Accelerated alpha particles from the Berkeley heavy-ion linear accelerator were used in a series of experiments designed to elucidate the conditions by which radiation can stimulate or modify nerve action in mammals. Single millisecond pulses in excess of 40,000 radsor pulse trains of less than 1 sec duration elicited the corneal blinking reflex when delivered to the cornea of unanesthetized rabbits. The lowest threshold dose was observed when the Bragg ionization peak was placed at 140 {mu} depth.

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.

Improvements in performance of products with nonmetallic engineered materials are obtained at the cost of increased complexity of product design, manufacture, and maintenance. NDE (nondestructive evaluation) techniques have been developed for verifying design models, identifying manufacturing flaws, and assessing service-related damage. This project involved developing a new NDE method that provides additional information; the sensor measures changes in an imposed electric field to obtain electrical impedance images of a component. Effective sensing volume and orientation of imposed electric field may be varied to optimize field interaction with the internal structure of a part. These interactions are combined into multidimensional impedance images that reflect variations in the mechanical geometry and internal structure of a part. Location of an impedance anomaly may be correlated with the location of a flaw.

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

A half reactor test was initiated at B Reactor on February 1, 1967, to determine whether the concentration of P{sup 32} and As{sup 76} in the reactor effluent water would be reduced by the addition of activated alumina in the water treatment process. This test was prompted by the reported effectiveness of activated alumina in sorption of phosphates when water flow is through a packed bed of this material. Although direct feed of material would not be expected to be as effective, testing of this possible approach appeared warranted. This report summarizes the results of this test. Samples taken from each effluent riser during reactor operation indicated no improvement in either As{sup 76} or P{sup 32} performance. This comparison is shown below with a complete tabulation of daily values included as Attachment 1.

As a part of the RAIL feasibility study, Operation Dorothe (March 1961) was conducted to determine if a liquid explosive could survive the acceleration of launch from a 155 mm howitzer. This operation was successful, although some structural difficulty was experienced with the test round (C-90). Upon completion of that exercise, it was decided to design a test round that could be used with the more viscous slurry-type explosives, and to fire several of these new rounds with inert filler prior to their use with slurry High Explosives (H.E.), precluding the difficulty previously experienced. The C-91 projectile, is a modified M107 H.E. round. It has been reduced in weight, equipped with an obturator, and provided with a large fill orifice. The rotating band has been altered to eliminate rotation. Internally, a plastic plug is used to control column height. A piston-type `O` ring seal prevents gun gas from reaching the interior to the projectile. Four of these projectiles were fired from a 155 mm howitzer at 15,500 g`s, plus. They survived not only the launch, but also impact and repeated ricochet in sand, gravel, and small rock. No leakage of the inert filler (glycerin) occurred. All rounds were destroyed with …

This monthly document provide source and special nuclear material composition of ending inventory reports for the month of April 1966.

This memorandum provides the minutes of the 7th meeting of the Livermore Vulnerability Committee. The Laboratory commitments in the Tapestry experiment, with particular reference to those experiments proposed in the Polaris MK 2 and the Minuteman MK 2 programs.

This report summarizes releases of radioactive waste to the environs of the Savannah River Plant during the calendar year 1965. Total quantities of radioactive waste released from plant startup through 1965 are also reported. Accuracy is not always implied to the degree indicated by the number of significant figures reported. Values were not rounded off, since data will be used in future cumulative summaries. No explanations are given for unusual releases; this information may be found in the Radiological and Environmental Sciences Division Monthly Reports and in the Semi- annual and Annual Environmental Monitoring Reports for 1965.

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The desirability of evaluating low assay plutonium-238 ({approximately}23% Pu-238) oxide was discussed with AEC personnel during a meeting at Germantown on July 6, 1967. In September, 1967 a sample of this material was furnished to Mound for evaluation. This evaluation was to be completed on a schedule which would not interfere with production of material for the SNAP programs, and was to include characterization of the oxide feed, and preparation and subsequent characterization of plasma-fired microspheres according to SNAP-27 procedures. Authorization to perform this work was received from DAO on September 1, 1967.

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 during May 1968.

This report presents the details of the activities of Douglas United Nuclear at the Hanford site during the month of April 1968.

This report presents details of the activities of Douglas United Nuclear at the Hanford site during the month of April 1967.

This report presents the details of the activities of Douglas United Nuclear at the Hanford site during the month of April 1969.

This report presents details of the status of special reactor process tube loadings for the month of May 1966.

This document, dated May 3, 1966, presents data from the zirconium tube sample evaluation program at the Hanford Reservation. Data presented includes: (1) operating history, (2) flow characteristics, (3) time in core, and (4) average temperature for numerous samples. The document consists entirely of data.

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The production reactors operated by Douglas United Nuclear, Inc., use treated Columbia River water as the coolant on a once through basis. Thus, radionuclides formed largely by the neutron activation of river salts are discharged to the river. One method of reducing the quality of radionuclides in the effluent is to increase the efficiency of parent isotope removal during the water treatment process. Prior to 1961 the water treatment process for preparing reactor coolant had been improved to the point that reactor quality coolant could be produced using an average alum flocculent feed rate of 6 ppM. Laboratory experiments carried out in 1959 and 1960 demonstrated that a markedly increased removal of parent isotopes resulted when alum feed rates in the neighborhood of 20 ppM were used. The results were confirmed by two half-plant tests of short duration in July, 1961, all water treatment plants began to use alum at a somewhat arbitrarily selected rate of 18 ppm. The practice Continues to date at all plants except at the K Reactors. The K Reactor alum feed has been limited to a nominal 15 ppM because of the high filtered water requirements. The use of the high alum feed rate did …

This document provides the report to the working committee of the fuel element development committee for small and K reactor production fuels. Topics discussed are: Uranium core production data; uranium specification; future planning -- five year R&D program; thoria development; heat treating; UO{sub 2} irradiation; and alternate process development.

Isotope production calculations have been prepared in the past to indicate present and potential reactor capability; however, the cases evaluated generally considered production of only one or possibly two isotopes. With the wide variety and potential demand for numerous isotopes, the question arises as to what the production capability would be if several isotopes were being produced at the same time. To study this problem in more detail and determine which of several alternates may be used in meeting production requirements, the Case Generator and Evaluator System has been developed. This document presents a production matrix and reviews the assumptions used to derive the matrix. This matrix should be useful in planning future CAGE isotope cases.

While the safety status of the Richland facilities has in the past been deemed adequate all aspects of nuclear technology have progressed and evolved including standards of nuclear safety. During FY 1968 the nuclear safety R&D efforts continued along the lines and at about the schedule predicted at the beginning of the year. Hence, the safety problems to be studied have been identified and the program seems well-defined. While some program modifications and changes in emphasis are to be expected, the five-year outline shown here is considered to be a reasonable representation of the safety work of highest priority to be studied.

Daily check of 325 stack filters on 5/9/66 revealed contamination released to the atmosphere within the operating area. Investigation indicated that about 0.4 Ci (mostly Ce-144) had been released as a result of steam jet transfer of some Ce-141-144 from a cask to a storage vault in 325-A. on 5/9/66. A further release of about 0.2 Ci vas indicated by survey of stack filters 5/12/66 following completion ot the transfer. Actions taken include vehicle smears, ground surveys around the 300 area fence line, and smears of the 329 loading dock. Daily check or 325 stack filters on 5-9-66 shoved an increase from about 8000 c/m (GM) Friday afternoon to about 450 mrads/hr (CP) Monday afternoon. Vehicle smears on 4-12 shift 5/9/66, ground surveys around the 300 Area fence line, and smears of the 329 loading dock have not revealed any contamination spread. Inventory in 325A (5/10/66) includes about 3 x 10{sup 6} Ci Ce-141-144 and about 3 x 10{sup 6} Ci Pm-147.