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Abstract: A study has been made of the source, acceleration, and neutralization of ions for application to space propulsion. A summary is made in this paper of some of the most important problems in this area and their solutions.

Review of a study regarding a lid-tank shielding facility's properties, including fast-neutron and gamma dose rates and thermal-neutron fluxes, which were mapped in a symmetry plane. The removal cross section of gadolinium was determined through comparison with various other materials.

The 107-B retention basin was constructed in 1943--44 as part of the original reactor installation. Thermal stressing has caused extensive cracking of the concrete walls and leaking at cracks and joints, requiring repeated maintenance including a major repair program in 1952--53. Although a major repair or replacement program will eventually be necessary, existing basin leakage does not require immediate action, other than periodic control effort, with one exception. Effluent from 107-B leakage is flowing into the 181-B river pumphouse forebay, measurably increasing the temperature of the raw water and raising the question of continued stability of the building foundation. A basic inadequacy also exists in the inability to dispose of undesirable effluents other than to the river. The unique situation of B Reactor adjacent to the C Reactor effluent system permits consideration of improving the effluent disposal situation in this one area with minimum capital investment. The purpose of this report is to provide the scope for a project proposal for interim effluent system modifications in 100-B Area only. This will avoid future production losses and improve effluent disposal capability during resolution of a more permanent solution to the overall problem of effluent routing and treatment.

A lid-tank shielding facility, simular to the one in operation at Oak Ridge, has been constructed and is in operation at Battelle. This facility was descnibed in BMI-1291. The fast-neutron and gamma dose rates and thermalneutron fluxes were mapped in a symmetry plane of the shielding tank. Fast-neutron and gamma dose rates were raeasured behind a series of shielding plugs along a line in the water perpendicular to the fission-plate center. The plug materials included aluminum, iron, lead, titanium, and gadolinium. In order to use small- diameter plugs the effective diameter of the fission plate was reduced for these experiments by placing an iris between the thermal column and the flssion plate. The purpose of the test was to determine the removal cross section of gadolinium by comparison with other materials, using a small amount of gadolinium. The removal cross section for gadolinium is about the same as for lead. Experiments were conducted on ordinary and enriched LiH slabs 4 to 32 in. thick. Fast- neutron and gamma dose rates in addition to thermalneutron fluxes were measured on the water center line behind the slabs. (auth)