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NaK FREE CONVECTION COOLED SHAFT FREEZE SEAL FOR SRE PUMPS

Description: An investigation was conducted to determine the feasibility of using an NaK free-convection-cooled shaft freeze seal on the SRE main sodium pumps. The use of sodium in this application instead of tetralin eliminates the carburization hazard present should the seal coolant-(tetralin) leak into the sodium system. Results and recommendations are included. (J.R.D.)
Date: June 18, 1959
Creator: Perez, F.
Partner: UNT Libraries Government Documents Department

CONTROL OF OXYGEN CONCENTRATION IN A LARGE SODIUM SYSTEM

Description: Data on the performances of two types of cold traps in the 50,000-lb radioactive sodium system at the SRE are tabulated. The rates were determined when trap inlet oxygen concentrations were at 8 to 10 parts per million. Oxygen concentration was readily controlled to 8 ppm using a cold trap. Extraction of oxygen from sodium by zirconium at 1200 deg F (hot trapping) reduces the concentration below the limit of detection, i.e., oxide solubility saturation temperature below 225 deg F. The theoretical limit for the equilibrium oxygen concentration was calculated to be less than 7 x 10/sup -6/ ppm. The observed extraction rate of 0.009 lb oxygen/hr was one-half of the rate predicted from material behavior studies. (auth)
Date: December 1, 1959
Creator: Hinze, R B
Partner: UNT Libraries Government Documents Department

MEASUREMENT OF THE SRE AND KEWB PROMPT NEUTRON LIFETIME USING RANDOM NOISE AND REACTOR OSCILLATION TECHNIQUES

Description: The prompt neutron lifetime of the SRE was measured by both the oscillation and random noise techniques. Measurement by use of the oscillation technique gave a prompt neutron lifetime of (5 25 plus or minus 0 35) x 10/sup - 4/ sec for a calculated beta of 7 x 10/sup -3/. The measured noise response indicated a lifetime of (5.25 plus or minus 0.7) x 10/sup -4/ sec. Both measured values are in agreement with the calculated value of 5 x 10/sup -4/ sec. Four experiments utilizing the noise analysis technique were performed to determine the prompt neutron lifetime of the KEWB. All four experiments gave results which agreed within 3%, For an estimated beta of 8 x 10/sup -3/, the measured value obtained was (7.8 plus or minus 0.3) x 10/sup -5/ sec. This is in reasonable agreement with both the energy independert calculated value of 6.6 x 10/sup -5/ see and the value of 6.2 x 10/sup -5/ sec obtained from the experimental inhour equation The oscillation technique has been found to be better suited for lifetime determinations in reactors where the prompt neutron break frequency is less than 5 cps. Reactor noise analysis is more suitable for reactors which have prompt neutron lifetime break frequencies above 20 cps. (auth)
Date: October 15, 1959
Creator: Griffin, C.W. & Lundholm, J.G. Jr.
Partner: UNT Libraries Government Documents Department

FLOWSHEET EVALUATION FOR THE DISSOLVING AND NEUTRALIZATION OF SODIUM REACTOR EXPERIMENT USED NUCLEAR FUEL

Description: This report includes the literature review, hydrogen off-gas calculations, and hydrogen generation tests to determine that H-Canyon can safely dissolve the Sodium Reactor Experiment (SRE; thorium fuel), Ford Nuclear Reactor (FNR; aluminum alloy fuel), and Denmark Reactor (DR-3; silicide fuel, aluminum alloy fuel, and aluminum oxide fuel) assemblies in the L-Bundles with respect to the hydrogen levels in the projected peak off-gas rates. This is provided that the number of L-Bundles charged to the dissolver is controlled. Examination of SRE dissolution for potential issues has aided in predicting the optimal batching scenario. The calculations detailed in this report demonstrate that the FNR, SRE, and DR-3 used nuclear fuel (UNF) are bounded by MURR UNF and may be charged using the controls outlined for MURR dissolution in a prior report.
Date: October 30, 2012
Creator: Daniel, W. E.; Hansen, E. K. & Shehee, T. C.
Partner: UNT Libraries Government Documents Department

PRELIMINARY RADIATION SURVEY OF THE SRE

Description: An investigation was conducted to determine radiation dosags rates associated with operation of the Sodium Reactor Experiment at 8.3 Mw. These values were extrapolated to full-power operation. Hadiation survey results are tabulated. (J.R.D.)
Date: September 18, 1957
Creator: Hale, J.P.
Partner: UNT Libraries Government Documents Department

POWER REACTOR FUEL REPROCESSING: MECHANICAL PHASE

Description: An occurrence at the SRE which caused approximately 7 fuel elements to part when being pulled from the reactor complicated reprocessing, however the bulk of the elements may still be reprocessed as planned. New or reworked pants for the mechanical decladder were supplied by the fabricators for rebuilding in ORNL shops. Administrative actions dictated by budgetary considerations include reduction of UO/sub 2/ pellet order to the quantity needed this fiscal year, reduction of Mark III prototype fuel element to 12, stoppage of all work by REE Division personnel, and stoppage of all work not related to SRE fuel element reprocessing. (auth)
Date: September 1, 1959
Creator: Klima, B.B.
Partner: UNT Libraries Government Documents Department

Safety Analysis of the Storage and Handling of the SRE Fuel

Description: "The most hasardous conditions relating to the storage and handling of the SRE fuel are those in which water and fuel form a possible critical assembly. Therefore, this memorandum is primarily devoted to an analysis of the conditions necessary for a critical mixture of water and SRE fuel. Certain special geometries are then analyzed for their safeness."
Date: November 17, 1954
Creator: Williams, R. O.
Partner: UNT Libraries Government Documents Department

RADIAL THERMAL AND FAST NEUTRON FLUX DISTRIBUTIONS IN THE SODIUM REACTOR EXPERIMENT (SRE) AND IN THE TITLE I CONFIGURATION OF THE HALLAM NUCLEAR FACILITY (HNPF)

Description: The thermal neutron flux distributions for the Sodium Reactor Experiment and the Hallam Power Reacter radial shields are calculated by three different methods. The method giving the highest fluxes is used to calculate conservative values of the heat generation rates in these shields. (T.F.H.)
Date: March 27, 1959
Creator: Legendre, P.J.
Partner: UNT Libraries Government Documents Department

Design, Fabrication and Installation of SRE Fuel Element Guide Assembly 7519-44741

Description: The design, fabrication, and installation of a fuel-element guide assembly for the Sodium Reactcr Experiment are described. Improvements in this assembly over other models are outlined, and recommendations for the testing of SRE core elements are presented. (T.F.H.)
Date: November 25, 1960
Creator: Meise, E. R. & Gower, G. C.
Partner: UNT Libraries Government Documents Department

Hanford site sodium management plan

Description: The Hanford Site Sodium Management Plan, Revision 1, provides changes to the major elements and management strategy to ensure an integrated and coordinated approach for disposition of the more than 350,000 gallons of sodium and related sodium facilities located at the DOE`s Hanford Site
Date: September 25, 1995
Creator: Guttenberg, S.
Partner: UNT Libraries Government Documents Department

Sodium Graphite Reactor Quarterly Progress Report for July-September, 1954

Description: Reactivity calculations have been performed for the steady-state Pu feedback technique outlined in the previous progress report. A full-scale power plant study was initiated, based on sodium-graprite technology. A twin-core power plant is now considered to be the most promising configuration. Several design drawings are given of such a reactor, using slightly enriched U to produce Pu amd electrical power. The thermal neutron flux distribution in a cluster of 6 U rods was measured, and the results are compared with previous measurements for 7 rod cluster. The average thermal cycling of hollow U slug elements was begun. Results are given for 500 cycles between 100 and 500 deg C. A series of powder- compacted U alloys were thermal cycled between 200 and 700 deg C. Data on the transfur of radioactivity from Zr by Na has been obtained from a capsule of the first series of three miniharps. Fe, Al, and Cu were immersed in toluene end irradiated at 150 deg F in the MTR-Gamma canal. Toluene is being considered as a shield coolant for the SRE. The effect of 1-Mev electron irradlation on terphenyls was also studied. A venting tube arrangement has been designed for the Zr-canned graphite moderator. A number of thermal insulating brick amd fiber materials were sublected to liquid Na to study deterioration effects. The materials tested were JohnsManville Brick C-16 (Sil-O-Cel mortar), Superex Paste, and Eagle-Pitcher Mineral Wool. Encouraging results were obtained in an efiort to evaluate the effectiveness of Na decontamination by liquid ammonia. Pressure drop and flow characteristics of the latest design SRE fuel element have been completed. Design details of the 2-speed control rod drive assembly are given. Other aspects of the reactor control system, including design and component fabrication, are discussed. Gamma dose rates at the surface of the top shield ...
Date: December 1, 1954
Creator: Siegel, S. & Inman, G. M.
Partner: UNT Libraries Government Documents Department

GAMMA-RAY AND FAST NEUTRON ANNULAR STREAMING EVALUATION THROUGH SODIUM REACTOR EXPERIMENT (SRE)-MARK II CONTROL AND SAFETY ROD ASSEMBLIES

Description: An experimental program was initiated io determine the extent of fast neutron and gamma ray streaming through the SRL Mark II control and safety rods and to evaluate the adequacy of the shielding provided in these control and safety rods. The methods and procedures used to evaluate these problems are routine and proven for determining gamma-ray and fast neutron dosages using radiation sensitive films and gold foils. The final experimental results indicated that no excessive streaming of either gamma rays or fast neutrons is present above or around the SHE Mark II control and safety rods. The analytical attenuation methods used to calculate the fast neutron and gamma-ray streaming dose rates gave results that compared favorably with the experimental data. Even ihough the agreement was favorable, it cannot be concluded that these analyical methods would be equally valid for other annular geometries. Additional experimental work will be necessary in order to establish the validity for performing similar analysis, but the favorable agreement encourages the use of such methods until other methods are determined. (auth)
Date: October 15, 1959
Creator: Anderson, F. D.
Partner: UNT Libraries Government Documents Department

STUDY OF FUEL TEMPERATURE AND FLOW EFFECTS OF PLUGGING IN SRE FUEL CHANNELS

Description: The fuel surface temperatures and flow rate effects which might be produced by plugs in SRE fuel channels were investigated. It was found that plugs which locally insulate more than 20 to 30% of the surface of a fuel rod are dangerous. Heat transfer through the mcderator would not significantly affect the sensitivity of the outlet thermocouple to change in mass flow through a fuel channel, provided the reactor power is above 2 Mw and the channel is not completely plugged. If a 5% or greater increase in a fuel channel DELTA t is taken to indicate that a plug exists in the channel, about 80% of all possible plugs will be detected and roughly 95% of all dangerous plugs will be detected by this criterion. (C.J.G.)
Date: March 15, 1960
Creator: Noyes, R.C.
Partner: UNT Libraries Government Documents Department

OPERATING EXPERIENCE WITH THE SODIUM REACTOR EXPERIMENT AND ITS APPLICATION TO THE HALLAM NUCLEAR POWER FACILITY

Description: The Sodium Reactor Experiment (SRE) was constructed to demonstrate the feasibility of sodium-oooled graphitemoderated reactors for central station power. The operating experience of SRE has provided valuable data for the design of the Hallam Nuclear Power Facillty (HNPF) now under construction. Some of the difficulties found in the SRE, which HNPF will be designed to avoid, are the sodium-sodium intermediate heat exchanger (horizontal position in SRE gave trouble; a vertical position will be used in HNPF), sodium pumps, handling of broken fuel elements, and excessive thermal stresses due to inadequate coolant flow. Other features of HNPF include the addition of an activity monitoring system for the core cover gas, elimination of tetralin for auxiliary cooling of plant equipment, instrumentation of fuel elements, and addition of carbon traps in the primary sodium system. SRE operation has demonstrated unusual reactor stability and capability for rapid power changes. (D.L.C.)
Date: January 1, 1960
Creator: Beeley, R.J. & Mahlmeister, J.E.
Partner: UNT Libraries Government Documents Department

SRE-EDISON PLANT CONTROL SYSTEM

Description: The design of the control system for the steam plant to be used with the SRE is given. Operation of the system is discussed. (C.J.G.)
Date: April 14, 1959
Creator: Hall, R.J.; Bilbao, E.D. & Young, E.
Partner: UNT Libraries Government Documents Department

SRE STANDARD OPERATING PROCEDURES

Description: General SRE operating instructions, limits, and procedures are listed. Specific operating instructions are given for the reactor, sodium heat-transfer systems, sodium service systems, service cooling system, helium system, nitrogen and dehumidification systems, vent system, liquid waste system, fuel handling machine, building ventilation systems, wash cells, emergency power system, pump coolant systems, crane operation, off-normal conditions, and special procedures. (W.D.M.)
Date: June 27, 1960
Creator: Durand, R.E.; Jenkins, O.G.; Johnson, L.L.; Pearson, E.N. & Vorderbrueggen, L.E.
Partner: UNT Libraries Government Documents Department

PROCEDURES FOR LOW-POWER PHYSICS EXPERIMENTS IN THE SRE

Description: A complilation of the procedures for the low-power physics experiments to be performed with the SRE second fuel loading is presented. Reactor power will remain below 120 kw. Critical mass, shim rod worths, statistical weights, isothermal temperature coefficient, and reactor transfer function will be measured. (W.D.M.)
Date: August 1, 1960
Creator: Burton, S.F.; Griffin, C.W.; Keaten, R.W.; Lewis, R.A.; Moser, R.A. & Woodruff, R.W. eds.
Partner: UNT Libraries Government Documents Department