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Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 5. Spiked Core Concept

Description: Fifth part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Date: October 23, 1961
Creator: Combustion Engineering, inc. Nuclear Division.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Criteria for Evaluating Hazards Involved in Proposed Tests On and/or Modifications To the SM-1

Description: Abstract: This technical report elucidates principles of hazards evaluation. The concept of hazards potential is introduced and utilized to show how a reactor system perturbation will influence its nuclear safety. Literature relating to reactor safety is referenced to provide the sources of information required for hazards analysis and show how they influence a hazards evaluation. A checklist of items which should be considered in evaluating a change, test, or modification is presented.
Date: October 18, 1961
Creator: Scoles, J. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Comparison of Radiation-Induced Graft Copolymerization Untilizing Electron Accelerators and Isotope Sources as Radiation Initiators

Description: "A brief examination of the post irradiation grafting of machine irradiated polyethylene film with acrylic acid monomer was made. Evidence of postgrafting was detected in samples that had been irradiated to a total dose of 10 Mrads at a dose rate of 0.01 Mrad/sec. and then exposed to a 25% purified acrylic acid solution in benzene for periods of 1 to 4 days."
Date: October 17, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effect of Radiation Damage on SM-1, SM-1A and PM-2A Reactor Vessels

Description: Report describing the status of the SM-1, SM-1A, and PM-2A reactors, specifically regarding the effects "of irradiation on nil-ductility transition temperature and the associated problem of brittle fracture." (p. iii)
Date: October 14, 1961
Creator: McLaughlin, D. W.; Rowekamp, B. J.; Chittum, R. A.; Coombe, J. R.; Kelleman, R. W.; Bobe, P. E. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Equation of State of Solids at Low Temperature

Description: Technical report describing and evaluating the the three experimental methods for obtaining equation of state data at low temperatures; (1) approximate measurement of the PVT relationship by a piston-displacement technique, (2) the measurement of a heat capacity at constant volume as a function of molar volume and temperature, and (3) direct measurement of the pressure variation of the elastic constants using ultrasonic techniques. X-ray methods also might be applicable.
Date: October 13, 1961
Creator: Bernardes, N. (Newton), 1931- & Swenson, C. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hazards Report for SM-1 Core II With the SM-1 Core II High Burnup Elements Replaced with SM-1 Core I Spare Elements

Description: Abstract: The removal of both SM-1 Core I high burnup elements from the SM-1 Core II and the insertion of two SM-1 Core I spare elements i their places are discussed. Nuclear and thermal characteristics of Core II with the change are presented and conclusion related to the change in hazard potential are made. If the core change indicated by this report is made, local peaking factors will be decreased and burnout ratios will be increased. This, of course, in itself leads to a more conservative… more
Date: October 9, 1961
Creator: Coombe, J. R.; Lee, D. H. & Matthews, F. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hazards Report for SM-1 Core II Without the SM-1 Core I High Burnup Elements and With the PM-1-M-2 Element

Description: Abstract: The removal of both SM-1 Core I high burnup elements from SM-1 Core II and the insertion of the PM-1-M-2 element and the SM-1 Core I spare element in SM-1 Core II is discussed. Nuclear and thermal characteristics of Core II with these changes are presented and conclusions related to the changes in the hazard potential are made. If the core change indicated by this report is made, local peaking factors will be decreased and burnout ratios will be increased. This, of course, in itself… more
Date: October 7, 1961
Creator: Coombe, J. R.; Lee, D. H. & Mathews, F. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Scintillation Spectrometer Measurements of Capture Gamma Rays From Natural Elements: First Quarterly Report

Description: From abstract: "The objective of this program is to make a compilation of neutron capture gamma ray spectra of the naturally occurring elements, covering both the low and high energy region, using Na I(TI) scintillation detectors...During this phase of the program a detection system, together with its associated shielding was constructed and tested."
Date: October 4, 1961
Creator: Greenwood, Reginald C. & Stone, C. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Health and Safety Laboratory Fallout Program Quarterly Summary Report: June 1, 1961 - September 1, 1961

Description: Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date: October 1, 1961
Creator: Hardy, Edward P., Jr.; Rivera, Joseph & Frankel, Robert
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Design Criteria for Irradiated Vessels Task 6.0 Summary Report

Description: Abstract: This technical report presents design criteria to prevent the brittle fracture of ferritic reactor vessels that cold occur as a result of the rise in NDT caused by fast neutron irradiation. The criteria require that maximum principal stress in the vessel does not exceed 18 percent of yield stress at temperatures below NDT + 60 degree F. Under certain conditions the allowable stress may be based on the irradiated yield stress. A discussion of brittle fracture and an explanation of the … more
Date: September 29, 1961
Creator: McLaughlin, D. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Comparison of Radiation-Induced Graft Copolymerization Untilizing Electron Accelerators and Isotope Sources as Radiation Initiators

Description: "A comparison of grafting to two thicknesses of polypropylene film is made using isotope and electron accelerator initiation. The results indicate that the grafting of methacrylic acid: styrene to polypropylene is mainly a surface reaction."
Date: September 12, 1961
Creator: Odian, George; Oliver, William F. & Pierre, Karl
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hazards Evaluation of the SM-1 Penetrated Gasket

Description: Abstract: This technical report describes the as-constructed SM-1 penetrated gasket designed for SM-1 Core and Flow Instrumentation (Task XIV). This report supplements APAE No. 79, The Summary Hazards Report for Task XIV, and evaluates the effects of a postulated failure of this gasket. The effects of failure on the Maximum Credible Accident are determined and conclusions and recommendations for the use of this gasket are made.
Date: September 8, 1961
Creator: Coombe, J. R.; Gebhardt, F. G. & James, B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Steady State and Transient Thermal and Hydraulic Analysis of SM-2 Termination Report

Description: Abstract: Thermal characteristics of the SM-2 core were analyzed at steady state and loss of flow conditions. For steady state operation, the steady state code STDY-3 was used. For transients during a loss of flow accident, ART-02, a one-dimensional code, was used. This analysis indicates the SM-2 core is safe from burnout under steady state operation at design power level (28 tMW) because (1) no nucleate boiling exists, and (2) the minimum burnout ratio is above 2.0. The core is safe from burn… more
Date: September 8, 1961
Creator: Segalman, I. & Bradley, P. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Consolidated Edison Thorium Reactor: Core Assembly Physics and Zero Power Tests Report

Description: Results of zero power tests to confirm the nuclear design of the Consolidated Edison Thorium Reactor Core are presented. The maximum core reactivity, control rod worths, and power distribution were measured.
Date: September 1961
Creator: Edlund, Milton C. (Milton Carl), 1924-; Ball, R. M.; Deddens, J. C. & Flickinger, R. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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