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The Radiation Leakage Survey of the Shield of the Nuclear Ship Savannah

Description: A detailed 4urvey of the radiation from the N.S. Savannah shield was made. The study was accomplished with the reactor at its full power of 69 Mw during a cruise of 2821 miles. The results of the detailed shield survey show that the design dose rate of 0.5 rem/yr for passenger spaces is not exceeded in any region to which passengers have access. ln the area restricted to crew access the design dose rate of 5.0 rem/yr is nowhere exceeded except in a small region on D'' deck in a room to which en… more
Date: August 29, 1962
Creator: Blizard, E.P.; Blosser, T.V. & Freestone, R.M. Jr.
Partner: UNT Libraries Government Documents Department
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MARITIME REACTOR PROGRAM ANNUAL PROGRESS REPORT FOR PERIOD ENDING NOVEMBER 30, 1961

Description: Progress is reported on general support of the NS Savannah, operation of the pressurized-water in-pile loop, and advanced core development. A shield survey, iodine adsorption studies, a bioassay development program, preparation of replacement control rod drives, irradiation testing of pressure-vessel steel, a thermal insulation investigation, and an analysis of primary system components for gamm-emitting elements were carried out in the NS Savannah program. Water- chemistry studies in the press… more
Date: March 1, 1962
Partner: UNT Libraries Government Documents Department
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Feasibility Study of Economics and Performance of Solar Photovoltaics at the Tronox Facility in Savannah, Georgia.

Description: The U.S. Environmental Protection Agency (EPA), in accordance with the RE-Powering America's Land initiative, selected the Tronox Facility site in Savannah, Georgia, for a feasibility study of renewable energy production. The National Renewable Energy Laboratory (NREL) provided technical assistance for this project. The purpose of this report is to assess the site for a possible photovoltaic (PV) system installation and estimate the cost, performance, and site impacts of different PV options. I… more
Date: March 1, 2013
Creator: Kiatreungwattana, K.; Geiger, J.; Healey, V. & Mosey, G.
Partner: UNT Libraries Government Documents Department
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OZONE EXPLOSION IN IRRADIATED CRYOGENIC APPARATUS AND IMPLICATIONS UPON N.S. SAVANNAH GASEOUS WASTE DISPOSAL SYSTEM

Description: The several incidents of ozone explosions in cryogenic apparatus in radiation fields are reviewed. It is concluded that the explosions may be avoided if oxygen regions where, in static systems they tend to concentrate by liquefaction. Such provisions would make the proposed circulating N/sub 2/- cooled trap for the N.S. Savannah off-gas system acceptable if the initial oxygen content of the nitrogen coolant is less than 200 ppm. Higher concentrations are undoubtedly safe but the lack of informa… more
Date: July 24, 1958
Creator: Cottrell, W. B.
Partner: UNT Libraries Government Documents Department
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Local and Regional Economic Benefits from Forest Products Production Activities at the Savannah River Site: 1955-Present

Description: SRS was established in 1951 as a nuclear materials production facility; however, decline in the defense mission budget at SRS has created a major economic impact on the community in the Central Savannah River Area. SRS has been offsetting these effects by producing revenue (80 million dollars to date) from the sale of forest products since 1955 primarily trees, but also pine straw. Revenue has been re-invested into the infrastructure development, restoration and management of natural resources.… more
Date: January 1, 2002
Creator: Teeter, L. & Blake, J.I.
Partner: UNT Libraries Government Documents Department
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TRIP TO ALCO PRODUCTS, KAPL, COMBUSTION ENGINEERING CO. AND FT. BELVOIR (APPR). RE: COOLING WATER ACTIVITY BUILDUP IN PRESSURIZED WATER REACTORS

Description: Several uncertainties associated with predicting activity levels in water-cooled reactors are discussed in connection with development of the Nuclear Merchant Ship Reactor (Maritime Pressurized Water Reactor). (T.R.H.)
Date: August 1, 1958
Creator: Culver, H.N.
Partner: UNT Libraries Government Documents Department
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NS SAVANNAH UPGRADING ANALOG COMPUTER ANALYSIS

Description: An extensive transient analysis was made of the NS Savannah power plant using analog computer technique to determine the control and safety system actions required to prevent plant damage following operating and accident transients. This work amplified previous design studies by considering accidents of greater severity, automatic limiting devices to preclude safety action, and more realistic parameters based on operating experience. The following transients were analyzed; startup accident, rod… more
Date: November 1, 1962
Creator: Rosser, R.M.
Partner: UNT Libraries Government Documents Department
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ACTIVITY RELEASE FROM THE N.S. SAVANNAH IN THE MAXIMUM CREDIBLE ACCIDENT

Description: The release of fission products that would occur following the maximum credible accident aboard the N.S. Savannah has been examined. Four significantly different, but realistic, operating histories were considered. The rate of release of noble gases and of iodine isotopes as a function of time after the accident was determined for each operating history and for both normal and emergency reactor-compartment ventilation systems. The influence of radioactive decay and of the time delay in release … more
Date: October 16, 1963
Creator: Anderson, T. D.; Buchanan, J. R.; Cottrell, W. B.; Fontana, M. H.; Klepper, O. H. & McCurdy, H. C.
Partner: UNT Libraries Government Documents Department
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ULTRASONIC INSPECTION OF A SECTION OF THE NS SAVANNAH PRIMARY PIPING SYSTEM

Description: A section of NS Savannah primary pipe and part of a primary system gate valve were examined ultrasonically to determine whether a fluctuating flow of low- temperature makeup water entering through a nozzle in the valve hsnd damaged the components during service. Examination was prompted by failure of a Vallecitos Boiling Water Reactor (VBWR) recirculating pipe in which makeup water was introduced under conditions similar to those in the Savannah. The ultrasonic equipment was calibrated on spare… more
Date: October 1, 1963
Creator: Johnson, C.R.
Partner: UNT Libraries Government Documents Department
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MARITIME REACTOR PROGRAM. Annual Progress Report for Period Ending November 30, 1962

Description: A survey of the,N. S. Savannah reactor shield was carried out during the report period. The results showed that the shield effectively meets design specifications. Tests of 12 removal by a charcoal unit in the N. S. Savannah reactor emergency ventilation system using 80 to 90% water-saturated air showed a unit efficiency of 99.86 plus or minus 0.07% at the 95% confidence level. Simplified procedures were devised for using shipboard equipment to screen personnel suspected of having body burdens … more
Date: April 1, 1963
Partner: UNT Libraries Government Documents Department
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Vapor Suppression Test Program Report

Description: The Vapor Suppression Test Program conducted under the NS Savannah Upgrading Program demonstrated that the containment of a reactor and its primary system will operate under water, and that a water-filled containment has definite advantages over a standard dry containment. A test facility was constructed to obtain information on condensation, shock formation, and impact forces resulting from an under water pipe rupture. Forty-six rupture tests were conducted with 1- , 2-, 3-, and 6-inch-diamete… more
Date: August 1, 1962
Creator: Luken, R. C. & Leeman, C. A.
Partner: UNT Libraries Government Documents Department
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NEUTRON PHYSICS DIVISION ANNUAL PROGRESS REPORT. Period Ending September 1, 1962

Description: A total of 74 subsections are included in the report. The information in 4 subsections was previously abstracted in NSA. Separate abstracts were prepared for 38 of the subsections. Those sections for which no abstracts were prepared contain information on prompt neutron lifetime, Rover critical experiments, Pu/sup 239/ fission, neutron decay, the O5R code, alpha scattering, 8 and P wavelengths, proton scattering, deuteron scattering, local optical potentials, N. S. Savamah radiation leakage, re… more
Date: January 11, 1963
Partner: UNT Libraries Government Documents Department
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Study of Core Cooling Requirements During NS Savannah Refueling

Description: The requirements for cooling the NS Savannah reactor core during refueling were investigated. The two-part study included analysis of the system required to provide coolant flow to the reactor and to remove the decay heat generated and analysis of flow and temperature characteristics in the reactor during refueling. Since previous investigations of the system requirements were made, this study was concerned primarily with the flow and temperature analysis. (auth)
Date: May 1, 1963
Creator: Hicks, J. H. & Bader, J. F.
Partner: UNT Libraries Government Documents Department
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Radiochemistry During Start-Up and Early Operation of the Nuclear Ship Savannah. Final Report

Description: It was demonstrated that the radioactivity content of the primary system of the N.S. Savannah reactor plant was small and normal during the period of initial criticality and start-up, and during the sea trials and acceptance tests. The principal radioactive constituents (/sup 56/Mn, /sup 41/Ar, /sup 13/N and / sup 18/F) are either intrinsic to the primary system of the pressurized water reactor or are normally found in the coo1ant in concentrations comparable to those observed in this program. … more
Date: July 1, 1962
Creator: Battist, L; Winnowski, W S; Dieterly, D K & Koch, R C
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 1, 1961
Creator: MacKinney, A. L.; Ball, R. M.; Barksdale, C. E.; Batch, M. L.; Cure, J. W.; Farrar, J. P. et al.
Partner: UNT Libraries Government Documents Department
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Preliminary Design Report for the NMSR Pressurized Water Loop at ORR

Description: The design criteria, description, flow diagrams, and some drawings of a pressurized water loop in which reactor operation conditions can be simulated are presented. The prirnary purpose of this test facility is irradiation testing of various versions of fuel elements for use in the Merchant Ship Reactor Program. The loop proper is designed for operation at 625 deg F and 2250 psi with a water flow rate of 90 gpm. Heat exchanger capacity is 150 kw at 300-F system water temperature. Loop construct… more
Date: October 23, 1958
Creator: Dudley, I.T.; Trauger, D.B. & Savage, H.W.
Partner: UNT Libraries Government Documents Department
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MARITIME REACTOR PROJECT ANNUAL PROGRESS REPORT FOR PERIOD ENDING NOVEMBER 30, 1959

Description: During the report period, the nature of the ORNL supporting activities gradually changed, reflecting the progress in the conetruction of the N.S. Savannah. Design reviews continued to require considerable attention. The Inspection Engineering Dept. of the Jab. continued to act as an inspection agency for the ALC, witnessing inspections and tests during fabrication of components of the nuclear reactor system. An enviromnental analysis was made of safeguard aspects of operation of the N.S. Savann… more
Date: January 25, 1960
Partner: UNT Libraries Government Documents Department
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An Evaluation of the Substitution of Zircaloy for Stainless Steel in n.s. Savannah Fuel-Element Containers. Summary Report

Description: The possibility of reducing fuel-cycle costs for the N.S. SAVANNAH by replacing the stainless steel fuelelement containers in the permanent reactor core structure by similar containers of a zirconium alloy was investigated. These containers, although not integral parts of the fuel-bearing components, are located within the active core and divide the core into 32 separate channels into which the fuel elements are placed. Areas of investigation included reactor physics, fuel-cycle economics, mate… more
Date: November 1, 1963
Creator: Anderson, T. D.; Gross, E. E.; McCurdy, H. C.; Schaffer, L. D.; Shobe, L. R. & Whitmarsh, C. L.
Partner: UNT Libraries Government Documents Department
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