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Subcontract Work by Thompson Products, Inc.

Description: In April, 1954, Thompson Products Inc. formally began work on a program leading to the fabrication of two test radiators. The work done to date is summarized in report number PWAC-127, First Technical Report by Thompson Products Inc. on Liquid-Metal-to-Air Radiators and in PWAC-128, Second Technical Report by Thompson Products Inc. on Liquid-Metal-to-Air Radiators. The first report describes possible radiator design concepts meeting the required specifications and presents an analytical method which was derived to optimize the designs. Thompson Products has decided that a core with cast NaK passages in combination with the sheet-metal, ribbon fins on the airside offers maximum reliability. The second report formulates the analysis of the final radiator design and presents the fabrication and evaluation studies used to select the design. To evaluate the permeability of cast NaK passages, Thompson Products is planning to build a hot NaK flow rig. A parallel investigation on wrought materials will be carried out as an alternate NaK passage type. The next phase of the program, the final design of the test radiator, has started.
Date: April 20, 1955
Creator: Shaw, R.H.
Partner: UNT Libraries Government Documents Department

Design of LCCBM and LCCBN Loops

Description: The special fabrication requirements of the newer columbium alloys, particularly with respect to brazing, stress relieving, weld filler wire, etc., necessitates individual detail and layout drawings for the construction of forced convection corrosion loops from different columbium alloys. Accordingly, it is requested that detail and layout drawings be provided for two forced convection corrosion loops to the specifications outlined.
Date: March 1, 1960
Creator: Coyle, C.E.
Partner: UNT Libraries Government Documents Department

Primary Piping Static Test Design Request

Description: It is requested that a design be initiated for the primary piping static test. This test is necessary to provide information as to the reliability of the pipe subjected to reactor operating conditions. The test conditions are as follows: temperature - 2000 F (isothermal), pressure effective - 42 psi, and test time - 10,000 hours. It will be necessary to test two sizes of pipe as shown on the preliminary piping layout (2.250-inch O.D. x .095-inch wall and 3 1/2 SCH. 10 pipe). The test specimens shall be jacketed in an inconel containment vessel. The test rig should be similar to the design of the 4-inch pressure vessels (T-1030244). In addition an outer containment vessel constructed of stainless steel must be provided around the clam shell heaters and the inconel containment vessel. This is to provide an inert atmosphere for the inconel vessel. Provisions should be made in the design for a 1/4-inch clad thermocouple. It is planned to use the pipe test as a vehicle for studying experimental Tc's (Cb-Mo and W-W.26% Re).
Date: November 30, 1961
Creator: O'Brien, R.W.
Partner: UNT Libraries Government Documents Department

Reflector Moderated Solid Fuel Element Sodium Cooled Reactor Critical Mass vs. Power Density

Description: This is the sixth of seven reports to be issued on the parametric studies of reflector-island moderated and core moderated solid fuel element reactors. The power distribution and hence fuel volume were varied for the optimum island size reflector moderated reactor. The effect on the critical mass, power distribution and neutron leakage was determined and is plotted in Figures 1, 2, and 3.
Date: September 6, 1955
Creator: Merriman, F. C. & Chase, G.
Partner: UNT Libraries Government Documents Department

Request for Design of a Fuel Element Assembly Soak Test

Description: It is requested that the design be completed for a full-scale fuel element soak test. The test assembly must be designed to permit the fuel element test specimen to be submerged in a lithium bath under a pressure of 60 psi. The maximum temperature of the lithium is to be 2000 F. A total of four test units will be required to complete the test program. Two specimens will be exposed to a thermal cycle between 2000 F and 1400 F with the remaining two specimens being exposed to a thermal cycle between 2000 F and 1000 F. Heating will be done at the rate of 200 F/hour preceded by a 150 hour soak at 2000 F. Heat will be supplied by clam-shell type heaters. The test specimen - lithium system will be contained by a Cb-lZr vessel which will be surrounded by a 310 steel container. The heating units will be mounted on the outside of this 310 S.S. container. A bottom fill line is requested in order to insure a lithium system free from gas pockets. A slow lithium fill will be made up through the specimen to a level indicated by a probe in the expansion tank.
Date: November 30, 1961
Creator: Spahl, R.J.
Partner: UNT Libraries Government Documents Department

Request for Nuclear-Ramjet Radiator Weight Data

Description: Weight data on the following liquid metal to air radiators is requested. This information is to be used in a comparison of the performance attainable with different nuclear reactors and liquid metal systems in a ram-jet powered airplane. The radiator dimensions are based on estimates using the performance curves presented in CNLM-338.
Date: June 23, 1958
Creator: Larson, J.W.
Partner: UNT Libraries Government Documents Department

Shield Weights

Description: Shield weights were calculated for a number of fast reactors having desirable engineering characteristics using the Shield Optimization code. On the basis of these calculations, a Design Fast Reactor was chosen. This reactor, henceforth known as the PWAR-9, has a 12.75 inch core O.R. with a 2 inch Ni reflector. The reactor-shield weight and weight components for a supersonic mission, 2 man crew compartment, are given in table 1. The rpesent shield design uses U and LiR as shielding materials on the reactor and U and plastic on the crew compartment. No intermediate heat exchanger is used since hot Na is pumped directly to the engines. The dose from the activated Na is taken into account by putting more shielding on the crew compartment. No patch weights on the reactor have been added since it is estimated that little will be needed.
Date: July 31, 1957
Creator: Woodsum, H.C. & Rost, E.S.
Partner: UNT Libraries Government Documents Department

Subcontract Work by the Ferrotherm Co.

Description: The Ferrotherm Company is undertaking a design study of a test radiator. Since January 21, 1955, preliminary designs of several radiators have been completed prior to the selection of one for the final design study. Ferrotherm has been given prototype design specifications for structural design, typical in-flight prototype performance specifications for core-size estimates, test core specifications for their design study, and a method whereby radiators may be evaluated. From analysis of the prototype specifications a matrix will be selected for the test core design study. Although the analysis has narrowed to both a plate-and-sheet-metal fin and a plate-and-pin-fin core geometry, Ferrotherm is more or less committed to pin-fins.
Date: April 20, 1955
Creator: Shaw, R.H.
Partner: UNT Libraries Government Documents Department