gas sampling reveals that : 1, The chromatographic approach to fuel failure detection and locatlon is technically feasible and holds promise of having distinct advantages over existing methods. 2, Considerable knowledge which is directly applicable to the problem exists and therefore the research and development costs required will be modest, 3. Existfng knowledge indicates that there is a high probability that a successful failed fuel locator can be constructed based on gas chromatographic separation of the rare gases followed by radiochemical counting . 4, Sample selection and conditioning will pose a major problem in any failure location system which is based on the measurement of fission gas concentration in individual cover gas channels.

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This document is the March 1969 monthly report for Hanford Categories C-57 and C-65. It contains information on reactor plant operation, fuel and target fabrication, technical activities, and irradation services at the Hanford Production and Irradiation reactors. The document features a discussion of the 300 area environmental control program.

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Primary, secondary, and thermal stresses were calculated and evaluated for the SNAP-8 developmental reactor fuel element cladding. The effects of fabrication and assembly stresses, as well as test and operational stresses were included in the analysis. With the assumption that fuel-swelling-induced stresses are nil, the analytical results indicate that the cladding assembly is structurally adequate for the proposed operation.

The concept of reactor effluent disposal to ground in infiltration trenches was proposed by Nelson and Alkire in 1963. At that time the available data indicated that radionuclide infiltration rates were probably adequate for trench disposal and that decontamination factors of 10 to 100 should be obtainable. Field tests at 100-F Area 1965 and 100-D Area 1967 have indicated that the infiltration rates are adequate and DF`s of from 2.5 for {sup 51}Cr to 7276 for {sup 65}Zn were obtained during the 100-D test. The purpose of this report is to present the results and interpretations of data from studies conducted over a reactor coolant effluent disposal test site. Data presented in this report were collected over the 100-C Area test in which a significant percentage of the reactor coolant effluent was disposed to an existing trench for a five-month period. Results of infrared thermal surveys and ground water temperature and potential measurements collected during this test are presented.

This report itemizes the irradiations performed by Testing and Irradiation Services for Battelle-Northwest. It lists the material being irradiated, awaiting disposition and material shipped during the report period.

This report presents details of the status of special reactor process tube loadings for the month of April 1969.

This report was prepared by Battelle-Northwest under Contract No. AT(4S-l)-1830 for the Atomic Energy Commission, Division of Reactor Development and Technology, to summarize technical progress made in the Fast Flux Test Facility Program during March 1969.

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A semiautomatic grinder was designed and built at Mound Laboratory to grind molded plastic detonator heads to close tolerances. It uses a vertical spindle, dry grinding technique to decrease grinding time of some diallyl phthalate (DAP) detonator heads with wire inserts and to eliminate the problem of error in repeatability which is characteristic of the manual grinding process. The semiautomatic grinder is essentially air-operated with electrical control and was primarily designed using standard components for ease of manufacture and maintenance. As development of the semiautomatic grinder progressed, DAP detonator heads with wire inserts ground using the manual surface grinder were evaluated along with the same type of detonator heads ground using the semiautomatiac grinder. Also, a time study was conducted to determine the cost savings of grinding miniature DAP detonator heads with wire inserts using the semiautomatic grinder. Inspection and analytical results and radiographic sections of ground detonator head surfaces from each grinding technique indicated that the semiautomatic grinding technique provides acceptable ground DAP detonator heads with wire inserts at a cost savings of 83.5% and a significant reduction in grinding time.

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The effects of several perturbations are investigated. They are: modification of the shape of a pole, error excitation, displacement, and rotation of a pole. The effects are described in terms of changes of multipole coefficients. General relationships between some of these coefficients are described, and formulae are derived that allow their calculation for a model 2N-pole magnet. Numerical values of these coefficients are given for a quadrupole, sextupole, and octupole.

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