Books on the topic 'Fuel cladding'

Agency, International Atomic Energy, ed. Management of cladding hulls and fuel hardware: Report of a technical committee meeting on management of cladding hulls and fuel hardware. Vienna: International Atomic Energy Agency, 1985.

Flanagan, Michelle. Mechanical behavior of ballooned and ruptured cladding: Prepared by Michelle Flanagan. Washington, DC: U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2012.

Novák, J. Mechanical properties of zirconium alloy cladding tubes and critical fuel element power ramps. Řež, Czechoslovakia: Nuclear Research Institute, Information Centre, 1988.

Carrotte, Jerome. Thermomechanical aspects of pellet-cladding interaction in a pressurised water reactor fuel rod. Birmingham: University of Birmingham, 1995.

Yegorova, L. A. Data base on the behavior of high burnup fuel rods with Zr-1% Nb cladding and UO2 fuel (VVER Type) under reactivity accident conditions. Washington, D.C: U.S. Nuclear Regulatory Commission, 1999.

P, Moeller M., U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Safety Review and Oversight., Pacific Northwest Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Reactor Accident Analysis., eds. The Impact of fuel cladding failure events on occupational radiation exposures at nuclear power plants: Case study. Washington, D.C: Division of Safety Review and Oversight, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1986.

A, Yegorova L., U.S. Nuclear Regulatory Commission., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research., Joint Stock Company "TVEL", Institut problem bezopasnogo ispolʹzovanii︠a︡ i︠a︡dernoĭ ėnergii (Rossiĭskiĭ nauchnyĭ t︠s︡entr "Kurchatovskiĭ institut"), Institut de radioprotection et de sûreté nucléaire., and Gosudarstvennyĭ nauchnyĭ t︠s︡entr Rossiĭskoĭ Federat︠s︡ii "Nauchno-issledovatelʹskiĭ institut atomnykh reaktorov", eds. Experimental study of embrittlement of Zr-1%Nb VVER cladding under LOCA-relevant conditions. Washington, D.C: U.S. Nuclear Regulatory Commission, 2005.

P, Kaplar E., ed. Mechanical properties of unirradiated and irradiated Zr-1% Nb cladding: Procedures and results of low temperature biaxial burst tests and axial tensile tests. Washington, D.C: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2001.

P, Kaplar E., ed. Mechanical properties of unirradiated and irradiated Zr-1% Nb cladding: Procedures and results of low temperature biaxial burst tests and axial tensile tests. Washington, D.C: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2001.

T, Berta V., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research., Idaho National Engineering Laboratory, and EG & G Idaho., eds. Determination of the bias in LOFT fuel peak cladding temperature data from the blowdown phase of large-break LOCA experiments. Washington, DC: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1993.

T, Berta V., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research., Idaho National Engineering Laboratory, and EG & G Idaho., eds. Determination of the bias in LOFT fuel peak cladding temperature data from the blowdown phase of large-break LOCA experiments. Washington, DC: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1993.

R, Theaker J., and International Symposium on Zirconium in the Nuclear Industry (10th : 1994), eds. Fabrication of Zr-2.5Nb pressure tubes to minimise the harmful effects of trace elements. Chalk River, Ont: Fuel Channel Components Branch, Chalk River Laboratories, 1994.

G, Schumacher, Henkel P. R, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research., and Sandia National Laboratories, eds. In-pile observation of fuel and clad relocation during LMFBR core-disruptive accidents. Washington, DC: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.

G, Schumacher, Henkel P. R, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research., and Sandia National Laboratories, eds. In-pile observation of fuel and clad relocation during LMFBR core-disruptive accidents. Washington, DC: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.

G, Schumacher, Henkel P. R, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research., and Sandia National Laboratories, eds. In-pile observation of fuel and clad relocation during LMFBR core-disruptive accidents. Washington, DC: Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.

Pak, Chang-jin. Kyŏngsuro sayong hu haek yŏllyo hwibalsŏng sanhwa kongjŏng kisul kaebal =: Development of voloxidation process for treatment of LWR spent fuel. [Seoul]: Kwahak Kisulbu, 2007.

Pak, Chang-jin. Kyŏngsuro sayong hu haek yŏllyo hwibalsŏng sanhwa kongjŏng kisul kaebal =: Development of voloxidation process for treatment of LWR spent fuel. [Seoul]: Kwahak Kisulbu, 2007.

K, Soppet W., U.S. Nuclear Regulatory Commission. Division of Systems Analysis and Regulatory Effectiveness., and Argonne National Laboratory, eds. Air oxidation kinetics for Zr-based alloys. Washington, D.C: U.S. Nuclear Regulatory Commission, Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regualtory Research, 2004.

International Symposium on Zirconium in the Nuclear Industry (15th 2007 Sunriver, Or.). Zirconium in the nuclear industry: 15th international symposium. Edited by Kammenzind Bruce, Limbäck Magnus, and ASTM Committee B-10 on Reactive and Refractory Metals and Alloys. West Conshohocken, PA: ASTM International, 2009.

India) International Symposium on Zirconium in the Nuclear Industry (17th 2013 Hyderabad. Zirconium in the nuclear industry: 17th international symposium. Edited by Comstock Robert editor and Barbéris Pierre (Engineer) editor. West Conshohocken, PA: ASTM International, 2015.

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.

International Symposium on Zirconium in the Nuclear Industry (10th 1993 Baltimore, Md.). Zirconium in the nuclear industry: tenth International Symposium. Edited by Garde A. M, Bradley E. Ross, and ASTM Committee B-10 on Reactive and Refractory Metals and Alloys. Philadelphia, PA: ASTM, 1994.

International Symposium on Zirconium in the Nuclear Industry (8th 1988 San Diego, Calif.). Zirconium in the nuclear industry: Eighth international symposium. Edited by Van Swam, Leo F. P., Eucken Craig M. 1951-, ASTM Committee B-10 on Reactive and Refractory Metals and Alloys., International Atomic Energy Agency, and International Symposium on Zirconium in the Nuclear Industry (8th : 1988 : San Diego, Calif.). Philadelphia, PA: ASTM, 1989.

International Symposium on Zirconium in the Nuclear Industry (15th 2007 Sunriver, Or.). Zirconium in the nuclear industry: 15th international symposium. Edited by Kammenzind Bruce, Limbäck Magnus, and ASTM Committee B-10 on Reactive and Refractory Metals and Alloys. West Conshohocken, PA: ASTM International, 2009.

D, Moan Gerry, Rudling Peter, ASTM Committee B-10 on Reactive and Refractory Metals and Alloys., and International Symposium on Zirconium in the Nuclear Industry (13th : 2001 : Annecy, France), eds. Zirconium in the nuclear industry: Thirteenth international symposium. West Conshohocken, Pa: ASTM, 2002.

Commissariat à l'énergie atomique, Cadarache., Direction de l'énergie nucléaire, DEC, Electricité de France, and OECD Nuclear Energy Agency, eds. Pellet-clad interaction in water reactor fuels: Seminar proceedings, Aix-en-Provence, France, 9-11 March 2004. Paris: Nuclear Energy Agency, Organisation for Economic Co-operation and Development, 2005.

Coordinated Research Programme Meeting on Investigation of Fuel Element Cladding Interaction with Water Coolant in Power Reactors (1986 Bhabha Atomic Research Centre). Proceedings of Coordinated Research Programme Meeting on Investigation of Fuel Element Cladding Interaction with Water Coolant in Power Reactors and Topical Meeting on Water Chemistry in Nuclear Energy Systems, Bhabha Atomic Research Centre, Bombay 400085, November 24-28, 1986. Bombay: The Centre, 1986.

Genthon, J. P. Reactor Dosimetry: Dosimetry Methods for Fuels, Cladding and Structural Materials. Dordrecht: Springer Netherlands, 1985.

1951-, Eucken Craig M., Garde A. M, ASTM Committee B-10 on Reactive and Refractory Metals and Alloys., Japan Society of Newer Metals., Nihon Genshiryoku Gakkai, and International Symposium on Zirconium in the Nuclear Industry (9th : 1990 : Kobe, Japan), eds. Zirconium in the nuclear industry: Ninth international symposium. Philadelphia, PA: American Association for Testing and Materials, 1991.

B, Adamson R., Van Swam, Leo F. P., ASTM Committee B-10 on Reactive and Refractory Metals and Alloys., and International Conference on Zirconium in the Nuclear Industry (7th : 1985 : Strasbourg, France), eds. Zirconium in the nuclear industry: Seventh international symposium. Philadelphia, Pa: American Association for Testing and Materials, 1987.

E, Coleman C., and International Symposium on Zirconium in the Nuclear Industry (10th : 1993 : Baltimore, Md.), eds. Mitigation of harmful effects of welds in zirconium alloy components. Chalk River, Ont: Chalk River Laboratories, 1993.

France. Commissariat à l'énergie atomique., ed. Proceedings of the seminar on thermal performance of high burn-up LWR fuel: 3-6 March 1998, Commissariat à lÉnergie Atomique (CEA) Cadarache, France. Paris: Nuclear Energy Agency, Organisation for Economic Co-operation and Development, 1998.

H, Scott H., Meyer R. O, and U.S. Nuclear Regulatory Commission. Division of Systems Analysis and Regulatory Effectiveness, eds. A new comparative analysis of LWR fuel designs. Washington, DC: Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2001.

K, Mikitiouk, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research, Institut I︠A︡dernykh Reaktorov (Rossiĭskiĭ nauchnyĭ t︠s︡entr "Kurchatovskiĭ institut"), and Institut problem bezopasnogo ispolʹzovanii︠a︡ i︠a︡dernoĭ ėnergii (Rossiĭskiĭ nauchnyĭ t︠s︡entr "Kurchatovskiĭ institut"), eds. Modification of IPSN's SCANAIR fuel rod transient code for high burnup VVER fuel. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1999.

D, Lanning D., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Technology., Pacific Northwest National Laboratory (U.S.), and Idaho National Engineering and Environmental Laboratory., eds. FRAPCON-3. Washington, DC: Division of Systems Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1997.

Energy, U. S. Dept of. Report of an investigation into deterioration of the Plutonium Fuel Form Fabrication Facility (PuFF) at the DOE Savannah River Site. Washington, D.C: U.S. Dept. of Energy, Office of Nuclear Safety, 1991.

U.S. Dept. of Energy. Report of an investigation into deterioration of the Plutonium Fuel Form Fabrication Facility (PuFF) at the DOE Savannah River Site. Washington, D.C: U.S. Dept. of Energy, Office of Nuclear Safety, 1991.

U.S. Dept. of Energy. Report of an investigation into deterioration of the Plutonium Fuel Form Fabrication Facility (PuFF) at the DOE Savannah River Site. Washington, D.C: U.S. Dept. of Energy, Office of Nuclear Safety, 1991.

A, Shestopalov, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research, Institut problem bezopasnogo ispolʹzovanii︠a︡ i︠a︡dernoĭ ėnergii (Rossiĭskiĭ nauchnyĭ t︠s︡entr "Kurchatovskiĭ institut"), and Institut I︠A︡dernykh Reaktorov (Rossiĭskiĭ nauchnyĭ t︠s︡entr "Kurchatovskiĭ institut"), eds. Modification of USNRC's FRAP-T6 fuel rod transient code for high burnup VVER fuel. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1999.

A, Berna Gary, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Technology., eds. FRAPCON-3: A computer code for the calculation of steady state thermal-mechanical behavior of oxide fuel rods for high burnup. Wasington, DC: The Commission, 1997.

Causey, A. R. Irradiation-enhanced creep of cold-worked Zr-2.5Nb tubes and helical-springs. Chalk River, Ont: Reactor Materials Research Branch, Chalk River Laboratories, 1993.

1951-, Christodoulou Nicholas C., ed. Modelling irradiation creep of zirconium alloys. Chalk River, Ont: Reactor Materials Research Branch, Chalk River Laboratories, 1993.

Peter, Rudling, and Kammenzind Bruce, eds. Zirconium in the nuclear industry: Fourteenth international symposium. West Conshohocken, Pa: ASTM, 2006.

P, Sabol George, Bradley E. R, and International Symposium on Zirconium in the Nuclear Industry (11th : 1995 : Garmisch-Partenkirchen, Germany), eds. Zirconium in the nuclear industry: Eleventh international symposium. West Conshohocken, PA: ASTM, 1996.

Pierre, Genthon Jean, Röttger Heinz 1927-, American Society for Testing and Materials., Euratom, and GKSS-Forschungszentrum Geesthacht, eds. Reactor dosimetry: Dosimetry methods for fuels, cladding and structural materials : proceedings of the Fifth ASTM-Euratom Symposium on Reactor Dosimetry, GKSS Research Centre, Geesthacht, F.R.G. September 24-28, 1984. Dordrecht, Holland: D. Reidel Pub. Co., 1985.

IAEA. Delayed Hydride Cracking of Zirconium Alloy Fuel Cladding. International Atomic Energy Agency, 2010.

Beverly James Sierer Payson D. Lowe. Cladding Thickness of Fuel Elements by X-Rays. Creative Media Partners, LLC, 2021.

Almarshad, Abdullah I. A. A model for waterside oxidation of zircaloy fuel cladding in pressurized water reactors. 1990.

Ren, Yongli. Fracture toughness behavior of Zircaloy-4 in the form of fuel cladding tubing in nuclear reactors. 2004.

The Impact of fuel cladding failure events on occupational radiation exposures at nuclear power plants: Case study. Washington, D.C: Division of Safety Review and Oversight, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1986.