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Two techniques for the end-of-life shutdown of orbiting SNAP reactors are presented. One technique consists of two alternative methods for the destruction of the reactor core. This technique (and others) have been investigated during the past year. A second technique, uses a naturally occurring phenomena, which works on the principle of a low neutron absorbing nuclide decaying to a high neutron absorbing daughter (poison). The present design criteria for the latter technique is that only a small reduction in reactivity should occur during the mission lifetime with the slow build-up of poison eventually shutting down the reactor at some later date. Tritium, an isotope of hydrogen is presented as a parent that appears to meet all of the requirements for such an end-of-life shutdown device. The daughter, He/sup 3/ has a high neutron absorption cross section. The results of a preliminary study of the tritium device are presented.

Estimates are made relating radionuclide movement to ground water velocity as part of the safety program for a proposed experiment to detonate nuclear devices within the Tatum salt dome. The estimates are based on distribution coefficients obtained from laboratory studies. Core samples obtained from hydrologic test well HT-3, Tatum salt dome, Lamar County, Mississippi, were equilibrated with radionuclides in solutions simulating aquifer waters found in the area. The combinations of Cenozoic sand and silty clay, and quality of water of the area were studied and summarized. The distribution coefficients obtained for different radionuclides were tested and indicate retardation factors from 1.3 to 857 for the travel time of these radionuclides when compared to the travel time of water in the aquifer system. Laboratory results indicate that migration of any radioisotope inadvertently introduced to the aquifers in the vicinity of the dome as a result of proposed nuclear test explosions would be extremely slow. Revised estimates of the rate of dissolved radioisotope movement will be made on the basis of further laboratory studies utilizing chromatographic adsorption columns of 0.5 to 4.0 feet in length.

The instructions described in this procedure are typical of the operation of Test Cell A relative to the KIWI-B4A. Operation of Test Cell A relative to the NRX reactor will require modifications dictated by specific test requirements. Under NRX conditions, it will be the responsibility of the test cell manager to evaluate the capabilities of Test Cell A in terms of given test requirements and then set forth detailed checklists which will be compatible with the test requirements.

This manual covers the technology involved in the 200 Area process for the recovery of Np/sup 237/ from certain aqueous waste streams in the separations plants, for the recovery of NP/sup 237/ and Pu/sup 238/ from irradiated NpO/sub 2/-Al slugs and for the fabrication of NpO/sub 2/-Al slugs. The manual contains sections on the fundamental chemistry, the primary recovery of Np by ion exchange, the decontamination of Np by ion exchange, the processing of NpO/sub 2/-Al targets, the separation and purification of Np/sup 237/ and Pu/sup 238/, the finishing of Np, the preparation of NpO/sub 2/, the disposal of spent resin, and the safety aspects of the handling of hydrazine. The section on the fabrication of NpO/sub 2/-Al slugs will be added later. 76 refs., 22 figs.

This document summarizes the amounts of radioactive contamination discharged to ground from separations facilities through December 1962. Detailed data for individual disposal sites are presented on a month-to-month basis for the period of January through December 1962. Previous publications of this series are listed in the bibliography and may be referred to for specific information on measurements and radioactivity totals prior to December 1962. Tables list the major disposal sites in the 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. This same data is presented on a monthly basis for cribs still in use. Information is presented on the source of the waste stream and the settling facility if used. Isotopic data are included for disposal sites from which the waste was analyzed for specific contaminants. Estimates of contamination and volumes discharged to swamps are also included.

On September 13 and 14, 1962, 8.3 curies of iodine-131 were emitted from the Hanford Redox Plant at a rate of from 0.35 to 0.65 curies per hour for a period of approximately 18 hours. During the emission, the plume trajectories were plotted from meteorological data and samples were collected across the predicted plume trajectories at several altitudes and at distances up to 50 miles from the Plant. Filter, charcoal trap, and air samples were collected during the emission using aircraft; and caustic scrubber, vegetation, and milk samples were collected during and after the emission at selected ground stations in the usual manner. Appropriate background samples were collected before the test began. The data and conclusions are given in this report.

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

This document details activities of the Irradiation Processing Department during the month of August, 1958. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; Employee Relations Operation; and Financial Operation.

This report details activities of the N-Reactor Department during the month of August 1963.

This report, from the Chemical Processing Department at HAPO for September 1963, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations, facilities engineering; research; employee relations; weapons manufacturing operation; and power and crafts operation.

This report is applicable to the eight operating production reactors, B, C, D, DR, F, H, KE, and KW. It covers the following: operating parameter limitations; reactivity limitations; control and safety systems; reactor fuel loading; coolant requirements with irradiated fuel in reactor; reactor confinement; test facilities; code compliance; safety instrumentation and set points; and control criteria. Also discussed are administrative procedures for process control, training, audits and inspection, and reports and records.

This report, from the Chemical Processing Department at HAPO for May 1963, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations, facilities engineering; research; employee relations; weapons manufacturing operation; and power and crafts operation.

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

This document details activities of the irradiation processing department during the month of June, 1963. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; and Financial Operation.

This document details activities of the Irradiation Processing Department during the month of August, 1958. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; Employee Relations Operation; and Financial Operation.

This document details activities of the Irradiation Processing Department during the month of August, 1958. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; Employee Relations Operation; and Financial Operation.

This report, from the Chemical Processing Department at HAPO for June 1963, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations, facilities engineering; research; and employee relations; weapons manufacturing operation; and power and crafts operation.

During the 18-year history of Hanford operations, a high degree of safety has been provided at reasonable cost by the storage of high-activity liquid wastes in underground tanks, by the percolation of low-activity liquid wastes (principally water) through the soil to the ground water, and by the adsorption or filtration of radioactive materials from gaseous effluents prior to their discharge to the atmosphere. Studies of the Hanford area indicate that current practices could be continued almost indefinitely without jeopardizing environmental safety, provided the stored liquid wastes are periodically transferred to new tanks before the existing ones fail. In 1960, a Fission Product Recovery Program was prepared outlining a plan to meet the Atomic Energy Commission`s needs for isolated fission products. Emphasis was placed on developing processes for isolating selected fission products and on providing interim production capability for recovering the fission products of immediate interest. In 1961, development efforts were channeled almost exclusively toward meeting the immediate needs of the Commission for separated strontium-90 and cesium-137. During this time, it became increasingly evident that substantial economies could be realized, both in immediate development and subsequent operating efforts, if the separate fission product recovery and waste management programs were merged. The …

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

The objective of this test is to demonstrate and evaluate the design of the proposed N-Reactor fuel surface crud monitor to be used in the N Reactor.

About 298,000 OIIIN aluminum components were received from Harvey for evaluation after major steps were take in the vendor`s plant to upgrade product quality. This material met HAPO specifications and was comparable to Alcoa control components. Finished fuel elements (non-bumper and bumper) canned in the test and control components are tabulated by uranium core type and canning month. Non-destructive and destructive test data did not show any differences in clad fuel elements attributable to component quality. Irradiation status of non-bumper and bumper fuel elements clad in Harvey improved components as of Dec. 31, 1962, is tabulated, as is a summary of ruptures. It was recommended that Harvey Aluminum Co. be allowed to bit competitively on all future Al component orders except for the KVN and KVE component models.

The purpose of this January, 1963 report is to review existing Redox exhaust gas sampling equipment and to propose modifications and additions where appropriate. A study was conducted to determine what modifications, if any, should be made to the Redox exhaust gas sampling equipment to improve their present methods of monitoring for excessive amounts of fission product activity.

This document details the process of casting plutonium for the purpose of reducing the in-process inventory. The plutonium is cast, then rough machined to produce a storable form, then stored for the ten-day waiting period.