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P Division monthly report, September 1949

Description: This progress report discusses the activities of the P Division for the month of September, 1949. The B and F piles operated at 275 megawatts (MW) and the D pile at 305 MW throughout the month except for cutages listed under Area Activities. A total of 60.22 tons of metal, at an average concentration of 396 megawatt days/ton (MWD/ton) was discharged from the piles during the month. The 105-H Building was accepted from the Construction Division on September 28 with certain exceptions noted under… more
Date: October 6, 1949
Creator: Lee, Edward P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Compilation of data on 51 ruptured slugs

Description: The following tabulation includes information on all uranium slug failures which have occurred through September 26, 1951. The four suspect slugs which are listed were discharged from tubes which gave strong indication of containing ruptures. Although no obvious rupture could be found among the slugs from these tubes, the listed pieces exhibited defects which may be incipient ruptures.
Date: October 4, 1951
Creator: O'Keefe, D.P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Technical activities report: Heat, water, and mechanical studies

Description: Topics in the heat studies section include: front and rear face reflector shields at the C-pile; process tube channel thermocouples; water temperature limits for horizontal rods; slug temperature and thermal conductivity calculations; maximum slug-end cap temperature; boiling consideration studies; scram time limit for Panellit alarm; heat transfer test; slug stresses; thermal insulation of bottom tube row at C-pile; flow tests; present pile enrichment; electric analog; and measurement of therm… more
Date: October 4, 1951
Creator: Alexander, W. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Vernatherm functional test, Test Project No. 14

Description: The Vernatherm unit is a temperature sensitive capsule which translates temperature change to mechanical movement of a brass plunger. A change in phase of a hydrocarbon contained in a cylinder caused by temperature change, causes movement of the brass plunger. The units are available for various temperature ranges. The adaptation considered was to monitor the outlet water temperature from individual process tubes in the ``G`` pile. The purpose of the test was to determine the magnitude of error… more
Date: October 31, 1951
Creator: Smith, J. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Travel to Battelle Memorial Institute. Trip report, September 17, 24, and October 8, 1953

Description: This report gives a brief summary of work at Battelle in support of Savannah River reactor fuel elements. Barrier effectiveness tests show that 0.2 mil nickel is a minimum for diffusion barrier application. Successful bonds by roll cladding with an electrodeposited nickel bond layer have been produced without deformation of 1 inch x 1 inch x 0.180 inch cores. Deformation of core versus pack has been established for several conditions of core dimension and rolling schedule. Apparatus for a criti… more
Date: October 15, 1953
Creator: Beckman, G. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Monthly report of the Design Analysis Group for September 1954

Description: The following topics were discussed in this report: pressurization of the rear face for existing reactors; loss of steam in existing reactors; in-pile boiling in the 105-KER recirculation facilities; feasibility report for special study reactor plant; shielding requirements of the special study reactor plant; sulfuric acid addition to 100-K; radiation from activated iron in a recirculating system; ion exchanger activity from Fe corrosion; thermal shock-KER loop; shielding of tube bundles; adjus… more
Date: October 26, 1954
Creator: Andersen, R. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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[Dispersion of fission products]

Description: This historic report is on letter which details the research into atmospheric dispersion of fissioviable materials in the event of a reactor accident at Savannah River Plant. Graphs are included.
Date: October 29, 1956
Creator: Menegus, R. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Special hazards report - I E fuel loads

Description: This report has been prepared in answer to the request from the AEC contained in the letter of October 1, 1957, from A. T. Gifford, HOO to A. B. Greninger. As requested, the report is of a summary nature and a more complete discussion of many of the points considered will be found in the references listed. The report is directed primarily at C reactor but some discussion of the other reactors is also included. A description of the proposed utilization of I E slugs in C reactor together with the… more
Date: October 15, 1957
Creator: Brown, J.H.; Fullmer, G. C.; Trumble, R. E. & VanWormer, F. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Pressurized Water Reactor Program Technical Progress Report for the Period July 15, 1954 to August 26, 1954

Description: This progress report has 2 parts. Part 1 PWR Engineering covers the following topics: (1) power plant analysis and systems; (2) power plant components and component materials and tests; and (3) reactor and auxiliaries. Part 2 PWR Development covers: (1) fuel element development; (2) metallurgy of core materials; (3) materials application development; (4) chemistry development; (5) irradiation effects; and (6) reactor physics.
Date: October 31, 1957
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Tests to determine effect of humidity on high-efficiency filters when installed horizontally

Description: The object of tests is to determine effect of high-humidity air on the physical characteristics of filter media and separators when the filter is mounted in the horizontal position. Usual installation is with the filter mounted vertically.
Date: October 4, 1960
Creator: Palmer, J. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Radiation damage study on the lithium hydride SNAP shield

Description: Radiation damage may occur to the lithium hydride shields as a result of the reaction Li{sup 6}(n, {alpha})H{sup 3}. There is evidence in the literature indicating both the existence and absence of radiation damage to the SNAP shields. It is believed that there is a high probability that there will be damage and that it will adversely affect the properties of the shield. This damage may take the form of: (1) volume expansion of the hybrids, (2) void formation within the hybrids, and (3) gas pre… more
Date: October 4, 1961
Creator: Doctor, R. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Presentation to the Atomic Energy Commission and the Air Force, June 14, 1962

Description: This volume contains the charts and backup material presented to the Atomic Energy Commission and Air Force on June 14, 1962 concerning General Electric's Nuclear Materials and Propulsion Operation (formerly the Aircraft Nuclear Propulsion Department), during its work on the development of a nuclear power plant for manned aircraft.
Date: October 1, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Design criteria for phase II dummy hydraulic core for containment systems experiment reactor simulator

Description: The design of a Phase II dummy hydraulic core for the CSE reactor simulator is described. The core will be a scale model having features typical of PWR or BWR reactor cores, and will include control rods and associated support mechanisms, fuel elements, a thermal shield, top and bottom core guide and support plates, and flow baffles. The core and simulator vessel will be instrumented to provide measurement of temperature, static and differential pressures, forces on core components, and rarefac… more
Date: October 3, 1966
Creator: Henager, C. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Tensile and stress rupture tests of S8DR Hastelloy-N heats: ORNL verification tests

Description: In connection with the ORR Hastelloy-N irradiation experiments, a limited number of tensile tests and uniaxial and biaxial stress-rupture tests on S8DR Hastelloy-N heats were conducted at AI to determine the effect of some of the ORNL test conditions. The tests performed at AI were in parallel to the ORNL control tests. The results showed that the effect of the test condition variations between the two tests were generally insignificant. The effect of the test conditions is discussed.
Date: October 5, 1967
Creator: Lee, S. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fast Flux Test Facility. Design and Development Quality Assurance Requirements for the FFTF

Description: The document is presented to provide general management requirements for Pacific Northwest Laboratory (PNL) and contractor design and development quality assurance programs to assure the required quality level of the various items required for the FFTF. The document is applicable as imposed by the contract to FFTF contractors and subcontractors. The document is also applicable to PNL design and development activities related to the FFTF.
Date: October 23, 1968
Creator: Albert, W. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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