Maritime Nuclear Steam Generator Progress Report No. 4 PDF Download
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Author: General Electric Company. Nuclear Materials and Propulsion Operation
Publisher:
ISBN:
Category : Propulsion systems
Languages : en
Pages : 142
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Book Description
Author: General Electric Company. Nuclear Materials and Propulsion Operation
Publisher:
ISBN:
Category : Propulsion systems
Languages : en
Pages : 142
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Book Description
Author:
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Category :
Languages : en
Pages : 0
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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).
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Category :
Languages : en
Pages :
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Category :
Languages : en
Pages : 119
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Category :
Languages : en
Pages :
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Category : Marine nuclear reactor plants
Languages : en
Pages : 284
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Author: General Electric Company
Publisher:
ISBN:
Category : Marine nuclear reactor plants
Languages : en
Pages : 96
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Category :
Languages : en
Pages :
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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).
Author: General Electric Company
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ISBN:
Category : Marine nuclear reactor plants
Languages : en
Pages : 101
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Languages : en
Pages :
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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.).
