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100 Areas Technical Activities Report - Physics, January 1947

Description: Four routine shutdowns were experienced during the month. A measurable amount of the excess reactivity held in the control rods at the first of the month has been lost in the decrease in the average accumulated exposure of all the metal in the pile. The vertical safety rod guides have been measured for vertical alignment by the Maintenance Dept. A definite pattern has been found in the misalignment of the guides. The horizontal rod thimbles were borrowed on January 2, 1947 to see if any leaks w… more
Date: February 12, 1947
Creator: Montgomery, E. B.
Partner: UNT Libraries Government Documents Department
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Production test IP-2-A: Enriched uranium conversion ratio and stability test

Description: This test as detailed in this report is one of three parts of the initial testing program to demonstrate enriched usage at HAPO. It proposes to irradiate two twelve-tube blocks of enriched uranium and lithium-aluminum slugs to obtain conversion ratios and preliminary information concerning slug stability.
Date: November 12, 1956
Creator: Lang, L. W.
Partner: UNT Libraries Government Documents Department
captions transcript

[News Clip: Sports Show]

Description: Video footage from the WBAP-TV television station in Fort Worth, Texas, to accompany a news story.
Date: April 12, 1964
Duration: 2 minutes 39 seconds
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Partner: UNT Libraries Special Collections
open access

SLUG PROGRAM QUARTERLY REPORT FOR APRIL, MAY, JUNE 1953

Description: Preliminary results are reported on the coating of U by immersion in nonreacting molten Mg saturated with Zr, Ni, or Si. A corrosion analysis of the resulting Mg-- Zr outer coat was performed on one failure occurring in boiling water. Further experiments are described on the corrosion testing of Cu-plated and Zn-dipped U. Improvements in the Zn-dip process are uncertain, however, because hot-dip Zn coats show comparable corrosion characteristics. Investigations have been conducted on the castin… more
Date: August 12, 1953
Creator: Chiotti, P. & Carlson, O.N.
Partner: UNT Libraries Government Documents Department
open access

High Level Waste Tank Gamma Profiling

Description: Cleanup at the Savannah River Site brings with it the need to clean out and close down the radioactive waste tanks constructed in support of the fuel rod dissolution process. An innovative technique for assaying waste tanks has been developed at the Savannah River Site. The technique uses a gamma detector in the annular space between the inner and outer walls of double walled tanks. Unique shielding, counting electronics, and deployment techniques were developed to facilitate mapping interstiti… more
Date: December 12, 2003
Creator: Moore, F.S. Jr.
Partner: UNT Libraries Government Documents Department
open access

HEAT-TRANSFER EXPERIMENTS ON A PROPOSED FUEL ASSEMBLY FOR THE EXPERIMENTAL GAS COOLED REACTOR. SECTION II FO FUEL-ASSEMBLY HEAT-TRANSFER AND CHANNEL PRESSURE-DROP EXPERIMENT FOR THE EGCR RESEARCH AND DEVELOPMENT PROGRAM

Description: Heat-transfer data are presented for the Experimental Gas Cooled Reactor Title I seven-rod fuel-assembly design. The effect on heat transfer of (1) the radial location of the outer six rods of the seven-fuel-rod cluster and of (2) the addition of helical-finned spacers at the midpoint of each of the seven fuel rods is discussed. The heattransfer data were obtained to verify preliminary general assumptions pertaining to the heat-transfer characteristics of the seven- rod fuel-assembly design and… more
Date: April 12, 1960
Creator: Beaudoin, C.L. & Higgins, R.M.
Partner: UNT Libraries Government Documents Department
open access

Pathfinder Atomic Power Plant. Clustered Pin Superheater Lattice Experiments

Description: Experiments to obtain detailed thermal flux distribution measurements within a unit fuel cell and measurements of sub-cadmium and epi-cadmium U/sup 238/ absorption in the fuel rods are described. These quantities are required for determination of the thermal utilization and resonance escape probability of the fuel loading. (auth)
Date: February 12, 1963
Creator: Selep, A.
Partner: UNT Libraries Government Documents Department
open access

[News Script: Drag races held at guard base]

Description: Script from the WBAP-TV station in Fort Worth, Texas, covering a news story about a series of fund-raising drag races held at the National Guard base near Eagle Mountain lake.
Date: December 12, 1954
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Partner: UNT Libraries Special Collections
open access

A Purex process one cycle plant study

Description: In keeping with the announced goals for production at Hanford, a series of separations plant studies is being conducted with the objective of providing an insight into worthwhile design development goals both process and plant-wise. These studies will provide a basis for evaluation of research and development programs, with all cost estimates and other supporting information standardized, both in presentation and detail. These developments are vital to the future of separations plant planning i… more
Date: December 12, 1955
Creator: Fecht, J. B.; Jaske, R. T.; Lane, T. V. & Ludlow, J. O.
Partner: UNT Libraries Government Documents Department
open access

Photographs of Failure 250, the first C-pile rupture

Description: This memorandum discusses four photographs of Failure 250, from Tube No. 2179-C, which are presented to show the type of failure as viewed in the 111-B cave. The first three photographs are successive rotations of the slug, illustrating the split-out portion at the base end of the piece. The fourth photo was focused on the split to show the bulging of the slug and the width of the opening.
Date: March 12, 1953
Creator: Chockie, L. J.
Partner: UNT Libraries Government Documents Department
open access

Calculated and observed P-10 production in H-10

Description: Recently three H-10 tubes (2,772, 2,176, 3,673) have been removed and the tritium and other gases have been extracted from the Z slugs. It is of interest to compare the calculated volumes of gases with the amounts obtained in these extractions. The comparison is given in this paper. The reasons for the large disagreement are not known at present. As pointed out below, the weakest part of the calculation is the knowledge of the exposure which these Z slugs have received. It is possible that some… more
Date: January 12, 1951
Creator: Ozeroff, W. J.
Partner: UNT Libraries Government Documents Department
open access

The Bonding of Molybdenum-and Niobium-Clad Fuel Elements

Description: A solid-state bonding technique involving the use of gas pressure at elevated temperatures was utilized for the self-bonding of molybdenum and niobium. Bonding conditions and surface preparation as a function of the integrity of the bond achieved were evaluated for each material. Optimum self-bonding of niobium was achieved by bonding parameters of 2100 to 2300 deg F at 10,000 psi for 3 hr with surfaces which had been prepared by etching in a nitrichydrofluoric acid solution prior to bonding. T… more
Date: July 12, 1960
Creator: Paprocki, S. J.; Hodge, E. S. & Gripshover, P. J.
Partner: UNT Libraries Government Documents Department
open access

STRUCTURAL EVALUATION OF HNPF U-MO FUEL ELEMENTS

Description: A structural evaluation is presentsd of the Hallam Power Reactor fuel elements. The fuel rcd spacer examined is an interim design, but the final spacer is considered to be adequately represented by the analysis of the interim design. Loading of the spacer is considered at temperatures up to 600 deg F. The maximum stress in the hanger rod is found to be 4700 psi. Creep in the fuel rod cladding from internal pressure is predicted to be 5.2% after 48 months of operation, based on a predicted volum… more
Date: April 12, 1961
Creator: Waters, F.J.
Partner: UNT Libraries Government Documents Department
open access

Progress Relating to Civilian Applications During May 1960

Description: The investigation of the stabilizing influence of oside additions to UO/ sub 2/ was continued. The effects of fast-neutron irradiation upon the mechanical properties of Type 347 stainless steel are being investigated. Tensile data are reported for alloys of Nb-Cr and Nb-Zr. The major effect of fast-neutron irradiation on the creep properties of Zircaloy-2 is being studied by comparing the in-reactor creep behavior of the alloy with out-of-reactor creep properties. New methods for the determinat… more
Date: July 12, 1960
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
Partner: UNT Libraries Government Documents Department
open access

Further Studies on Control of the Converter Reactor

Description: Introduction: "This report is an extension of NAA-SR-Memo-178. The results show the number of control rods as a function of the amount of reactivity to be controlled. Numerical solutions are given for a typical example and are readily obtainable for other cases."
Date: May 12, 1952
Creator: Robinson, L. B.
Partner: UNT Libraries Government Documents Department
open access

Neutronic Benchmarks for the Utilization of Mixed-Oxide Fuel: Joint U.S./Russian Progress Report for Fiscal Year 1997 - Volume 4, Part 2--Saxton Plutonium Program Critical Experiments

Description: Critical experiments with water-moderated, single-region PuO{sub 2}-UO{sub 2} or UO{sub 2}, and multiple-region PuO{sub 2}-UO{sub 2}- and UO{sub 2}-fueled cores were performed at the CRX reactor critical facility at the Westinghouse Reactor Evaluation Center (WREC) at Waltz Mill, Pennsylvania in 1965 [1]. These critical experiments were part of the Saxton Plutonium Program. The mixed oxide (MOX) fuel used in these critical experiments and then loaded in the Saxton reactor contained 6.6 wt% PuO{… more
Date: October 12, 2000
Creator: Abdurrahman, NM
Partner: UNT Libraries Government Documents Department
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