The macroreticular anion exchange resin, Amberlite IRA-900-OH, and an experimental resin from Ionac Chemical Company were irradiated by a /sup 60/Co source to doses of 5 x 10/sup 7/ rad and 10/sup 8/ rad. These doses approximate or exceed the dose encountered by the deionizer resins in 100-Area service. The loss in exchange capacity and the volume changes of Amberlite IRA-900 on irradiation were similar to those found previously for Amberlite IRA-400. The Ionac experimental resin, which had a considerably lower initial exchange capacity, likewise was not stable to radiation. It is concluded that Amberlite IRA-900 offers no advantage over Amberlite IRA-400 for 100-Area purification service. Since there is little justification for further evaluation of macroreticular resin for 100-Area use, the present work completes RTA-893-R.

A bibliography on pion-pion interactions is presented. The 241 references are those available through November 7, 1961. A chronological listing is given together with excerpts or comments. In another part the references are grouped according to subject. An author index is included. (M.C.G.)

This report describes the use of a target containing polarized protons in a particle-scattering experiment. Positive pions of 246-MeV kinetic energy were scattered from the polarized protons. The parameter P that was measured is equivalent to that determined by analyzing the recoil-proton polarization in scattering from an unpolarized target. It has been measured to a higher accuracy than heretofore achieved in pion-proton scattering, at an energy and at angles inconvenient for double-scattering techniques.

About 70,000 pictures of 2.45-GeV/c K{sup -}-p interactions have been obtained in the present 72-inch hydrogen bubble-chamber experiment. Approximately 24,000 events of all topologies except 1-, 2-, and 3-prong events have been measured, and 50% have been remeasured. They report here on a study of the production of known resonances in the reactions: (1) K{sup -} + p {yields} {Lambda} + {pi}{sup +} + {pi}{sup -}; (2) K{sup -} + p {yields} {Lambda} + {pi}{sup +} + {pi}{sup 0} + {pi}{sup -}. The cross section for production and number of events in reactions (1) and (2) are given in Table I.

None

The April 7, 1962 criticality accident involving human exposures was the first to have occurred in any production facility at Hanford. The accidental nuclear excursion did not result in any mechanical damage or spread of contamination. Three employees received over-exposure to gamma and neutron radiation. None were fatally exposed and in each case the over-exposure was recognized promptly. Following an initial period of medical observation and testing, the men were released to work. They continued to be followed clinically. Clinical studies performed were hematological procedures including leukocyte chromosome aberrations, morphologically aberrant blood cells, bone marrow evaluations, blood chemistry determinations, amino acid excretion studies, seminal fluid, urinary gonadotropins and estrogen excretion studies, testicular biopsies and crystalline lens examinations. These studies, along with a brief description of the accident and of the dosimetry, are summarized in this report by those participating in the studies. In view of the dose ranges received in these cases, both the negative and positive findings are considered to be of unusual interest due to the lack of knowledge of effects following human exposures at these levels.

None

The altitudes and times of ablation have been determined for the SNAP-10A, SS-316 vessel wall reentering under various conditions. The results are confined to one typical location on the reactor and to one typical reentry trajectory. The location is the side wall of the vessel and the trajectory is the one used in NAA-SR-8303.

The results are presented of a parameter survey of the properties and mechanisms affecting the reentry ablation of SNAP fuel particles. The following properties and mechanisms were studied: aerodynamic heating, oxidation, oxide vaporization, metal vaporization, particle emissivity, specific heat, density, velocity, and initial size. These studies were made for particle release altitudes ranging from 170,000 to 228,000 feet.

This document details activities of the N-Reactor Department during the month of October 1963.

Fission product measurements in the PRTR primary D{sub 2}O and helium systems during the startup tests in May 1961, showed the presence of a defective fuel elements(s). Reactor operation was discontinued during the latter part of May and during June for reactor maintenance and fuel element inspection. On resumption of operation on July 1, a sampling and analytical program was initiated to study the radioisotope concentrations resulting from this defective element(s) which were present in the primary D{sub 2}O and helium systems during the various phases of reactor operation. The data accumulated during this study are to serve as background information in future fuel element rupture identification and location studies as well as serving as a guide in setting up the rupture monitor for the individual tubes of the PRTR reactor. A summary of the analytical results from this study and their theoretical interpretation is presented in this paper.

This document details activities of the N-Reactor Department during the month of January 1964.

This document details activities of the N-Reactor Department during the month of September 1963.

This report is a comparison of findings from the twelve two-ton test batches irradiated in the KE and H reactors with respect to reactor plutonium yield predictions. Included are plans for the application of these findings to improve the accuracy of plutonium yield equations used for Hanford product accountability.

During fuel element assembly, a dip-brazing process., the aluminum can which is ultimately a jacket for a uranium core is protected from the molten AlSi solution by a steel sleeve. Once the can is inserted into the sleeve and thermal expansion is complete, upset metal rings prevent molten AlSi from flowing between the can and sleeve, a situation that warrants rejection. Passage of molten solution beyond upset metal to a point on the can wall not removed during the subsequent facing operation is called an ``AlSi Slopover`` or ``Slop.`` With discovery of a solution which would mask 8001-F aluminum alloy from molten AlSi, efforts were directed towards using this solution to eliminate AlSi stopovers. With proper application and control, PWR 125 proved that cans coated with PX1288 did not alloy AlSi in the molten state to pass beyond the upset metal region during canning. Since this material has been used on total production, the CPR rate has been greatly reduced. Percentage of rejects attributable to the CPR category is 0.5%.

Assistance was requested in reviewing and comparing certain measures that could be effected immediately with little capital cost to render the plant less vulnerable to self-destruction in case of a war situation that made it impossible to man the water plants. Several courses of action have been considered with the assumptions detailed.

This document details activities of the N-Reactor Department during the month of May 1963.

This report details activities of the N-Reactor Department during the month of April 1964.

Information is presented on current reactor fuel development (uranium core production data, fuel performance, AlSi process development, and alternate process development) and NPR fuel development (fuel production status, KER loop testing, and process development).

This report is a compilation of available data on ruptures that have occurred since KER start-up. Some of the data presented in this report are inconclusive, but are reported to insure a complete summary of all potential and confirmed ruptures.

While it is obvious that a power surge in a Hanford reactor will result in temperature increases of the fuel and water, it is also true that there will be changes in the coolant flow rate and the pressures in each process tube. In addition, if the power increase is of sufficient magnitude, a self-induced flow reduction will occur as a result of pressure changes due to boiling within the process tube. The relations between power, temperatures, flow and pressure following a power surge are difficult to calculate with precise accuracy. However, a knowledge of these relations is important for incorporation with physics considerations to allow prediction of maximum fuel temperatures following a power surge and to specify detection instrumentation for proper reactor control. Fairly precise information of temperatures, flow, and pressure in a single process tube following a power surge can be obtained using an electrically heated model in the 189-D heat transfer laboratory. Obtaining such information for all possible conditions and for all the Hanford reactors would be a fairly large job. However, two cases were run with an existing full scale electrically heated model of a single column of fuel elements in a C reactor overbore process …

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.

G. A. Last reports on metallic uranium irradiation studies: cluster irradiations, tubular element irradiations, MTR-ETR irradiations on NaK capsules, effects of pH on film formation, fuel performance, effect of pressure on swelling, and ETR rupture tests. R. D. Leggett reports on irradiation program, and pore site and distribution in irradiated uranium.

To run a second BPA outage test at the DR-Reactor using the same instrumentation and procedure but increasing the trip-out level fro 800 MW up to a maximum of 1200 MW.