11 Matching Results

Search Results

Advanced search parameters have been applied.
in subjects: "Physics"  
Results: 1 - 11
open access

PCTR Measurement of EGCR Control Rod Worth

Description: This paper describes the measurement of control rod strength in the PCTR. The first section outlines the theory and method of such a measurement, and the second section presents the results of the measurement of the Experimental Gas Cooled Reactor (EGCR) control rod strength. The reactor parameter actually inferred is the difference in the infinitive multiplication factor for a control rod supercell with and without the control rod in place in the supercell. These measurements are, therefore, v… more
Date: July 20, 1960
Creator: Nichols, P. F.; Engesser, F. C. & Oakes, T. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Eurochemic Questions -- Preliminary Report

Description: The referenced memo asked several questions on the operation of the Purex Plant which are of interest to the Eurochemic personnel. These questions are answered below. 1. A qualitative description of the nitric acid recovery systems is desired -- flow of materials, number of pieces of equipment, etc.
Date: August 24, 1959
Creator: Geier, R. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

PRTR High Pressure Loop Hazards Survey of Preliminary Scope Design

Description: Conceptual design studies conducted at HAPO indicate that the improved thermal efficiencies which can be obtained in a high pressure, high temperature, nuclear-electric power plant might reduce unit power costs substantially. The Plutonium Recycle Test Reactor (PRTR) is designed primarily to investigate various facets of plutonium recycle operation. In order to increases the usefulness of the PRTR as an experimental tool, it is desirable to include facilities for testing materials and fuel conc… more
Date: October 15, 1959
Creator: Walkup, P. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Estimated Power Generation in MTR Slug Test Facility

Description: The very strong flux gradient in the MTR reflector might be thought to be some cause of worry. However, this gradient will be minimized by the presence of the large block of aluminum, which, because of its small effect on neutrons, will tend to flatten the neutron flux in its vicinity. Advantage should be taken of the shape of the test facility by placing the water hole corner closest to the MTR core. This placement should take best advantage of the flattening potentialities of the slowing-d… more
Date: December 30, 1953
Creator: Neumann, Hans, 1936-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

PRTR Gas-Cooled Loop, Hazards Survey of Preliminary Scope Design

Description: The Atomic Energy Commission has recently developed an enlarged program for the study of graphite moderated, gas cooled power reactor systems. It has been recognized, however, that understanding of radiation damage and radiation induced chemical reactions of graphite at the proposed high moderator temperatures is inadequate and that improved understanding is essential if the design of such reactors is to be optimized. Accordingly, the Atomic Energy Commission requested Hanford to organize a mod… more
Date: April 20, 1959
Creator: Wittenbrock, N. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Notes on Lattice Parameter Calculations

Description: In the last two or three years there has been a notable improvement in the knowledge and understanding of reactor lattice physics. During this interval, measurements of parameters have been improved and the methods of analysis have been greatly strengthened. It has become apparent that the classical ways for computing the lattice parameters are not sufficient. It is the purpose of this report to publish under one cover as much of the most recent information as possible.
Date: October 6, 1960
Creator: Joanou, G. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Gamma Heating in PRTR Gas Loop

Description: It is being considered that the in-reactor portion of the test section of the PRTR Gas-Cooled Loop Facility consist, in part, of two concentric Inconel-X tubes. The outer tube is the main stress member, with 3.5 O.D. and a wall thickness of 0.065. The inner tube is 3.0 O.D. and has a wall thickness of 0.030. The inner tube provides an annular gas space to serve as thermal insulation.
Date: June 23, 1959
Creator: Reginbel, J.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Nuclearly Safe Mass Limits, Volume Limits, Infinite Cylinder Diameters and Slab Thicknesses for Slightly Enriched Uranium Rods in Light Water

Description: Graphs have been made which show the nuclearly safe parameters for uranium rods in light water with uranium enrichments up to five weight percent U-235. These data were to serve as a guide to those persons who may be involved with the maintenance of nuclear safety in handling and processing operations with slightly enriched uranium fuel elements. The data are applicable to fuel element fabrication and processing operations, and in general to those operations involving the handling and storage o… more
Date: May 24, 1960
Creator: Clayton, E.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

EGCR Lattice Radial and Angular Power Distribution 2.6 w/o Enrichment

Description: The measurements reported here are companion measurements to those reported earlier in HW-63585. The only significant difference between the measurements is that 1.8 w/o enrichment UO2 fuel was used for the first set, and 2.6 w/o enrichment UO2 fuel was used for the measurements described in this report. The new results will be presented graphically, and for completeness, the details of the measurement will be included here as well as in HW-63585.
Date: May 10, 1960
Creator: Nichols, P. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
Back to Top of Screen