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Abstract: This report, intended as a working document, contains analytic representations and analog models of the Hallam Nuclear Power Facility as used in studies of the Control and Protection Systems.

Abstract: Design charts and systematic design forms are presented for simplified calculations to check the number of convolutions and thickness required to limit the deflection and pressure stress range in three types of bellows.

This report addresses the Application of Snap Reactor Power Systems to Manned Space Stations.

Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.

A description of the fuel elements for SNAP 1OA, SNAP 2, and SNAP 8 was presented at the 17th High Temperature Fuels Committee Meeting, and some of the experimental results obtained in the program were reviewed at the last meeting. This report present some of the more recent detailed findings of the research and development effort on SNAP fuel element materials.

Activities for each of the following departments are discussed in this report: Reactor and Materials Technology Dept.; Physics and Instruments Dept.; Chemistry Dept.; Biology Dept.; Applied Mathematics Dept.; Radiation Protection Dept.; and the Test Reactor and Engineering Services Dept.. Activities are in support of Hanford reactors (production reactors, N-reactor, PRTR reactor, etc) and reprocessing and radioactive waste management efforts at Hanford.

Abstract: In fulfillment of the general objective of developing information on two-phase flow required in the safety evaluation of sodium cooled reactors, pool and forced-convection boiling of sodium were studied both experimentally and analytically.

This report presents the results of a recent analysis to determine if there is a practical method for using carbon dioxide for pH adjustment at the 100-K Reactors. Carbon dioxide could be recovered from the boiler stack gas and introduced into the K Reactor process water. The approximately $240,000 installation cost would be repaid in about one year by the reduction of sulfuric acid costs. The proposed system would consist of a blower, a purification system, and a distribution system for conducting the gas from the boiler house stacks to spargers in the process water clearwells. The blower would draw gas from the boiler stacks and then blow it successively through the purification system and the distribution system. The purified gas, consisting primarily of carbon dioxide, oxygen, and nitrogen, would bubble up through the water in the clearwells, where the carbon dioxide would be absorbed by direct contact with the water. The development work necessary before the use of carbon dioxide can be recommended consists primarily of in-reactor single tube tests followed by a half-reactor test. These tests are necessary to show the effects of carbon dioxide on aluminum corrosion, effluent activity, and reactor hydraulics. The single tube tests already …

Report from Hanford Laboratories concerning "the design and construction of the 100-N Reactor and heat dissipation plant complete with the necessary auxiliaries" (p. 2). Details of its construction and the plant's systems and instrumentation are described as well as economic considerations.

Experiments were carried out to (1) explore possibilities for developing a less expensive device than the Hurst threshold detector unit (TDU) for monitoring possible accidental critical reactions in uranium-processing facilities, (2) to study the precision and accuracy of the TDU, and (3) to evaluate the ORNL film badge in mixed neutron-gama radiation fields.

Abstract: An experimental bowable fuel element was developed to study temperature oscillations in the second core loading of the SRE.

This report addresses the development of an improved "bubble through" saturator.

The results of the RTD calibration at temperatures of 1000°F and the thermal cycling at this elevated temperature indicated the temperature transducers may be operated in this environment without a serious compromise in the accuracy of reliability for relatively short periods of time to meet the requirements of this test endeavor. The calibration change which was observed was with the 3°F inherent uncertainty in the measurement and could not be identified as degradation.

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This report describes EG&G activities in support of the Rover Program for the month of January, 1964. Details are discussed in succeeding sections and in the appendices with respect to the various tasks included in our scope of work. At Test Cell A., the Facility Mapping Test, EP-IV, was success- fully completed. Preparation continued for the NRX-AL program scheduled for February, 1964. At Test Cell C., a high flow acoustics test, EP- 1, was conducted. This was the last experimental plan to be completed before the Kiwi-B4D cold flow test series, scheduled to begin on 31 January 1964. Cost curves, except for Test Cell C Operations, still are somewhat below the budget.

This documents contains a table has been prepared to assist in the evaluation of hazards to occupants of the Wahluke Slope associated with radioactive liquids discharged to the river in the event of reactor accidents. Concentration ratios have been estimated for both the maximum point in the river as well as along the shoreline opposite the reactors for several locations of potential interest and for reactors in B, K, and D Areas. The shoreline concentrations apply to water up to 25 yards from shore. 1 tab.

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Abstract: The experimental application of centrifugal clarification, precoat filtration, conventional filtration, and adsorption to the removal of impurities from a bypass stream of irradiated reactor coolant at the Organic Moderated Reactor Experiment is described and evaluated.

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