Figures have and can be generated that indicate a higher charge-discharge rate if required before 105-N will be comparable with existing reactors. Also, these figures show an apparent operating cost incentive to increase the charge-discharge rates proposed for 105-N. Although these figures may be true by themselves, other figures developed from the same information and stated on a basis that affords a true comparison, show that the proposed rates for 105-N are compatible with those in existing reactors. However, the accomplishments of existing reactors should be considered as a guide only and not as Criteria since the design basis has already been established for Project CAI-816. An average charge-discharge rate has been proposed for 105-N that is compatible with the two main ground rules of the Project. Namely, the capital cost limitation and the plant factor. This rate of 8 tubes/hr. is one that appears to be reasonable from the charge-discharge design aspects and there is a good possibility that it can be increased with operational experience.

Report documenting two in-pile loop experiments conducted at the Battelle Research Reactor-Gas Cooled Reactor (BRR-GCR). These experiments test heat transfer calculations and the behavior of the fuel element under severe thermal-cycling conditions.

The Single Tube Prototype Mockup (STPM) was constructed to be used as a tool to evaluate the mechanical problems involved in operating and maintaining many components of the Plutonium Recycle Test Reactor (PRTR). This report has been written to acquaint interested HAPO components with the capability of the STPM and for use as an aid in scheduling tests and/or to properly evaluate testing results obtained from the mockup.

This report summarizes the research and development work carried out during March, April and May, 1959, for Budget Activity 2790 - Separations Development for Non-Production Reactors, The effort on Activity 2790 will enable Hanford to begin reprocessing in January, 1962, the fuel elements from power reactors which employ depleted or slightly enriched uranium fuels.

The 300A and loop were operated for 2862 hr with thorium oxide slurry at 1500 psi and 280ºC to determine the effects vane inlet and exit geometries on impeller wear, the wear rate of aluminum oxide bearings in this size pump, and the operating characteristics of the loop. The thoris, a 1600*C-fired oxide, had a mean particle size of approximately 2 u. Average circulating slurry concentration was approximately 450 grams of thorium per kilogram of water and average flow rate was approximately 300 gpm.

The present paper summarizes and correlates broadly some of the research results applicable to fin-stabilized ammunition. The discussion and correlation are intended to be comprehensive, rather than detailed, in order to show general trends over the Mach number range up to 7.0. Some discussion of wings, bodies, and wing-body interference is presented, and a list of 179 papers containing further information is included. The present paper is intended to serve more as a bibliography and source of reference material than as a direct source of design information.

This document describes in detail the calculations that are basic to the xenon problem. While much of this work appears elsewhere, herein an attempt has been made to bring it together and make it as understandable as possible. The principle purpose of this document is to calculate the equilibrium xenon poisoning for the I and E geometry fuel element and compare the results to the equilibrium xenon poisoning for the solid geometry fuel element. Further objectives are to provide an understandable reference for those with interest in the basic xenon formulation, and to serve as a training guide for new personnel.