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Zirconium in the nuclear industry: 17th international symposium : ASTM 17th international symposium on zirconium in the nuclear industry : Feb 2013, Hyderabad, India. (STP ; 1543)

Zirconium in the nuclear industry: 17th international symposium : ASTM 17th international symposium on zirconium in the nuclear industry : Feb 2013, Hyderabad, India. (STP ; 1543)
Paper図書
ASTM International[2015]<M17-15-2362>
National Diet LibraryOther Libraries in Japan
  • Subject HeadingNuclear fuel claddings--Congresses. Zirconium alloys--Congresses.

Zirconium in the nuclear industry: 16th international symposium : May 2010, Chengdu, China. (STP ; 1529)

Zirconium in the nuclear industry: 16th international symposium : May 2010, Chengdu, China. (STP ; 1529)
Paper図書
ASTM Internationalc2011.<M17-12-3235>
National Diet LibraryOther Libraries in Japan
  • Subject HeadingNuclear fuel claddings--Congresses. Zirconium alloys--Congresses.

Zirconium in the nuclear industry: 15th international symposium. : Jun 2007, Sunriver, OR. (STP ; 1505)

Zirconium in the nuclear industry: 15th international symposium. : Jun 2007, Sunriver, OR. (STP ; 1505)
Paper図書
ASTM Internationalc2009.<M17-10-436>
National Diet LibraryOther Libraries in Japan
  • Subject HeadingNuclear fuel claddings -- Congresses. Zirconium alloys -- Congresses.

軽水炉内用材料の高度化試験照射装置の開発と自己修復条件の探索

軽水炉内用材料の高度化試験照射装置の開発と自己修復条件の探索
Paper図書
木下, 智見, 九州大学1995-1997<Y151-H07558070>
National Diet Library
  • Subject Heading...perty hardness zirconium alloy dislocation loop oxidation el...

Zirconium in the nuclear industry: fourteenth international symposium. : Stockholm conference : ASTM symposium on zirconium in the nuclear industry : Jun 2004, Stockholm, Sweden. (STP ; 1467)

Zirconium in the nuclear industry: fourteenth international symposium. : Stockholm conference : ASTM symposium on zirconium in the nuclear industry : Jun 2004, Stockholm, Sweden. (STP ; 1467)
Paper図書
ASTM Internationalc2005.<M17-06-1663>
National Diet LibraryOther Libraries in Japan
  • Subject HeadingNuclear fuel claddings -- Congresses. Zirconium alloys -- Congresses.

Zirconium in the nuclear industry: thirteenth international symposium. : 13th ASTM international symposium on zirconium in the nuclear industry : Jun 2001, Annecy, France. (STP ; 1423)

Zirconium in the nuclear industry: thirteenth international symposium. : 13th ASTM international symposium on zirconium in the nuclear industry : Jun 2001, Annecy, France. (STP ; 1423)
Paper図書
ASTM Internationalc2002.<M17-06-1390>
National Diet LibraryOther Libraries in Japan
  • Subject HeadingNuclear fuel claddings -- Congresses. Zirconium alloys -- Congresses.

The reactions of zinc vapor with Zircaloy-4 and pure zirconium [microform] / Maureen Williams (NISTIR ; 6447)

The reactions of zinc vapor with Zircaloy-4 and pure zirconium [microform] / Maureen Williams (NISTIR ; 6447)
Microform図書
2000<YCA-C 13.58:6447>
National Diet Library
  • Subject HeadingZinc -- Reactivity Zinc coating Zirconium alloys -- Corrosion

Zirconium in the nuclear industry: twelfth international symposium. : 12th ASTM international symposium on zirconium in the nuclear industry : Jun 1998, Toronto, Canada. (STP ; 1354)

Zirconium in the nuclear industry: twelfth international symposium. : 12th ASTM international symposium on zirconium in the nuclear industry : Jun 1998, Toronto, Canada. (STP ; 1354)
Paper図書
ASTMc2000.<M17-06-764>
National Diet LibraryOther Libraries in Japan
  • Subject HeadingNuclear fuel claddings -- Congresses. Zirconium alloys -- Congresses.

Interaction of zinc vapor with Zircaloy and the effect of zinc vapor on the mechanical properties of Zircaloy [microform] / prepared by R.J. Schaefer, R.J. Fields, M.E. Williams

Interaction of zinc vapor with Zircaloy and the effect of zinc vapor on the mechanical properties of Zircaloy [microform] / prepared by R.J. Schaefer, R.J. Fields, M.E. Williams
Microform図書
2000<YCA-Y 3.N 88:25/6675>
National Diet Library
  • Subject HeadingZinc -- Reactivity Zinc coating Zirconium alloys -- Corrosion

Adaptation of USNRC's FRAPTRAN and IRSN's SCANAIR transient codes and updating of MATPRO package for modeling of LOCA and RIA validation cases with Zr-1%Nb (VVER type) cladding [microform] / prepared by A. Shestopalov, K. Lioutov, L. Yegorova NUREG/IA-0209 NSI RRC KI 3067 IRSN-2002/33 (International agreement report ; NUREG/IA-0209)

Adaptation of USNRC's FRAPTRAN and IRSN's SCANAIR transient codes and updating of MATPRO package for modeling of LOCA and RIA validation cases with Zr-1%Nb (VVER type) cladding [microform] / prepared by A. Shestopalov, K. Lioutov, L. Yegorova NUREG/IA-0209 NSI RRC KI 3067 IRSN-2002/33 (International agreement report ; NUREG/IA-0209)
Microform図書
2003<YCA-Y 3.N 88:53/0209>
National Diet Library
  • Subject Heading...ddings Niobium-zirconium alloys Nuclear fuel rods -- Safety ...

Zinc-zircaloy interaction in dry storage casks [microform] / prepared by H. Tsai, Y. Yan

Zinc-zircaloy interaction in dry storage casks [microform] / prepared by H. Tsai, Y. Yan
Microform図書
2001<YCA-Y 3.N 88:25/6732>
National Diet Library
  • Subject HeadingSpent reactor fuels -- Storage Zinc -- Reactivity Zinc coating Zirconium alloys -- Corrosion

Mechanical properties of unirradiated and irradiated Zr-1% Nb cladding [microform] : procedures and results of low temperature biaxial burst tests and axial tensile tests / prepared by E. Kaplar ... [et al.] (International agreement report ; NUREG/IA-0199)

Mechanical properties of unirradiated and irradiated Zr-1% Nb cladding [microform] : procedures and results of low temperature biaxial burst tests and axial tensile tests / prepared by E. Kaplar ... [et al.] (International agreement report ; NUREG/IA-0199)
Microform図書
2001<YCA-Y 3.N 88:53/0199>
National Diet Library
  • Subject Heading...ngs -- Testing Zirconium alloys -- Effect of radiation on Ni...

Zirconium in the nuclear industry : 19th international symposium : hbk

Zirconium in the nuclear industry : 19th international symposium : hbk
Paper図書
editors, Robert J. Comstock and Arthur T. MottaASTM Internationalc20121
Other Libraries in Japan
  • Subject HeadingNuclear fuel claddings -- Congresses Zirconium alloys -- Congresses
  • Subject Heading (ID)Nuclear fuel claddings -- Congresses Zirconium alloys -- Congresses

Zirconium in the nuclear industry : 18th international symposium : pbk

Zirconium in the nuclear industry : 18th international symposium : pbk
Paper図書
editors: Robert J. Comstock and Arthur T. MottaASTM Internationalc2018
Other Libraries in Japan
  • Subject HeadingNuclear fuel claddings -- Congresses Zirconium alloys -- Congresses
  • Subject Heading (ID)Nuclear fuel claddings -- Congresses Zirconium alloys -- Congresses

Zircaloy-4 oxidation at 1300 to 2400°C / prepared by J.T. Prater, E.L. Courtright

Zircaloy-4 oxidation at 1300 to 2400°C / prepared by J.T. Prater, E.L. Courtright
Microform図書
1987<YCA-Y 3.N 88:25/4889>
National Diet Library
  • Subject HeadingZirconium alloys Oxidation

Zirconium in the nuclear industry : 17th international symposium

Zirconium in the nuclear industry : 17th international symposium
Paper図書
editors, Robert Comstock, Pierre BarbérisASTM International2015
Other Libraries in Japan
  • Subject HeadingNuclear fuel claddings -- Congresses Zirconium alloys -- Congresses
  • Subject Heading (ID)Nuclear fuel claddings -- Congresses Zirconium alloys -- Congresses

In-vessel zircaloy oxidation/hydrogen generation behavior during severe accidents / prepared by A.W. Croneberg

In-vessel zircaloy oxidation/hydrogen generation behavior during severe accidents / prepared by A.W. Croneberg
Microform図書
1990<YCA-Y 3.N 88:25/5597>
National Diet Library
  • Subject HeadingZirconium alloys Oxidation Nuclear reactor ac...

Properties of reactor fuel rod materials at high temperatures : final summary report : severe core damage property tests program / prepared by J.T. Prater, E.L. Courtright

Properties of reactor fuel rod materials at high temperatures : final summary report : severe core damage property tests program / prepared by J.T. Prater, E.L. Courtright
Microform図書
1987<YCA-Y 3.N 88:25/4891>
National Diet Library
  • Subject HeadingNuclear fuel rods -- Thermal properties Zirconium alloys Oxidation

Zirconium in the nuclear industry : 16th international symposium

Zirconium in the nuclear industry : 16th international symposium
Paper図書
JAI guest editors, Magnus Limbäck, Pierre BarbérisASTM Internationalc2011
Other Libraries in Japan
  • Subject HeadingNuclear fuel claddings -- Congresses Zirconium alloys -- Congresses
  • Subject Heading (ID)Nuclear fuel claddings -- Congresses Zirconium alloys -- Congresses

Evaluating strength and ductility of irradiated zircaloy, task 5 : quarterly progress report, July-September 1979 / prepared by L.M. Lowry ... [et al.] ; prepared for Division of Reactor Safety Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission

Evaluating strength and ductility of irradiated zircaloy, task 5 : quarterly progress report, July-September 1979 / prepared by L.M. Lowry ... [et al.] ; prepared for Division of Reactor Safety Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
Microform図書
1980<YCA-Y 3.N 88:25/1571>
National Diet Library
  • Subject HeadingZirconium alloys Nuclear fuel claddings
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