4 Matching Results

Search Results

Results: 1 - 4
open access

The Alco Products Inc. Criticality Facility : Description and Operation

Description: The Alco Products Criticality Facility, site location, and operating procedures are described in detail, including the handling of fissionable material and the operating procedures for the safe performance of critical experiments.
Date: July 16, 1958
Creator: Noaks, John W.
Partner: UNT Libraries Government Documents Department
open access

Power Distributions for Type 3 Replacement Cores for SM-1, SM-1A and PM-2A

Description: Abstract: The most adverse power distribution and power peaking factors have been developed for Type 3 replacement cores for SM-1, SM-1A, and PM-2A. Also included is the 37 element Type 3 core for SM-1, which is known as SM-1 Core III and is a prototype of a Type 3 core for PM-2A. The power distributions were compared with measured distributions obtained on type 3 fuel elements in SM-1, SM-1A and PM-2A core configurations. Using the measured data as a standard, correction factors were obtained … more
Date: July 25, 1962
Creator: Oggerino, J. P.
Partner: UNT Libraries Government Documents Department
open access

Reactor Analysis APPR-1 Core II

Description: Preface; Subsequent to the analysis in the body of this report metallurgical developments indicated that it would not be feasible to build the APPR-1 Core II with the increased boron loading specified herein. At the time of the issuance of this report the Core II boron loading is to be the same as that for Core I. At the time of procurement of the core in the fall, if metallurgical developments warrant, the increased boron loading will be employed. The loading discussed in the body of the r… more
Date: July 15, 1958
Creator: Williamson, T. G.; Leibson, M. J. & Bryne, B. J.
Partner: UNT Libraries Government Documents Department
open access

SM-2 Full Scale Flow Studies Termination Report

Description: Abstract: Hydrodynamic flow studies were conducted on a full scale model of the SM-2 reactor vessel and core. Test fluid was water at 200 psi and 200 degree F. Test facilities, model, and instrumentation design are discussed. Flow distribution in the stationary fuel elements, lattices, and control rods of the second pass was investigated. Pressure losses through the various core components were measured and are compared with calculated values. Observed over-all pressure drop was 71 feet of wate… more
Date: July 30, 1961
Creator: Christenson, J. A.; Richards, W. M. S. & Davidson, S. L.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen