Technical Report Archive & Image Library (TRAIL) - 65 Matching Results
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- Gel-Addition Process Chemical Studies: Quarterly Progress Report Number 18, November 1970 - January 1971
- Quarterly progress report on activities of a project to develop "a sol-gel process and related processes for preparing (U, Pu)O2 fast reactor fuels" (abstract).
- 1000-MWe LMFBR Follow-On Study, Task I Report: Volume 5, Concept IV System Description
- From introduction: "The last of four designs to be developed by Babcock & Wilcox (B&W), Concept IV observes ground rules established under the LMFBR Follow-On Program and is based on the estimated state of technology in 1980."
- 1000-MWe LMFBR Follow-On Study, Task I Report: Volume 4, Concept III System Description
- From introduction: "The third of four designs to be developed by Babcock & Wilcox (B&W), Concept III observes ground rules established under the LMFBR Follow-On Program and is based on the estimated state of technology in 1980."
- 1000-MWe LMFBR Follow-On Study, Task I Report: Volume 1
- From introduction: "The objective of this study is to provide information that will assist the Atomic Energy Commission in furthering the National Liquid Metal Fast Breeder Reactor (LMFBR) Program. We plan to accomplish this end, in part, by extending the original studies to include system and component design and parametric evaluations of the nuclear steam supply system and its related systems and subsystems based on an estimation of the state of technology in 1980."
- 1000-MWe LMFBR Follow-On Study, Task I Report: Volume 3, Concept II System Description
- From introduction: "This report has been prepared in conjunction with the Liquid Metal Fast Breeder Reactor (LMFBR) Follow-On Study. It is the Concept II description of Task I as outlined by Argonne National Laboratory (ANL) in Appendix C of their Follow-On-Study Program."
- 1000-MWe LMFBR Follow-On Study, Task I Report: Volume 2, Concept I System Description
- From introduction: "This report has been prepared in conjunction with the Liquid Metal Fast Breeder Reactor (LMFBR) Follow-On Study. It is the Concept I description of Task I as outlined by Argonne National Laboratory (ANL) in Appendix C of their Follow-On Study Program."
- Evaluation of Thorium Fuels for the Heavy Water Organic Cooled Reactor
- From abstract: "A summary of work done by The Babcock & Wilcox Company to evaluate thorium fuels for the Heavy Water Organic Cooled Reactor (HWOCR)."
- Irradiation Performance of Thoria-Urania Fuel Materials: Quarterly Technical Report, Number 2, October - December 1964
- From introduction: "Complete exploitation of the advantages of thorium as a fertile material in thermal and particular resonant spectrum reactors has been inhibited by the lack of quantitative physical property data for thoria and thoria-urania fuels."
- NS Savannah Upgrading Analog Computer Analysis
- From abstract: "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."
- Consolidated Nuclear Steam Generator for Merchant Ship Application: A Conceptual Design
- Report concerning the economic feasibility of pressurized water reactors for use aboard merchant ships. This includes conceptual designs and work remaining for the future of a Pressurized Water Reactor.
- Preliminary Hazards Summary Report: Babcock & Wilcox Test Reactor
- This preliminary Hazards Summary Report presents to the Atomic Energy Commission (AEC), Division of Licensing and Regulation, a description of the Nuclear Development Center, the characteristics of the proposed site, and an evaluation of the potential hazards associated with operating the test reactor at this location.
- Consolidated Edison Thorium Reactor: Core Assembly Physics and Zero Power Tests Report
- Results of zero power tests to confirm the nuclear design of the Consolidated Edison Thorium Reactor Core are presented. The maximum core reactivity, control rod worths, and power distribution were measured.
- Development and Testing of Low Cost Fuel Elements for Power Reactor Service
- The development of swaging and vibratory compaction process for fabrication of clad UO2 fuel rods is described. The cost is less than 50% of that for an equivalent core fabricated from pellets. The irradiation testing of vibratory filled and swaged UO2 rods is reported for burn-ups from 2,000 to 12,000 Mwd/t UO2; the results indicate that the rods are capable of excellent performance power reactors.
- Fuel Element Structural Design and Manufacture for the Consolidated Edison Thorium Reactor Plant
- 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.
- Consolidated Edison Thorium Reactor Control Rod Drive Line Testing
- The adequacy of the Consolidated Edison Thorium Reactor (CETR) control rod drive line operation was evaluated and proven by the development program described in this report. This program also included evaluation of materials and fabrication processes.
- Consolidated Edison Thorium Reactor Control System Design
- 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 characteristics. Extensive analog studies have been made of the various plant parameters and their effect on control was carefully evaluated. These analog studies have shown that the control system will perform in a satisfactory manner under the most adverse plant conditions.
- Corrosion Product Activity Distribution Across the Chemical Process System in the Consolidated Edison Thorium Reactor Plant
- 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.
- Design of the Movable and Fixed Control Components for the Consolidated Edison Thorium Reactor
- 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.
- Irradiation Test Program for the Consolidated Edison Thorium Reactor
- 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.
- Consolidated Edision Thorium Reactor Physics Design
- 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.
- Consolidated Edison Thorium Reactor Critical Experiments with Oxide Fuel Pins
- This report describes the critical experiments with pin-type oxide fuel elements for the Consolidated Edison Thorium Reactor (CETR). This report also describes the measurements and gives a brief interpretation of the results in some cases
- Consolidated Edison Thorium Reactor: Reactor Vessel Internal Components Design
- 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.
- Control Blade Worth by Partial Water Height and Soluble Boron Methods
- The series of experiments described in this paper was performed to determine reactivity values of various patterns of fully inserted cruciform control blades. The experiments yielded the worth of fully inserted blade patterns in terms of their holddown characteristics.
- Thermal and Hydraulic Design of the Consolidated Edison Thorium Reactor
- This report presents the thermal and hydraulic analyses, both steady state and transient, for the CETR. Methods of calculations are discussed and results of analyses are presented. Steady state analyses are included for: pressure drops, flow distribution, orificing, burnout, fuel central melting, local boiling, and bulk boiling. Transient analyses are performed for several loss of forced coolant flow incidents.
- Consolidated Edison Thorium Reactor Hot Exponential Experiment
- 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.
- The Effects of Fuel Rod Fission Product Leakage on the Consolidated Edison Thorium Reactor Plant
- 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
- Functional Design Analysis of the Pressurizer for the Consolidated Edison Thorium Reactor Plant
- The pressurizer system and its related design and operating data are described. The philosophy and analytical procedures used in the design of the pressurizer for the Consolidated Edison Thorium Reactor are summarized
- Geometric and Temperature Effects in Thorium Resonance Capture for the Consolidated Edison Thorium Reactor
- 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 was the determination of reactivity coefficients by measurements of reactor period in the Lynchburg Pool Reactor.
- Thorium Uranium Physics Experiments: Final Report
- Report concerning the "study of uniform lattice cores moderate with light water" (p. xiii) and comparing the measurements with various theoretical models. Includes descriptions of the cores, core measurements, leakage experiments, and calculations.
- Lynchburg Test Reactor Summary Hazards Report
- 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.
- Liquid Metal Fuel Reactor Experiment: Induction Welding for Remote Maintenance -- Final Report
- Report concerning the technical feasibility of induction welding for use in remote maintenance at the Liquid Metal Fuel Reactor Experiment. Includes descriptions of the device used, test procedures, and results.
- The Liquid Metal Thorium Breeder Reactor
- From introduction: "Investigation of breeding potential and technical and economic feasibility of breeding in the Liquid Metal Fuel Reactor concept."
- Liquid Metal Fuel Reactor Experiment, Cavitation by Bismuth
- From abstract: "Croloy 2 - 1/4 was tested to determine the causes and effects of cavitation in dynamic liquid bismuth solutions."
- Transient Flow Performance in a Multi-Loop Nuclear Reactor System
- 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).
- Lynchburg Test Reactor: Critical Experiment, Hazard Evaluation
- 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.
- Liquid Metal Fuel Reactor Experiment: Dynamic Utility Test Loop
- 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.
- Liquid Metal Fuel Reactor Experiment Annual Technical Report: 1958
- 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.
- Liquid Metal Fuel Reactor Experiment Quarterly Technical Report: July - September 1958
- Report containing research and development undertaken regarding the Liquid Metal Fuel Reactor Experiment.
- Graphite-to-Metal Seal Screening Tests
- 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
- Core Design and Characteristics for the Consolidated Edison Reactor
- The general purpose of this report is to present the major characteristics and design of the Consolidated Edison Thorium Reactor (CETR) core
- Nuclear Merchant Ship Reactor: Determination of the Purification Rate for Normal Operation
- 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.
- Nuclear Merchant Ship Reactor Project: Status Report on Reactor Safeguards Analysis
- 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.
- Liquid Metal Fuel Reactor Experiment, Quarterly Technical Report: April 1958 - June 1958
- Quarterly technical report discussing progress and activities of the Liquid Metal Fuel Reactor Experiment.
- Nuclear Merchant Ship Reactor: Design of the MMSR Primary Shield
- 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.
- Chemical processing methods and economics for various liquid metal fuel reactors
- From abstract: "The economic factors of chemical processing of the fuel and blanket from liquid bismuth fuel reactors are described and evaluated."
- Nuclear Merchant Ship Reactor Project: Technical Progress Report for the Period October 1957-December 1957
- 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.
- Liquid Metal Fuel Reactor Experiment: Preliminary Hazards Evaluation for the Use of Sodium in the BNL Four-Inch Loop
- 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.
- Liquid Metal Fuel Reactor Experiment Monthly Progress Statement: September, 1957
- 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.
- Liquid Metal Fuel Reactor Experiment Monthly Progress Statement: August, 1957
- 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.
- Liquid Metal Fuel Reactor Experiment: Reference Design Report
- 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.