Books on the topic 'The reactor tube'

Canada, Atomic Energy of. Assessment of Beam Tube Performance For the Maple Research Reactor. S.l: s.n, 1985.

Govindan, D. Numerical investigation of heat transfer in the vertical annulus between pressure tube and calandria tube of the advanced heavy water reactor. Mumbai: Bhabha Atomic Research Centre, 2008.

Canada, Atomic Energy of. In-Reactor Deformation of A Pilgerred Cold-Worked zr-2.5 wt% nb Pressure Tube. S.l: s.n, 1985.

Moyer, R. G. Reduction of pressure-tube/calandria-tube contact conductance. Pinawa, Man: Whiteshell Laboratories, 1992.

Abouhadra, Dia Eddin Sadek. Serpentine tube characteristics under accident conditions in gas cooled reactors. Manchester: University of Manchester, 1997.

Chatterjee, S. Estimation of fracture resistance curve of pressure tube from ring tension test. Mumbai, India: Bhabha Atomic Research Centre, 1999.

Rummens, H. E. C. Experimental study of flow patterns near tube support structures. Chalk River, Ont: Chalk River Laboratories, 1994.

Kumar, Sunil. Preferred orientation parameters of KAPS 2 Zr-2.5% Nb pressure tubes. Mumbai: Bhabha Atomic Research Centre, 2005.

S, Chatterjee. Measurement and utility of fracture toughness properties of irradiated pressure tube from the ring tension test. Mumbai: Bhabha Atomic Research Centre, 2004.

Stubbe, E. J. Assessment study of RELAP-5 MOD-2 cycle 36.01: Based on the Doel-2 steam generator tube rupture incident of June 1979. Washington, D.C: U.S. Nuclear Regulatory Commission, 1986.

Chatterjee, S. Conservative estimation of fracture toughness of reactor operated cold worked Zr-2.5% Nb pressure tubes. Mumbai, India: Bhabha Atomic Research Centre, 1999.

Canada, Atomic Energy of. Steam Generator Tube Performance: Experience with Water-Cooled Nuclear Power Reactors During 1983 and 10984. S.l: s.n, 1985.

Chatterjee, S. Measurement and application of fracture toughness properties of ZR-2.5NB pressure tube removed from KAPS-2. Mumbai: Bhabha Atomic Research Centre, 2008.

Singh, R. N. Delayed hydride cracking velocity and crack growth measurement using DCPD technique in Zr-2.5Nb pressure tube material. Mumbai: Bhabha Atomic Research Centre, 2000.

Foley, W. J. Closeout of IE bulletin 78-08: Radiation levels from fuel element transfer tubes. Washington, D.C: U.S. Nuclear Regulatory Commission, 1986.

Workshop, on Steam Generator Tube Integrity in Nuclear Power Plants (1995 Oak Brook Ill ). Proceedings of the CNRA/CSNI Workshop on Steam Generator Tube Integrity in Nuclear Power Plants, held in Oak Brook, Illinois, October 30 - November 2, 1995. Washington, DC: U.S. Nuclear Regulatory Commission, 1997.

Canada, Atomic Energy of. Laser plasma generation of hydrogen-free diamond-like carbon thin films on ZR-2.5Nb CANDU pressure tube materials and silicon wafers with a pulsed high-power CO 2 laser. Chalk River, Ont: Chalk River Nuclear Laboratories, 1995.

Frank, L. Steam generator operating experience update for 1987-1988. Washington, D.C: Division of Engineering and Systems Technology, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1989.

Dodd, C. V. Improved eddy-current inspection for steam generator tubing progress report for period January 1985 to December 1987. Washington, DC: Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1990.

Dodd, C. V. Improved eddy-current inspection for steam generator tubing progress report for period January 1985 to December 1987. Washington, DC: Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1990.

L, McGrew Jay, and Water Engineering Research Laboratory, eds. Wet oxidation of municipal sludge by the vertical tube reactor. Cincinnati, OH: U.S. Environmental Protection Agency, Water Engineering Research Laboratory, 1986.

B, Sanderson D., ed. Reduction of pressure-tube to calandria-tube contact conductance to enhance the passive safety of a CANDU-PHW reactor. Pinawa, Man: Whiteshell Laboratories, 1993.

Reduction of pressure-tube to calandria-tube contact conductance to enhance the passive safety of a CANDU-PHW Reactor. Pinawa, Man: AECL, Whiteshell Laboratories, 1993.

Silver, P., and K. Gilchrist. The Thermal Conductivity of Oxide Layers Formed on the Water Side of a Fast Reactor Evaporator Tube. AEA Technology Plc, 1988.

Centre, Bhabha Atomic Research, ed. Study of hydride blisters grown on Zr-2.5Nb pressure tube spool piece under simulated condition of in-reactor pressure and temperature. Mumbai: Bhabha Atomic Research Centre, 2005.

Haslam, R. J. Pressure Tubes and Their Failures in Pressure Tube Reactors (Risley Technical Services Report). AEA Technology, 1989.

E, MacDonald Philip, U.S. Nuclear Regulatory Commission. Office for Analysis and Evaluation of Operational Data. Division of Safety Programs., Idaho National Engineering Laboratory, and Lockheed Idaho Technologies Company, eds. Steam generator tube failures. Washington, DC: Safety Programs Division, Office for Analysis and Evaluation of Operational Data, U.S. Nuclear Regulatory Commission, 1996.

E, Coleman C., and Chalk River Laboratories, eds. Improving the calandria tubes for CANDU reactors. Chalk River, Ont: Chalk River Laboratories, 1997.

1935-, Causey A. R., and Nuclear Industry Conference (1993 : Baltimore, Md.), eds. On the anisotropy of in-reactor creep of Zr-2.5Nb tubes. Chalk River, Ont: Reactor Materials Research Branch, Chalk River Laboratories, 1993.

1935-, Causey A. R., and Atomic Energy of Canada Limited., eds. On the anisotropy of in-reactor creep of Zr-2.5Nb tubes. Chalk River, Ont: Chalk River Laboratories, 1993.

Lindenschmidt, Karl-Erich *. Sizing cracks in reactor pressure tubes using the crack-tip diffraction method. 1989.

S, Neogy, and Bhabha Atomic Research Centre, eds. A study on metallurgical properties of two zirconium alloys for high burn-up fuel tube applications. Mumbai: Bhabha Atomic Research Centre, 2003.

Voltage-based alternative repair criteria: A report to the Advisory Committee on Reactor Safeguards. Washington, DC: Advisory Committee on Reactor Safeguards, U.S. Nuclear Regulatory Commission, 2001.

Voltage-based alternative repair criteria: A report to the Advisory Committee on Reactor Safeguards. Washington, DC: Advisory Committee on Reactor Safeguards, U.S. Nuclear Regulatory Commission, 2001.

Development of a carbon formation reactor for carbon dioxide reduction: Final report. Windsor Locks, Conn: United Technologies Corporation, Hamilton Standard Division, 1985.

Fong, Randy W. L., 1954- and Chalk River Laboratories, eds. External glass peening of zircaloy calandria tubes to increase the critical heat flux. Chalk River, Ont: Chalk River Laboratories, 1997.

Snell, Douglas C. A study of a diffusionally controlled reactive synthesis process using a multi-tube diffusion flame burner. 1994.

Sui, Yueh Chun. Dynamic simulation of a Westinghouse PWR four-loop plant during steam generator tube rupture event. 1985.

U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Engineering, ed. Circumferential cracking of steam generator tubes. Washington, D.C: U.S. Nuclear Regulatory Commission, 1997.

Singh, R. N., of Materials Science Division, Bhabha Atomic Research Centre. and Bhabha Atomic Research Centre, eds. Delayed hydride cracking velocity and crak growth measurement using DCPD technique in Zr-2.5Nb pressure tube material. Mumbai: Bhabha Atomic Research Centre, 2000.

V, Balakrishnan P., and Chalk River Laboratories. Reactor Chemistry Branch., eds. Hideout of sea water impurities in steam generator tube deposits: Laboratory and field studies. Chalk River, Ont: Reactor Chemistry Branch, Chalk River Laboratories, 1996.

R, Diercks D., Shack W. J, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology., and Argonne National Laboratory. Energy Technology Division., eds. Analysis of potential for jet-impingement erosion from leaking steam generator tubes during severe accidents. Washington, DC: Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2002.

R, Diercks D., Shack W. J, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology., and Argonne National Laboratory. Energy Technology Division., eds. Analysis of potential for jet-impingement erosion from leaking steam generator tubes during severe accidents. Washington, DC: Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2002.

United States. National Aeronautics and Space Administration., ed. Influence of alumina reaction tube impurities on the oxidation of chemically-vapor-deposited silicon carbide. [Washington, DC: National Aeronautics and Space Administration, 1995.

United States. National Aeronautics and Space Administration., ed. Influence of alumina reaction tube impurities on the oxidation of chemically-vapor-deposited silicon carbide. [Washington, DC: National Aeronautics and Space Administration, 1995.

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology. and Argonne National Laboratory, eds. Assessment of current understanding of mechanisms of initiation, arrest, and reinitiation of stress corrosion cracks in PWR steam generator tubing. Washington, DC: Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2000.

U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Engineering., ed. U.S. operating experience with thermally treated Alloy 600 steam generator tubes. Washington, DC: Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 2003.

U.S. operating experience with thermally treated Alloy 600 steam generator tubes. Washington, DC: Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 2003.

U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Engineering., ed. U.S. operating experience with thermally treated Alloy 600 steam generator tubes. Washington, DC: Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 2003.

U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Engineering., ed. U.S. operating experience with thermally treated Alloy 600 steam generator tubes. Washington, DC: Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 2003.