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Nuclear Merchant Ship Reactor Project: Status Report on Reactor Safeguards Analysis

Description: The purpose of this report is to describe the nuclear power plant for the N.S. Savannah and the program in progress for the analysis of potential hazards associated with the operation of a nuclear merchant vessel. Particular emphasis is given to the safety features embodied both in the design and operation of the plant.
Date: May 9, 1958
Creator: The Babcock & Wilcox Company
Partner: UNT Libraries Government Documents Department
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Graphite-to-Metal Seal Screening Tests

Description: In the basic design for a two-fluid LMFRE, a seal has to be made between the metal core inlet and the graphite bottom reflector. To evaluate the effectiveness of such a method of sealing, a screening test apparatus was constructed to determine quickly the physical parameters and the best configuration for interface contact
Date: September 1958
Creator: Gilhart, J. S.
Partner: UNT Libraries Government Documents Department
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Liquid Metal Fuel Reactor Experiment: Dynamic Utility Test Loop

Description: This report provides an overview of the creation of the Liquid Metal Fuel Reactor Experiment program. It furthers the work by constructing a single loop to test all the components required for the 16 loop reactor. This utility loop was also constructed to provide a facility for testing various components such as valves and flow meters.
Date: May 5, 1959
Creator: Baker, O. H.
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 primary shield tank vary from 3" to 1" in thickness.
Date: April 1958
Creator: Smith, W. R. & Turner, M. A.
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.
Partner: UNT Libraries Government Documents Department
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Transient Flow Performance in a Multi-Loop Nuclear Reactor System

Description: The method present can be used to determine fluid flow and coolant pump speed transients in a nuclear reactor system. Included are transients due to power failure, starting pumps in idle loops, and the opening of an active pump's discharge. Parallel pumps in the system may be analysed independently of each other. Typical cases are presented for the N.S. Savannah (NMSR) and Consolidated Edison Thorium Reactor (CETR).
Date: December 1959
Creator: Boyd, George M., Jr.; Rosser, Ralph M. & Cardwell, Bennett B., Jr.
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.
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 temperature.
Date: June 1960
Creator: Clark, R. H.; Barrett, L. G. & Funderburg, J. M.
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.
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.
Partner: UNT Libraries Government Documents Department
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Liquid Metal Fuel Reactor Experiment Monthly Progress Statement: February 1957

Description: A monthly report summarizing work perform by Babcock & Wilcox personnel for the U.S. Atomic Energy Commission. Included in this report was a study made regarding the possible use of beryllium as a core moderating material, calculations made regarding temperature distribution for various channel sizes and power levels, design parameters for initial operation of the LMFRE, and other work in the design and operation of the reactor.
Date: February 1957
Creator: Babcock & Wilcox Company
Partner: UNT Libraries Government Documents Department
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Liquid Metal Fuel Reactor Experiment Monthly Progress Statement: March 1957

Description: A monthly report summarizing work perform by Babcock & Wilcox personnel for the U.S. Atomic Energy Commission. In this monthly report work was reported on a completed study of the change in critical concentration and critical diameter with small changes in the physical and nuclear parameters of the reference design, reactor design #8 which incorporates an integral graphite core and core tank has been completed and distributed, and other work required for the design and construction of a LMFRE.
Date: March 1957
Creator: Babcock & Wilcox Company
Partner: UNT Libraries Government Documents Department
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Liquid Metal Fuel Reactor Experiment Monthly Progress Statement: April 1957

Description: A monthly report summarizing work perform by Babcock & Wilcox personnel for the U.S. Atomic Energy Commission. In this monthly report information on the reactor design No. 10 had been selected as the LMFRE preliminary reference design, various shielding designs have bee studied, various calculations on multiregion code and reactivity have been continued, and other related to the LMFRE
Date: April 1957
Creator: Babcock & Wilcox Company
Partner: UNT Libraries Government Documents Department
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Nuclear Merchant Ship Reactor: Determination of the Purification Rate for Normal Operation

Description: The objective of this study is to establish a primary loop purification rate for normal operation to (1) maintain the activity created in the primary coolant water by corrosion products and other impurities (excluding fission products) at tolerable level and (2) minimize the crud deposition on the core heat-transfer surfaces.
Date: June 1958
Creator: Babcock & Wilcox Company
Partner: UNT Libraries Government Documents Department
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Liquid Metal Fuel Reactor Experiment Monthly Progress Statement: May 1957

Description: A monthly report summarizing work perform by Babcock & Wilcox personnel for the U.S. Atomic Energy Commission. This month's report includes the Research and Development program was completed, a study of shielding requirements indicated the necessity for test data, more information on studies regarding reactor startup, and other developments related to develop the LMFRE.
Date: May 1957
Creator: Babcock & Wilcox Company
Partner: UNT Libraries Government Documents Department
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Liquid Metal Fuel Reactor Experiment Monthly Progress Statement: June 1957

Description: A monthly report summarizing work perform by Babcock & Wilcox personnel for the U.S. Atomic Energy Commission. This month's report includes information on various factors entering into the estimate of reference design core which has been analyzed for sources of error, further design and testing procedures on the nuclear core, and other work focused on construction and design elements.
Date: June 1957
Creator: Babcock & Wilcox Company
Partner: UNT Libraries Government Documents Department
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Liquid Metal Fuel Reactor Experiment Monthly Progress Statement: July, 1957

Description: A monthly report summarizing work perform by Babcock & Wilcox personnel for the U.S. Atomic Energy Commission. In this months report includes specifications a utility loop, further calculations for fuel rods, drawings were reviewed and specifications for the core reactor were reviewed.
Date: July 1957
Creator: Babcock & Wilcox Company
Partner: UNT Libraries Government Documents Department
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Liquid Metal Fuel Reactor Experiment Monthly Progress Statement: August, 1957

Description: A monthly report summarizing work performed by Babcock & Wilcox personnel for the U.S. Atomic Energy Commission. In this monthly report the R&D budget was reviewed, two-dimensional calculations were performed, analysis work was started on control rods and their housing, as well as continued work on the development of the LMFRE reactor.
Date: August 1957
Creator: Babcock & Wilcox Company
Partner: UNT Libraries Government Documents Department
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Liquid Metal Fuel Reactor Experiment Monthly Progress Statement: September, 1957

Description: A monthly report summarizing work performed by Babcock & Wilcox personnel for the U.S. Atomic Energy Commission. In this month's report comparison of second two-dimensional calculation with the equivalent one-dimensional calculations was performed, reference design core modifications were completed, along with continued work on the design of the core and containment vessel for a LMRFE.
Date: September 1957
Creator: Babcock & Wilcox Company
Partner: UNT Libraries Government Documents Department
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Liquid Metal Fuel Reactor Experiment: Preliminary Hazards Evaluation for the Use of Sodium in the BNL Four-Inch Loop

Description: The contemplated use of sodium in place of bismuth in the secondary system of the Four-Inch Loop at Brookhaven National Laboratory requires a re-evaluation of the loops design. This report covers those design changes deemed necessary for safe operation of the system. It also includes an evaluation of the possible hazards involved and methods of coping with them. No attempt is made here to cover the hazards of sodium-bismuth reaction.
Date: October 1957
Creator: The Babcock and Wilcox Company
Partner: UNT Libraries Government Documents Department
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Nuclear Merchant Ship Reactor Project: Technical Progress Report for the Period April 1, 1957-October 1, 1957

Description: Quarterly report on the development of a nuclear reactor for merchant ships. Included in this report are costs on testing and development of a core reactor, design and manufacturing techniques, and other elements required for a successful reactor design and functionality.
Date: 1957
Creator: The Babcock & Wilcox Company
Partner: UNT Libraries Government Documents Department
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