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
Annual report of the Liquid Metal Fuel Reactor Experiment describing progress during calendar year 1958 and as well as an evaluation of progress and plans for future work.
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.
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
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.
A monthly report summarizing work perform by Babcock & Wilcox personnel for the U.S. Atomic Energy Commission. Preliminary design studies for nuclear reactor development and its components were reported.
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.
A monthly report summarizing work perform by Babcock & Wilcox personnel for the U.S. Atomic Energy Commission. Initial contacts were made at National Reactor Testing Station and Hanford Works, design conditions for the proposed reactor vessels were reviewed, estimates of heating rates caused by radiation and the pluggage of fuel passages were computed, and design parameters for the LMFRE were established.
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.
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.
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.
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.
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.
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.
This is the first quarterly report which summarizes the project work on the Liquid Metal Fuel Reactor Experiment. As the initial contract was not signed until November, 1956, progress within this reporting period has been limited to establishing objectives, determining what research and development will be required, and selecting preliminary design parameters.
Report concerning preliminary designs of the Liquid Metal Fuel Reactor Experiment (LMFRE) facility. This includes descriptions of the reactor, degasser, and steam system, materials to be used, plant arrangement, building siting, and safety considerations.
Report concerning the technical feasibility of a full-scale Liquid Metal Fuel Reactor, including metallurgical, mechanical, and engineering evaluations.
Report containing descriptions of the Liquid Metal Fuel Reactor Experiment's reactor, containment, and plant design. Includes analyses of associated environmental hazards.
Report containing research and development undertaken regarding the Liquid Metal Fuel Reactor Experiment. This includes engineering information concerning the design, construction, and operation of the experiment.
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.
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.
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.
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.
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.
Quarterly report on the development of a nuclear reactor for merchant ships. This report covers details of a modified propulsion system, completing the basic design of reactor auxiliary systems, control rod effectiveness, and other continued design elements.
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).
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