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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...

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...

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 allo...

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 allo...

Corrosion of research reactor aluminium clad spent fuel in water. (Technical reports series ; no. 418)

Corrosion of research reactor aluminium clad spent fuel in water. (Technical reports series ; no. 418)
Paper図書
International Atomic Energy Agency2003.<NG71-B19>
National Diet LibraryOther Libraries in Japan
  • Subject HeadingAluminum -- Corrosion. Nuclear fuel claddings. Spent reactor fuels.

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 allo...

Pellet-clad interaction in water reactor fuels : seminar proceedings, Aix-en-Provence, France, 9-11 March 2004 / hosted by CEA Cadarache, DEN, DEC ; in co-operation with EDF ... [et al.]. (Nuclear science)

Pellet-clad interaction in water reactor fuels : seminar proceedings, Aix-en-Provence, France, 9-11 March 2004 / hosted by CEA Cadarache, DEN, DEC ; in co-operation with EDF ... [et al.]. (Nuclear science)
Paper図書
Nuclear Energy Agency, Organisation for Economic Co-operation and Developmentc2005.<DE64-B1582>
National Diet LibraryOther Libraries in Japan
  • Subject HeadingNuclear fuel claddings -- Congresses. Light water re...

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 allo...

バルク金属水素化物の創生と高温物性評価ならびに軽水炉燃料被覆管の健全性評価 : 平成18年度原子力安全基盤調査研究

バルク金属水素化物の創生と高温物性評価ならびに軽水炉燃料被覆管の健全性評価 : 平成18年度原子力安全基盤調査研究
Paper図書
大阪大学2007.3<NG61-H165>
National Diet Library
  • Authority（Subject Heading/altLabel）被覆管 Nuclear fuel claddings

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 HeadingNuclear fuel claddings Niobium-zirconium alloys Nucl...

使用済燃料被覆管の貯蔵施設受入れ時特性評価 平成17年度

使用済燃料被覆管の貯蔵施設受入れ時特性評価 平成17年度
Paper図書
原子力安全基盤機構2006.6<NG61-H152>
National Diet Library
  • Authority（Subject Heading/altLabel）被覆管 Nuclear fuel claddings

Examination of spent PWR fuel rods after 15 years in dry storage [microform] / prepared by R. E. Einziger ... [et al.] NUREG/CR-6831 ANL-03/17

Examination of spent PWR fuel rods after 15 years in dry storage [microform] / prepared by R. E. Einziger ... [et al.] NUREG/CR-6831 ANL-03/17
Microform図書
2003<YCA-Y 3.N 88:25/6831>
National Diet Library
  • Subject Heading...els -- Storage Nuclear fuel claddings -- Testing Nuclear fuel eleme...

被覆管特性評価試験(PWR) (高燃焼度燃料安全裕度確認試験成果報告書 ; 平成17年度 その2)

被覆管特性評価試験(PWR) (高燃焼度燃料安全裕度確認試験成果報告書 ; 平成17年度 その2)
Paper図書
原子力安全基盤機構2006.8<NG61-H151>
National Diet Library
  • Authority（Subject Heading/altLabel）被覆管 Nuclear fuel claddings

バルク金属水素化物の創生と高温物性評価ならびに軽水炉燃料被覆管の健全性評価

バルク金属水素化物の創生と高温物性評価ならびに軽水炉燃料被覆管の健全性評価
Paper図書
大阪大学2006.3<NG61-H139>
National Diet Library
  • Authority（Subject Heading/altLabel）被覆管 Nuclear fuel claddings

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 HeadingNuclear fuel claddings -- Testing Zirconium alloys -...

被覆管破損機構に係る調査および計算科学評価 (高燃焼度燃料安全裕度確認試験成果報告書 ; 平成16年度 その1)

被覆管破損機構に係る調査および計算科学評価 (高燃焼度燃料安全裕度確認試験成果報告書 ; 平成16年度 その1)
Paper図書
原子力安全基盤機構2005.11<NG61-H133>
National Diet Library
  • Authority（Subject Heading/altLabel）被覆管 Nuclear fuel claddings

ODSフェライト鋼被覆管の材料強度基準(暫定案) : 研究報告書 (JNC TN9400 ; 2005-15)

ODSフェライト鋼被覆管の材料強度基準(暫定案) : 研究報告書 (JNC TN9400 ; 2005-15)
Paper図書
核燃料サイクル開発機構大洗工学センター2005.2<NG61-H122>
National Diet Library
  • Authority（Subject Heading/altLabel）被覆管 Nuclear fuel claddings

BOR-60第2期照射試験用上部端栓付ODS鋼被覆管の製造 : 製造条件設定試験及び製品製作 : 試験報告 (JNC TN8430 ; 2004-3)

BOR-60第2期照射試験用上部端栓付ODS鋼被覆管の製造 : 製造条件設定試験及び製品製作 : 試験報告 (JNC TN8430 ; 2004-3)
Paper図書
核燃料サイクル開発機構東海事業所2005.3<NG61-H104>
National Diet Library
  • Authority（Subject Heading/altLabel）被覆管 Nuclear fuel claddings

バルク金属水素化物の創生と高温物性評価ならびに軽水炉燃料被覆管の健全性評価

バルク金属水素化物の創生と高温物性評価ならびに軽水炉燃料被覆管の健全性評価
Paper図書
大阪大学2005.3<NG61-H100>
National Diet Library
  • Authority（Subject Heading/altLabel）被覆管 Nuclear fuel claddings

高燃焼度燃料破損限界試験成果報告書 平成22年度

高燃焼度燃料破損限界試験成果報告書 平成22年度
Paper図書
原子力安全基盤機構2012.12<NG71-L2>
National Diet Library
  • Authority（Subject Heading/altLabel）核燃料サイクル 被覆管 原子炉燃料 原子燃料 Nuclear fuels Nuclear fuel claddings
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