The power of nuclear track research emulsion as a fast neutron dosimeter is examined in the exposure of a human phantom to PuBe neutrons. Semiautomatic track scanning and high-speed data analysis obviate the major disadvantages of this dosimeter, and allow the following basic information to be obtained without a serious cost in time: the rulative proton recoil energy spectrum, the absolute differential proton track den sity spectrum, and the average proton recoil energy at various locations in the phantom. From this are calculated the total absorbed local tissue doze due is proton recoils, the local thermal neutron intensity, and that portion of the tissue doze due to thermal [formula] tracks.

Laboratory-scale tests on methods for recovering uranium and thorium from graphite-base reactor fuel elements are reported. The 90% HNO/sub 3/ process, which involves simultaneous disintegration and leaching in 21 M HNO/sub 3/, is applicable to all fuel elenments which do not contain coated fuel particles. Leaching of irradiated (0.001% burnup) fuels containing 3 and 12% uranlum recovered approximates 99.3 and 99.9%, respectively, of the uranium in two 4-hr leaches with boiling acid. The graphite residue retained > 50% of the long-lived fission products. Three successive leaches of fuel containing uranium and thorium recovered approximates 99% of both elements. Uranium recoveries by combustion in oxygen followed by dissolution of the ash hn nitric acid or fluorlde-catalyzed nitric acid are quantitative only when the fuel is not coated, does not contain Al/sub 2/O/sub 3/-coated fuel particles, and is free from impurities such as iron. During combustion up to 95% of the Ru-106 was volatilized from irradiated specimens. Recoveries, by leaching with 70% HNO/sub 3/, from fuel specimens containing Al/sub 2/O/sub 3/-coated fuel particles were greater than 99% when the specimens were ground finer than 200 mesh to ensure crushing of the fuel particles. (auth)

A pump was developed for pumping carbon dioxide in a closed loop without introducing impurities. This pump will give flow rates of up to 3 liters/min and will develop a working pressure of over 70 mm Hg. No wear was observed after 2000 hr of testing. It is felt that this pump is more desirable for this application than those developed by other experimenters for two reasons: relatively inexpensive construction of the pump and the associated electronic circuit and the low coefficient of friction between the piston and the cylinder wall. Various modifications are suggested which will make this pump satisfactory for other applications. (auth)

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).

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.