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Materials Testing Reactor Project Handbook
The following handbook was made for the purpose of: (1) to give a semidetailed description of the testing reactor, and (2) to explain, in so far as possible, the reasons for the design.
Date:
May 7, 1951
Creator:
Argonne National Laboratory
System:
The UNT Digital Library
Preliminary Appraisal of the Carnotite Resources of the Carrizo Mountains Area, San Juan County, New Mexico, and Apache County, Arizona
From introduction: A rapid appraisal of the carnotite resources of the Salt Wash sandstone member of the Morrison formation in the Carrizo Mountains area was undertaken by the U. S. Geological Survey late in 1951 in connection with its current project of geologic mapping of the area. Though brief and preliminary, this report provides a summary of production trends and estimated reserves in the area and indicates as far as possible the total potential of the area as a source of uranium. This information may be helpful in planning new milling facilities or other measures to encourage a higher rate of production.
Date:
May 1952
Creator:
Strobell, J. D., Jr.
System:
The UNT Digital Library
Distribution of Thermal Neutrons from Fast Sources in Exponential Piles
Report regarding the mathematical analysis of the exponential pile experiment using highly absorbent slugs and assuming the emitting of fast neutrons. Related theory and equations are discussed.
Date:
May 27, 1954
Creator:
Anselone, Philip M.
System:
The UNT Digital Library
Electroplated Metals on Uranium for Aluminum Cladding
Abstract: "Aluminum-clad nickel-plated uranium is corrosion resistant in boiling water. Samples with intentional defects in the aluminum-nickel clodding layers, after testing for more than 300 hr. showed no sign of rapid failure. The study of electroplated metals on uranium for aluminum cladding has defined the effects of several processing variables on the corrosion resistance. The quality of the uranium and the quality of the aluminum-nickel bond were important. Heat treatment and vacuum outgassing of the nickel-plated uranium prior to aluminum cladding were beneficial, and minimizing the amount of air present in the hot-press assembly was desirable. Variation in the steps for electroplating on uranium did not affect the corrosion resistance of aluminum-clad uranium."
Date:
May 4, 1955
Creator:
Beach, John G.; Schickner, William C.; Hopkinson, Dolores. & Faust, Charles L.
System:
The UNT Digital Library
Design and Feasibility Study of a Pebble Bed Reactor-Steam Power Plant
Originally issued as S and P 1963A, Parts I and II. This report covers a design and feasibility study of a pebble bed reactor-steam power plant of 125 megawatt electrical output. The reactor design which evolved from this study is a two-region thermal breeder, operating on the uranium-thorium cycle, in which all core structural materials are graphite. Fuel is in the form of unclad spherical elements of graphite, containing fissile and fertile material. The primary loop consists of the reactor plus three steam generators and blowers in parallel. Plant design and system analysis including cost analysis and capital cost summary are given.
Date:
May 1, 1958
Creator:
unknown
System:
The UNT Digital Library
Li⁶ and Li⁷ (n. 2n) Cross Sections at 14.1 Mev
Abstract: "An absolute measurement of the 14.1-Mev (n, 2n) cross sections of Li-6 and Li-7 has been made using the large scintillator technique, resulting in cross sections in barns of 0.070 +/- 0.006 and 0.056 +/- 0.005 for Li-6 and Li-7, respectively."
Date:
May 29, 1958
Creator:
Ashby, V. J.; Catron, H. C.; Newkirk, Lester L.; Taylor, C. J. & Williamson, M. A.
System:
The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Monthly Progress Report: April 1959
Abstract: This monthly progress report covers the activities of the Army Gas-Cooled Reactor System Program for April 1959. The program includes a water-moderated heterogeneous reactor (Gas-Cooled Reactor Experiment I), a graphite-moderated homogeneous reactor (Gas-Cooled Reactor Experiment II), a mobile gas-cooled reactor (ML-1), and the coordination of the Gas Turbine Test Facility. [It reports] the progress of each project, the associated tests and data evaluation, the applicable design criteria, and the fabrication of reactor components" (p. 1).
Date:
May 25, 1959
Creator:
Aerojet-General Corporation
System:
The UNT Digital Library
Maritime Organic Moderated and Cooled Reactor
Introduction: This document describes the results of a six-week conceptual design study of an organic moderated and cooled reactor (OMCR) power plant adapted to a Class T-7 tanker.
Date:
May 27, 1959
Creator:
unknown
System:
The UNT Digital Library
Strontium Program: Quarterly Summary Report, May 29, 1959
From Abstract: "This report is one of a sequence of quarterly reports, each designed to up-date its predecessor beginning with HASL-42, "Environmental Contamination from Weapon Tests". Herein are presented data which have accrued since HASL-55. Levels of strontinum-90 in fallout, milk, air, water, vegetation, foods, and bone are given, based on data available from February 1, 1959 to May 20, 1959."
Date:
May 29, 1959
Creator:
Hardy, Edward P., Jr. & Klein, Stanley
System:
The UNT Digital Library
OMR Degasifier Loop Experiment
Abstract: A loop has been constructed to study the removal of water and highly volatile materials from Organic Moderated Reactor coolant by vacuum degasification. An analysis of the process was made to determine the most important parameters for study during the experimental program.
Date:
May 1, 1960
Creator:
Corporales, G. W. & Benson, P. R.
System:
The UNT Digital Library
OMRE Fuel Plate Surface Temperature Measurement
Abstract: Accurate measurement of OMRE fuel-element surface temperatures is important for evaluation of the performance of organic compound as moderator and coolant materials in nuclear reactors; a mixture of polyphenyls has been used in reactor operation to-date.
Date:
May 1, 1960
Creator:
Sudar, S.
System:
The UNT Digital Library
Piqua Prototype Handling System
Abstract: Equipment has been developed to handle the fuel elements and control rods for the Piqua (OMR) reactor.With the handling machine, which consists of a shielded cask mounted on a gantry, a fuel element can be replaced in the core in about 27 minutes.
Date:
May 1960
Creator:
Nadler, H.
System:
The UNT Digital Library
Plutonium: Enriched OMR Cores
Abstract: The influence of plutonium on the nuclear characteristics of organic moderated cores is studied.
Date:
May 1, 1960
Creator:
Connolly, T. J.
System:
The UNT Digital Library
Thermal Cycling and Leakage Tests of 12-inch Valves for Sodium Service
Abstract: Tests were performed to determine the effect of thermal cycling on the across-the-seat leakage characteristics of commercially available valves considered for use in the sodium coolant system of the Hallam Nuclear Power Facility.
Date:
May 1, 1960
Creator:
Baroczy, C. J.
System:
The UNT Digital Library
Thorium Uranium Physics Experiments: Final Report
Report concerning the "study of uniform lattice cores moderate with light water" (p. xiii) and comparing the measurements with various theoretical models. Includes descriptions of the cores, core measurements, leakage experiments, and calculations.
Date:
May 1960
Creator:
Snidow, N. L.; Anderson, R. C.; Batch, M. L.; deCoulon, G. A. G.; Lewis, R. H. & Vannoy, W. M.
System:
The UNT Digital Library
The ML-1 Design Report
From abstract: "This report describes the design of the mobile nuclear power plant which is to be the prototype of a mobile, low-powered nuclear power plant intended to furnish electrical power in remote locations."
Date:
May 16, 1960
Creator:
Linenberger, G. A.
System:
The UNT Digital Library
Investigations of Neutron Penetration in TiH and Steel Slabs
Abstract: A multigroup P1 approximation for hydrogen scattered neutrons has been developed and applied to the study of neutron flux distributions in titanium hydride and steel shield systems.
Date:
May 15, 1961
Creator:
Karcher, R. H.
System:
The UNT Digital Library
Reactor Containment Design Study
Introduction: Sargent & Lundy was authorized on November 1, 1960, to make an economic and technical feasibility study of various reactor containment designs which are being utilized for several power plants now under construction.
Date:
May 18, 1961
Creator:
Johnson, R. A. & Nelson, I.
System:
The UNT Digital Library
Research and Development Studies on Waste Storage Process
Report documenting "the determination of the thermal stability of various fission product oxides and nitrates, and an investigation of the gas phase decomposition of ruthenium tetroxide" (p. 4).
Date:
May 19, 1961
Creator:
Ortner, M. H.; Anderson, C. J. & Campbell, P. F.
System:
The UNT Digital Library
Thermonuclear Division Semiannual Progress Report, January 31, 1961
Report describing ongoing progress made at the Oak Ridge National Laboratory's Thermonuclear Division.
Date:
May 31, 1961
Creator:
Oak Ridge National Laboratory
System:
The UNT Digital Library
A Computer Program for Determining First-Collision Neutron Doses
Data processing program written to compute the neutron dose received by individuals exposed in a nuclear excursion.
Date:
May 21, 1962
Creator:
McMurray, C. S.
System:
The UNT Digital Library
U.S. Atomic Energy Commission Idaho Operations Office Health and Safety Division Annual Report: 1961
Report containing documentation of projects undertaken by the multiple branches of the Health and Safety Division of the Idaho Operations Office at the Nuclear Reactor Testing Station (NRTS).
Date:
May 21, 1962
Creator:
U.S. Atomic Energy Commission. Idaho Operations Office.
System:
The UNT Digital Library
Corrosion Studies in Simulated N-Reactor Secondary System Water Environment
Report containing the procedures and results of tests made to determine the corrosion resistance of materials in a simulation of Hanford Laboratories' N-Reactor secondary system water environment.
Date:
May 1963
Creator:
Larrick, A. P.
System:
The UNT Digital Library
Gas-Metal Reactions with Iron- and Nickel-Base Heat Resistant Alloys: An Interpretive Literature Survey
Report reviewing literature that concerns "the compatibility of stainless steels and nickel-base alloys with various gases which might be present in or around a high temperature nuclear reactor" (p. 2).
Date:
May 1963
Creator:
Jones, D. A.
System:
The UNT Digital Library