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Xenon calculations for I and E fuel element

Description: 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… more
Date: July 2, 1959
Creator: Chitwood, R. A.
Partner: UNT Libraries Government Documents Department
open access

Supplement No. 1. Projections of Costs, 1959-1975 for Nuclear-Conventional Power Plant Cost Study. Conventional Coal Fired Power Plants : 25,000 KW to 325,000 KW for Argonne National Laboratory, Lemont, Illinois

Description: In order to establish a basis for comparing the estimated cost of nuclear power plant designs, a set of general and detailed design considerations for conventional coal-fired power plants was established. Five preliminary designs of conventional coal-fired power plants ranging in size from 25to 325 mw were selected, and cost estimates were prepared. Supplement 1 shows a year by year projection of costs for the period 1959-1975.
Date: July 2, 1959
Creator: Chittenden, W. A.
Partner: UNT Libraries Government Documents Department
open access

Some Research on the Lift and Stability of Wing-Body Combinations

Description: 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 … more
Date: July 2, 1959
Creator: Purser, Paul E. & Fields, E. M.
Partner: UNT Libraries Government Documents Department
open access

105-N charge-discharge rates

Description: 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 … more
Date: July 2, 1959
Creator: Nesbitt, J. F.
Partner: UNT Libraries Government Documents Department
open access

Run 300A-B Slurry Run of 300A Pump and Loop

Description: 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… more
Date: July 2, 1959
Creator: Moyers, J. C.
Partner: UNT Libraries Government Documents Department
open access

In-Pile Loop Tests of GCRE Elements (I-IT and I-I'T)

Description: 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.
Date: July 2, 1959
Creator: Nakazato, S.; Williams, P. M. & Wilson, W. D.
Partner: UNT Libraries Government Documents Department
open access

Quarterly Report of Non-Production Reactor Fuels Reprocessing Budget Activity 3790

Description: 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.
Date: July 2, 1959
Creator: Cooper, V. R.
Partner: UNT Libraries Government Documents Department
open access

PRTR Single Tube Prototype Mockup (STPM) Operational Characteristics

Description: 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.
Date: July 2, 1959
Creator: Scott, P. A.
Partner: UNT Libraries Government Documents Department
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