Download or read book Maritime Nuclear Steam Generator Progress Report No 4 written by General Electric Company. Nuclear Materials and Propulsion Operation and published by . This book was released on 1963 with total page 142 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book 630A MARITIME NUCLEAR STEAM GENERATOR Progress Report No 4 written by and published by . This book was released on 1963 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: Studies showed that four feedwater heaters in cycle give the highest efficiency, but the efficiency is only 0.8 of an efficiency point lower with only one heater. Aftercooling studies showed that the maximum temperature, with a sudden loss in primary cooling, a 1-second scram delay, and a 3-second delay for the aftercooling flow to reach 7.5 lb/ sec, would be 1845 deg F.A study was completed on reducing the length of the reactor vessel by 20.5 inches. This could reduce the system weight by 18 tons. Measurement of a scrammed, flooded cell showed a lower reactivity than a dry cell without the rod inserted. Additional boron worth measurements are required to establish the cold clean reactivity of the critical assembly. The lowest value indicated is about 10.5 per cent DELTA k/k. Studies to position the nuclear sensors in the front shield plug are in progress. This location will provide monitoring of the reactor at ali times and permit servicing of the sensors without disturbing other systems. A modified side shield, which would serve as a total containment vessel is being studied. This concept will provide shielding even in the event of fission product release from both the fuel and the pressure vessel. With this shielded- containment'' concept, the pressure vessel will operate at temperatures close to those of the lower head, thus reducing thermal stresses in these components. The coil for the two-tube boiler test was received; specified fabrication tolerances were exceeded. Studies were made to determine the effect of only shim insert, without period scram, in the intermediate power range. The power levels reached were not excessive, which indicates that it may be possible to bypass period scram at low powers where electrical noise is troublesome. Calculations indicate that the scram time for the first 5-inch insertion of the rods is only 5 per cent longer in water than air. An order was placed for the fabrication and testing of the blower seal. The ORF-3 high burnup test has accumulated 1750 hours at 1450 deg F, which is equivalent to about 12,000 hours of 630A operation. Thermal cycle specimen EB-6 appeared to be in good condition after 5615 hours at 1600 deg F and 44 cycles to room temperature. The shakedown MTR sample 3-F-1 appeared to be in satisfactory condition after 591 hours at 1480 deg F. This sample will be inspected and, if no problems are found, sample 3-F-2 will be inserted for the long-time burnup test. Creep test of fuel sheets have reached 6000 hours at temperatures ranging from 1300 deg to 1800 deg F and stresses of 300 and 600 psi. Maximum elongation recorded is 0.3 per cent, Work is underway on the preparation of a preliminary safety report. All required operntions are being studied and various accidents are being evaluated. Preliminary procedures, equipment, and facilities for handling maintenance operations are being established. The critical experiment reached criticality November 15, 1982, and various measurements such as rod worths, power distributions, boron worths, and cell flooding have been made. (auth).
Download or read book 630A MARITIME NUCLEAR STEAM GENERATOR Progress Report written by and published by . This book was released on 1964 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book 630A Maritime Nuclear Steam Generator written by and published by . This book was released on 1962 with total page 119 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book 630A MARITIME NUCLEAR STEAM GENERATOR Progress Report written by and published by . This book was released on 1964 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book 630A Maritime Nuclear Steam Generator Status Report No 1 written by and published by . This book was released on 1963 with total page 284 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book 630 A MARITIME NUCLEAR STEAM GENERATOR Progress Report written by and published by . This book was released on 1962 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A layout of a reduced-height 630A assembly (34 to 23 ft) was prepared and is presently being evaluated for use in a merchant vessel. While shielding studies indicate the need for some rearrangement of the shield materials, the desired radiation constraint can be obtained without an increase in shielding weight. A preliminary stress analysis of the pressure vessel, flow path analysis, and insulation evaluation was completed and showed no major problems. Evaluation of the total containment design indicates a design pressure of 45 psig. The Critical Experiment (CE) mockup is about 80% complete. The CE tank and dolly is about 50% complete. The CE hazards report was reviewed and approved. The draft of the test program and procedures document is 75% complete. The LPT control room modifications were made, and the draft of the standard operating procedures completed. The CE fuel was inspected and a significant portion was found to be of no use, about 60% requires recoating. Creep and oxidation test time on some of the fuel sheet has exceeded 3000 hr with no significant oxidation or elongation on any of the samples. The nickel -chromium alloy sheet high- temperature (1750 F) stress and oxidating testing have exceeded 5000 hr with elongations below 0.8% except for one sample of 2.3%. Experimental fuel sheet samples were prepared and comparative property studies were ini-tiated. Fabrication of the ring test assembly, 3-F-1, for test in the MTR is essentially complete. The design of the test ring for seal evaluations was initiated. A detailed schedule for the work in FY 63 was prepared and issued for comments and concurrence. (auth).
Download or read book 630A Maritime Nuclear Steam Generator Progress Report written by General Electric Company and published by . This book was released on 1964 with total page 96 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book 630A Maritime Nuclear Steam Generator Progress Report written by General Electric Company and published by . This book was released on 1962 with total page 101 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book 630A MARITIME NUCLEAR STEAM GENERATOR Progress Report written by and published by . This book was released on 1964 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book 630A MARITIME NUCLEAR STEAM GENERATOR PROGRESS REPORT written by and published by . This book was released on 1963 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The current status of the 630A nuclear steam generator program is given. Information is included on the propulsion system, reactor, shield plus, pressure vessel, boiler, controls, primary coolant system, associated test equipment, auxiliary cooling system, critical experiment test operations, handling equipment, facilities and equipment, fuel materials, and safety analysis. (N.W.R.).
Download or read book 630A MARITIME NUCLEAR STEAM GENERATOR Progress Report written by and published by . This book was released on 1964 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This progress report covers the period from November 15, 1963 to February 15, 1964. A study indicated that the most desirable type of blower drive turbine is one using main turbine throttie steam conditions and exhausting to the main turbine cross-over line. Preliminary planning for the initiation of a dynamic structural analyses of the overall steam generator was completed. External pressure loading and thermal stress calculations show that the calandria has a suitable design margin. A revised fuel latch operable from the rear face of the core was designed. A study was initiated to determine the feasibility of substituting Zircaloy for the stainless steel tubing within the active core. Preliminary sizing of control rod extensions and gang plates was completed. Initial loading of the second configuration of the 630A critical experiment reactor was completed. Detailed power distributions were measured in the 11 typical positions. Subcritical and critical rod worth curves were obtained in the critical experiment with up to 132 shim rods in the core. Moderator temperature coefficient measurements were made and agreed well with analytical data. Critical experiment correlation of fine radial power calculations in the revised mock-up showed good agreement. Performance specifications were prepared for a 1-Mw(e) power plant. Parametric thermal analyses, based on various tube sheet thicknesses and heating rates, were completed for the top and bottom tube sheets. The shield plug was redesigned to accommodate additional shim rods and to facilitate fabrication and moderator flow adjustments. Calculations of the operating and shutdown dose at the nuclear sensor location was started. Studies were performed to determine the size of the port openings needed to prevent buckling in the containmert vessel in the event of ship sinking. A blower shaft static seal was built and tested with satisfactory results. Manufacture and procurement of all parts for two developmental dynamic rod actuators were completed. The two-tube boiler was modified and operated satisfactorily on automatic control down to 20 percent power. A reactor control system that meets response and accuracy requirements was simulated on the analog computer. Investigation of a possible test site for power testing the prototype reactor was continued with cost estimates and a facility layout drawing being made for the IET facility at ITS. Specimen ORF-4 was removed from test after 4800 hours of actual operation at 1300 deg F, equivalent to approximately 15,000 hours of full- power 630A operation. An estimated 40 percent burnup of the /sup 235/U atoms occurred. Creep tests on warm-finished fuel sheet have accumulated more than 12,000 hours at 630A stress and temperature conditions with no greater than 0.75 percent plastic creep. Cladding-stock creep tests have surpassed 15,000 hours at various combinations of stress and temperature with satisfactory results. (auth).
Download or read book 630A MARITIME NUCLEAR STEAM GENERATOR written by and published by . This book was released on 1963 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book 630A MARITIME NUCLEAR STEAM GENERATOR Progress Report written by and published by . This book was released on 1963 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The current status of the 630A Nuclear Steam Generator program is given in a summary of design features, safety assessments, and development work. Thermodynamic studies of the 85-cell 630A indicate that a 63,000 SHP capability can be achieved by using steam as the primary coolant; weight, size, and capital cost would be essentially the same as for the 30,000 SHP air-cooled unit. A lightweight air-cooled 50,000 SHP unit was investigated. The weight of this assembly was estimated to be 446 tons. The power rating of this unit could be increased to 100,000 SHP with steam cooling. Measurements in the critical experiment show that, with a minor redistribution of moderator volume fraction and fuel, the desired gross radial power can be achieved. The two-tube boiler test rig was operated and steam design conditions of 850 psia and 950 deg F were obtained. Stability between tubes was demonstrated in steady state and transient conditions and the feedwater control demonstrated the capability of controlling the steam superheat temperature under steady state and transient conditions. Fabrication of the blower seal test was begun. The ORF-4 fuel burnup sample was placed on test and has accumulated over 200 test hours. The ORF-3 fuel burnup test completed the equivalent of over 20,000 hours of 630A operation. The MTR 3- F-2 fuel burnup sample was removed from test after about 5000 hours at equivalent 630A operation. Laboratory stress and oxidation tests on fuel samples have exceeded 10,000 hours at temperatures above those expected in the 630A without excessive creep and apparently without excessive oxidation. (N.W.R.).
Download or read book 630A MARTIME NUCLEAR STEAM GENERATOR Progress Report written by and published by . This book was released on 1962 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A summary of the progress made on the 630 A Maritime Nuclear Steam Generator is preserted. Information is included on propulsion system investigations, reactor design, side shield development, boiler design, containment development, development of controls, development of primary coolant blowers, development of fuel materials, development of nonfuel materials, critical experiments, safety analyses, and development of facilities and equipment. (J.R.D.).
Download or read book Government wide Index to Federal Research Development Reports written by and published by . This book was released on 1966 with total page 980 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1976-06 with total page 1216 pages. Available in PDF, EPUB and Kindle. Book excerpt:
