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

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In conjunction with the proposed thorium target element replacement program, hydraulic tests were performed in the Hydraulics Laboratory in 185-D building to determine the flow characteristics of 1.480-inch OD solid thorium loadings in B, C, D, and K fringe tubes. Included are supply curve data for those orifice combinations which are tentatively to be used with the thorium loads in the various fringe tubes. In addition, predicted supply-demand characteristics are presented for a loading of 1.600-inch OD thorium solids in a K-Reactor Zircaloy-2 process tube equipped with a 0.270-inch flat-plate orifice in a X central zone double-orifice retainer union (cage), Drawing H-1-21952.

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A thermal and nuclear NRX-A5 Design Review was held at WANL on April 10, 1964. Analyses and planning performed to date on the NRX-A5 and subsequent reactors were presented. Systems analyses were performed on various "cooled periphery".and "hot periphery" seal configurations. A number of inner reflector designs were examined, as well as means for cooling the lateral support springs. Core component redesign incl,uded methods for controlling inter-element pressure distribution by undercutting or chamfering of fuel elements. Changes in tie rod diameters, use of as-extruded fuel elements, and performance analysis of the various systems were also described. Nuclear analysis was confined to parametric studies on excess reactivity and control drum span for inner reflector material combinations of graphite, aluminum, and/or beryllium. Changes required to more precisely define the NRX-A5 were discussed together with the effects associated with the twice power reactor capability envisioned for subsequent reactors.

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This is the specifications for the High Temperature Lattice Test Reactor Building 318 and it is divided into the following 21 divisions or chapters: (1) Excavating, Backfill & Grading; (2) Reinforced Concrete; (3) Masonry; (4) Structural Steel & Miscellaneous Metal Items, Contents - Division V; (5) Plumbing, Process & Service Piping; (6) Welding; (7) Insulated Metal Siding; (8) Roof Decks & Roofing; (9) Plaster Partitions & Ceiling; (10) Standard Doors, Windows & Hardware; (11) Shielding Doors; (12) Sprinkler System & Fire Extinguishers, Contents - Division XIII; (13) Heating, Ventilating & Air Conditioning; (14) Painting, Protective Coating & Floor Covering, Contents - Division XV; (15) Electrical; (16) Communications & Alarm Systems; (17) Special Equipment & Furnishings; (18) Overhead Bridge Crane; (19) Prefabricated Steel Building; (20) Paved Drive; and (21) Landscaping & Irrigation Sprinklers.

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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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.

This report details activities of the Irradiation Processing Department during the month of April 1964.