Method and apparatus for repairing boiling water reactor shrouds

Induced nuclear reactions: processes – systems – and elements – Reactor protection or damage prevention – Core restraint means

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376285, 376292, G21C 1100, G21C 510

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active

056006896

ABSTRACT:
A method and apparatus for repairing nuclear reactor core shrouds includes applying vertical compressive forces to the shroud in situ to urge opposed ends of the shroud toward one another using a plurality of tie-rods, each including a plurality of coaxial longitudinal members separated by a radial gap filled with reactor coolant or some other damping fluid. One of the longitudinal members is secured to upper and lower portions of the shroud for maintaining a sufficient preload to hold the shroud together and is coupled with one or more other longitudinal members in a manner to transmit axial loads thereto upon extending a predetermined axial distance. A plurality of radial spacers can also be positioned at longitudinally spaced locations along the length of the tie-rod to assure control rod insertion by limiting lateral movement of the shroud and can reduce the preload required for preventing the formation of new cracks and stabilizing existing cracks.

REFERENCES:
patent: 1994322 (1935-03-01), O'Neil
patent: 2865828 (1958-12-01), Long et al.
patent: 2929236 (1960-03-01), Steward et al.
patent: 2950576 (1960-08-01), Rubenstein
patent: 3011962 (1961-12-01), Koch et al.
patent: 3116214 (1963-12-01), Greenstreet
patent: 3215608 (1965-11-01), Guenther
patent: 3445971 (1969-05-01), Desmarchais et al.
patent: 3627634 (1971-12-01), Guenther et al.
patent: 3719555 (1973-03-01), Davis
patent: 3720581 (1973-03-01), Kaser
patent: 3733760 (1973-05-01), Koerner
patent: 3744660 (1973-07-01), Gaines et al.
patent: 3785924 (1974-01-01), Notari
patent: 3850795 (1974-11-01), Thome
patent: 3910447 (1975-10-01), Bevilacqua
patent: 3926722 (1975-12-01), Dupen
patent: 3994776 (1976-11-01), Keller
patent: 4011132 (1977-03-01), Kumpf et al.
patent: 4053080 (1977-10-01), Daublebsky
patent: 4055920 (1977-11-01), Becker
patent: 4056036 (1977-11-01), Kamann et al.
patent: 4057162 (1977-11-01), Gross
patent: 4073685 (1978-02-01), Brown et al.
patent: 4092215 (1978-05-01), Mutzl
patent: 4111327 (1978-09-01), Janakiev
patent: 4165021 (1979-08-01), Dorling
patent: 4192718 (1980-03-01), Janakiev
patent: 4199403 (1980-04-01), Puri et al.
patent: 4199994 (1980-04-01), Beine et al.
patent: 4223797 (1980-09-01), Skakunov
patent: 4265010 (1981-05-01), Doss et al.
patent: 4285503 (1981-08-01), Calhoun et al.
patent: 4299658 (1981-11-01), Meuschke et al.
patent: 4322880 (1982-04-01), Lampe
patent: 4379119 (1983-04-01), Fujimoto
patent: 4409179 (1983-10-01), Burger
patent: 4562332 (1985-12-01), Walter et al.
patent: 4585091 (1986-04-01), Budd
patent: 4596689 (1986-06-01), Gorholt et al.
patent: 4652426 (1987-03-01), Boyle et al.
patent: 4760678 (1988-08-01), Chambers
patent: 4789520 (1988-12-01), Morimoto et al.
patent: 5265392 (1993-11-01), Pedrocco
patent: 5274683 (1993-12-01), Broda et al.
patent: 5319692 (1994-06-01), Hopkins et al.
patent: 5392322 (1995-02-01), Whitling et al.
patent: 5402570 (1995-04-01), Weems et al.
patent: 5430779 (1995-07-01), Baversten et al.
J. S. Abel et al, "Applicability of Pipelocks as a Remedy for Intergranular Stress Corrosion Cracking in BWR's," Int. J. Pres. Ves & Piping 25, pp. 25-46 (1986).
J. S. Abel et al, "Mechanical Methods of Improving Resistance to Stress Corrosion Cracking in BWR Piping Systems," Int. J. Pres. Ves. & Piping 34, pp. 17-29 (1988).
Consumers Power Company, "Report of Operation of Big Rock Point Nuclear Plant," Docket No. 50-155, Forty Pages (Nov. 30, 1964).
Consumers Power Company, "Report of Operation of Big Rock Point Nuclear Plant," Docket No. 50-155, Six Pages (Dec. 30, 1965).
J. E. Corr, "Big Rock Point Nuclear Plant Thermal Shield Instability, Part 1, Redesign and Test Programs," General Electric, San Jose, California, Seventy-Three Pages (Nov. 3, 1966).
BWR Owner's Group, "Recommendations on Inservice Inspection of BWR Internal Components and Attachments," Presented to ASME Section XI Subcommittee on Nuclear Inservice Inspection, 29 Pages (Apr. 1991).
Baltimore Gas and Electric, "Updated Final Safety Analysis Report--Calvert Cliffs, Nuclear Power Plant," Forty-Five Pages (Jul. 20, 1982).
Illustrations of Haddam Neck Nuclear Plant, Figs. 5.3-4 and 04.2-10 (Mar. 1991 and Jun. 1994).
Illustrations of Hatch Nuclear Plant Fig. 3.3-1, Fig. 4.1-1, Fig. 4,2-9 & Fig. 4.1-4.
Kewaunee Reactor Vessel Schematic, Fig. 3.2-1 and Fig 4.2-2, Three Pages (Jul. 1, 1986).
Letter from Nuclear Regulatory Commission to Hatch dated Sep. 30, 1994, Thirteen Pages.
Hatch submittal to Nuclear Regulatory Commission dated Sep. 2, 1994, Nineteen Pages.
Illustration of Indian Point Unit 2, Figs. 2-1, 2-9, 3.2-47 and 3.2-51, Six Pages.
Illustrations of Maine Yankee Atomic Power Station, Fig. 3.3-1, One Page.
U.S. Nuclear Regulatory Commission, "Millstone Final Safety Analysis Report," Aug. 10, 1972, 54 Pages.
Handouts from NRC Meeting with Hatch/GE on Sep. 14, 1994, 211 Pages.
Illustration of Palo Verde Reactor Vertical Arrangement, Fig. 4.4-1, Mar. 1991, One Page.
Illustration of R. E. Ginna Rector Vessel Internals, Fig. 3.9-9 and 3.9-10, Two pages.
Florida Power & Light Company, "Final Safety Analysis Report--vol. 1, St. Lucie Plant," Feb. 28, 1972, Eighty-Four Pages.
Illustration from Shearon Harris Nuclear Power Plant, Carolina Power & Light Company, Final Safety Analysis Report, Fig. 3.92-1, Two Pages.
Yankee Atomic Electric Company, Yankee Rowe Proposal, Oct. 15, 1965, Twenty-Five Pages.
Handouts from NRC meeting with Hatch/GE on Sep. 14, 1994.

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