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NS Savannah Replacement Control Rod Drives Safeguards Report. Volume II. Description of System Modifications and Hazards Analysis

Description: Report discussing safeguards on operation of the NS Savannah with the replacement rod drive system. This volume includes a description of system modifications and a casualty analysis of the replacement drive system. Included is a description of the replacement control rod drive installation on the Savannah, the rod drive reliability, reactor control and rod program analysis, accident analysis, and a verification of analog computer results.
Date: October 1962
Creator: Wascher, Robert E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Nuclear Merchant Ship Reactor Project. Extended Zero Power Tests NS Savannah Core I. Final Report

Description: Experiments were performed on the NS Savannah Service Core I to supply irformation on future shipboard operation of the Nuclear Merchant Ship Reactor. Testing of instrumentation equipment was satisfactory. Correction factors for shipboard use were determined. Fast neutron flux, neutron fiux distribution, and stuck control rod studies were carried out successfully, as was a three- dimesional calculation to match two critical rod patterns. (auth)
Date: January 1961
Creator: MacKinney, A. L.; Ball, R. M.; Barksdale, C. E.; Batch, M. L.; Cure, J. W.; Farrar, J. P. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Nuclear Merchant Ship Reactor: Design of the MMSR Primary Shield

Description: The purpose of this report is to describe the shielding calculations and techniques used in sizing the MMSR primary shield, the results obtained, and the resulting shield thicknesses. The present report covers many of the items scheduled for presentation in the final MMSR shield design report to be issued in November of 1958. The primary shield in the MMSR consists of the reflector, thermal shields, pressure vessel wall, a 33" water annulus and a layer of lead shielding at the exterior of the… more
Date: April 1958
Creator: Smith, W. R. & Turner, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Effects of Fuel Rod Fission Product Leakage on the Consolidated Edison Thorium Reactor Plant

Description: Experiments performed by WAPD and others have shown that with fuel in an oxide form, it is possible to continue to operate a nuclear plant with fuel rods that have developed defects with only a small increase in the radiation contamination problem
Date: June 1960
Creator: Montgomery, D. W.; Howard, J. O. & Dodd, R. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Lynchburg Test Reactor: Critical Experiment, Hazard Evaluation

Description: This report summarizes the hazards associated with the operation of the Lynchburg Test Reactor (LTR) critical experiments. The LTR critical experiment program is outlined and the design of the experiment is described. The experiments will provide basic data to check two-dimensional calculational methods and provide information needed in the design of the LTR.
Date: November 1959
Creator: Engelder, T. C. & Schutt, P. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Consolidated Edison Thorium Reactor Hot Exponential Experiment

Description: A series of exponential experiments were performed using Consolidated Edison Thorium Reactor oxide type fuel pins in a light water lattice. These experiments were performed in a new facility where measurements were made at temperatures up to 468 F. In addition, boric acid was added to the system in various concentrations. The main objective of these experiments was to obtain the change in material buckling for the system as operating conditions were changed from ambient temperature to high t… more
Date: June 1960
Creator: Clark, R. H.; Barrett, L. G. & Funderburg, J. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Consolidated Edision Thorium Reactor Physics Design

Description: The nuclear characteristics of the CETR are described. Core operating lifetime, control-rod worth, and power density distribution are discussed in relation to maximizing the core operating life. Other objectives of nuclear design are to minimize the power-density variation and to assure control of the reactor.
Date: July 1960
Creator: Barringer, H. S.; Flickinger, R. B. & Spetz, S. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Lynchburg Test Reactor Summary Hazards Report

Description: The Babcock and Wilcox Company (B&W) proposes to construct and operate a Nuclear Test Reactor on the grounds of the Company's integrated nuclear facilities site, Mt. Athos, near Lynchburg, Virginia. This preliminary Summary Hazards Report present to the U.S. Atomic Energy Commission (AEC), Division of Licensing and Regulations, a description of the facility, the characteristics of the proposed site, and an evaluation of potential hazards to the area surrounding the site of operation.
Date: April 1960
Creator: Kulynych, G. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fuel Element Structural Design and Manufacture for the Consolidated Edison Thorium Reactor Plant

Description: The design of the fuel-element structure for the CETR is described. Component parts of the assembly comprise the fuel-bundle assembly, the fuel-can assembly, the upper transition, the fuel-element spring, and the upper nozzle and seal assembly.
Date: September 1960
Creator: Collings, D. M.; Gestson, D. K.; Andrea, C.; Ferris, H. D.; Boyer, R. L. (Ralph L.), 1910- & Larson, G. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Irradiation Test Program for the Consolidated Edison Thorium Reactor

Description: The Irradiation Test Program for the Consolidated Edison Thorium Reactor was conducted to obtain confirmation of the stability and performance of the reference fuel element materials and of test assemblies under design operation conditions. The irradiated specimens were tested to determine mechanical properties and corrosion resistance to borated water.
Date: August 1960
Creator: Baker, P. B.; Dzura, E. J. & Johnson, C. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Consolidated Edison Thorium Reactor: Reactor Vessel Internal Components Design

Description: The design functions and fabrication details for internal components of the CETR are presented and pertinent analytical stress studies are summarized. Functions of the internal components include proper orientation and support for the fuel elements, proper distribution of primary coolant within the reactor vessel, and the establishment of guide channels for the control rods.
Date: July 1960
Creator: Ficor, J.; Collings, D. M.; Sandrock, R. J. & Kalen, D. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Consolidated Edison Thorium Reactor Control System Design

Description: The Consolidated Edison Thorium Reactor Control System has been designed to provide the operators with a reliable, safe and accurate means of controlling the plant. Manual and automatic positioning of control rods can be accomplished. The automatic plant controller has been designed to meet the design criteria under the representative CETR demanded load changes. Adaptability has been built into the plant controller by providing variable controller adjustments for variations in reactor charac… more
Date: August 1960
Creator: Carson, W. E.; Chubb, W. B.; Pickett, R. T. & Deddens, J. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Corrosion Product Activity Distribution Across the Chemical Process System in the Consolidated Edison Thorium Reactor Plant

Description: A study has been performed to determine the corrosion product and water impurity activities in the CETR Chemical Process System. A simplified mathematical model is used to represent the physical situation; however, the magnitude of the activities, taken at the end of the core life to represent the most conservative case, is considered sufficiently accurate for engineering calculations.
Date: August 1960
Creator: Babcock & Wilcox Company
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Geometric and Temperature Effects in Thorium Resonance Capture for the Consolidated Edison Thorium Reactor

Description: Although there have been several previous investigations of neutron resonance absorption in thorium, knowledge in this area has not been sufficiently accurate nor extensive enough to satisfy the practical requirements of thorium breeder reactor design. The present experiment was performed in an effort to reduce this uncertainty by checking and extending the results of previous measurements of the geometric and temperature dependence of thorium resonance integrals. The experimental procedure w… more
Date: June 1960
Creator: Pettus, W. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Design of the Movable and Fixed Control Components for the Consolidated Edison Thorium Reactor

Description: Prototype testing and thorough design analyses have proven the control components for the Consolidated Edison Thorium Reactor are adequate to withstand loads imposed during operation and handling. Assumptions made in the design analyses and cycles run during prototype testing subjected the components to more rigid conditions that are anticipated during actual operation. Results indicate the control components meet their design requirements.
Date: August 1960
Creator: Gestson, D. K.; Collings, D. M. & Maynard, W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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