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Aging, shaking, and cracking of infrastructures : from mechanics to concrete dams and nuclear structures

Aging, shaking, and cracking of infrastructures : from mechanics to concrete dams and nuclear structures
紙図書
Victor E. Saouma, M. Anim Hariri-ArdebiliSpringer[2021]<NA21-D2>
国立国会図書館

Safety assessment for research reactors and preparation of the safety analysis report : specific safety guide. STI/PUB/1508 (IAEA safety standards series. Specific safety guide ; no. SSG-20)

Safety assessment for research reactors and preparation of the safety analysis report : specific safety guide. STI/PUB/1508 (IAEA safety standards series. Specific safety guide ; no. SSG-20)
紙図書
International Atomic Energy Agency2012.<A163-B1938>
国立国会図書館全国の図書館

Design of reactor containment systems for nuclear power plants : safety guide. (Safety standards series ; no. NG-G-1.10)

Design of reactor containment systems for nuclear power plants : safety guide. (Safety standards series ; no. NG-G-1.10)
紙図書
International Atomic Energy Agency2004.<A163-B158>
国立国会図書館全国の図書館
  • 件名Nuclear power plants -- Design and construction. Nuclear reactors -- Containment.

An approach for estimating the frequencies of various containment failure modes and bypass events [microform] : draft report for comment / prepared by W.T. Pratt, V. Mubayi ; prepared for Division of Risk Analysis and Applications, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission Rev 1, draft NUREG/CR-6595, Rev.1 BNL-NUREG-52539

An approach for estimating the frequencies of various containment failure modes and bypass events [microform] : draft report for comment / prepared by W.T. Pratt, V. Mubayi ; prepared for Division of Risk Analysis and Applications, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission Rev 1, draft NUREG/CR-6595, Rev.1 BNL-NUREG-52539
マイクロ図書
2003<YCA-Y 3.N 88:25/6595/REV.1/DRAFT>
国立国会図書館
  • 件名Nuclear reactors -- Containment Nuclear power plants -- Risk ...

Fragility modeling of aging containment metallic pressure boundaries [microform] / prepared by B.R. Ellingwood, J.L. Cherry

Fragility modeling of aging containment metallic pressure boundaries [microform] / prepared by B.R. Ellingwood, J.L. Cherry
マイクロ図書
1999<YCA-Y 3.N 88:25/6631>
国立国会図書館
  • 件名Nuclear reactors -- Containment -- Corrosion

An approach for estimating the frequencies of various containment failure modes and bypass events [microform] / prepared by W.T. Pratt ... [et al.]

An approach for estimating the frequencies of various containment failure modes and bypass events [microform] / prepared by W.T. Pratt ... [et al.]
マイクロ図書
1999<YCA-Y 3.N 88:25/6595>
国立国会図書館
  • 件名Nuclear reactors -- Containment Pressurized water reactors

Posttest analysis of the steel containment vessel model [microform] / prepared by J.S. Ludwigsen, V.K. Luk, M.F. Hessheimer

Posttest analysis of the steel containment vessel model [microform] / prepared by J.S. Ludwigsen, V.K. Luk, M.F. Hessheimer
マイクロ図書
2000<YCA-Y 3.N 88:25/6649>
国立国会図書館
  • 件名Nuclear pressure vessels -- Models Nuclear reactors -- Containment

Design, instrumentation, and testing of a steel containment vessel model [microform] / prepared by V.K. Luk ... [et al.]

Design, instrumentation, and testing of a steel containment vessel model [microform] / prepared by V.K. Luk ... [et al.]
マイクロ図書
2000<YCA-Y 3.N 88:25/5679>
国立国会図書館
  • 件名Nuclear pressure vessels -- Models Nuclear reactors -- Containment

Direct containment heating experiments at low reactor coolant system pressure in the Surtsey test facility [microform] / prepared by T.K. Blanchat ... [et al.]

Direct containment heating experiments at low reactor coolant system pressure in the Surtsey test facility [microform] / prepared by T.K. Blanchat ... [et al.]
マイクロ図書
1999<YCA-Y 3.N 88:25/5746>
国立国会図書館
  • 件名Nuclear reactors -- Containment Nuclear reactors -- Cooling

Evaluation of the HDR fire test data and accompanying computational activities with conclusion from present code capabilities [microform] / by Jason Floyd, Lothar Wolf, and John Krawiec (NIST-GCR ; 97-727)

Evaluation of the HDR fire test data and accompanying computational activities with conclusion from present code capabilities [microform] / by Jason Floyd, Lothar Wolf, and John Krawiec (NIST-GCR ; 97-727)
マイクロ図書
1997<YCA-C 13.57/2:97-727>
国立国会図書館
  • 件名Fire testing Nuclear reactors -- Containment

Safeguards techniques and equipment. 2003 ed. (International nuclear verification series ; no. 1 (revised))

Safeguards techniques and equipment. 2003 ed. (International nuclear verification series ; no. 1 (revised))
紙図書
International Atomic Energy Agency2003.<A163-B544>
国立国会図書館全国の図書館
  • 件名...s -- Analysis. Nuclear reactors -- Containment. Environmental sampling. Nucl...

Feasibility of magnetostrictive sensor inspection of containments [microform] / prepared by H. Kwun

Feasibility of magnetostrictive sensor inspection of containments [microform] / prepared by H. Kwun
マイクロ図書
1999<YCA-Y 3.N 88:25/5724>
国立国会図書館
  • 件名Nuclear reactors -- Containment -- Inspection Magnetostrictio...

Vapor explosions in a one-dimensional large-scale geometry with simulant melts [microform] / prepared by H.-S. Park, R. Chapman, M.L. Corradini

Vapor explosions in a one-dimensional large-scale geometry with simulant melts [microform] / prepared by H.-S. Park, R. Chapman, M.L. Corradini
マイクロ図書
1999<YCA-Y 3.N 88:25/6623>
国立国会図書館
  • 件名Light water reactors -- Accidents Nuclear reactors -- Containment -- Accidents

Capacity of steel and concrete containment vessels with corrosion damage [microform] / prepared by J.L. Cherry, J.A. Smith

Capacity of steel and concrete containment vessels with corrosion damage [microform] / prepared by J.L. Cherry, J.A. Smith
マイクロ図書
2001<YCA-Y 3.N 88:25/6706>
国立国会図書館
  • 件名Nuclear reactors -- Containment Nuclear pressure vessels -- C...

Evaluation of AP600 containment thermal-hydraulic performance [microform] / K.M. Campe, J.A. Kudrick

Evaluation of AP600 containment thermal-hydraulic performance [microform] / K.M. Campe, J.A. Kudrick
マイクロ図書
1998<YCA-Y 3.N 88:10/1632>
国立国会図書館
  • 件名Nuclear reactors -- Containment Nuclear power plants -- Safet...

格納容器健全性に関する機器の重要度評価(PWR)

格納容器健全性に関する機器の重要度評価(PWR)
紙図書
原子力安全基盤機構2007.2<NG41-H663>
国立国会図書館

Feasibility of high frequency acoustic imaging for inspection of containments [microform] / prepared by J.E. Bondaryk, C.N. Corrado, V. Godino ; prepared for Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission

Feasibility of high frequency acoustic imaging for inspection of containments [microform] / prepared by J.E. Bondaryk, C.N. Corrado, V. Godino ; prepared for Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
マイクロ図書
1998<YCA-Y 3.N 88:25/6614>
国立国会図書館
  • 件名Nuclear reactors -- Containment -- Testing Acoustic imaging N...

Resolution of the direct containment heating issue for combustion engineering plants and Babcock & Wilcox plants [microform] / prepared by M.M. Pilch ... [et al.]

Resolution of the direct containment heating issue for combustion engineering plants and Babcock & Wilcox plants [microform] / prepared by M.M. Pilch ... [et al.]
マイクロ図書
1998<YCA-Y 3.N 88:25/6475>
国立国会図書館
  • 件名Nuclear reactors -- Containment -- Reliability Pressurized wa...

格納容器健全性に関する機器の重要度評価(BWR)

格納容器健全性に関する機器の重要度評価(BWR)
紙図書
原子力安全基盤機構2006.7<NG41-H599>
国立国会図書館

Pretest round robin analysis of a prestressed concrete containment vessel model [microform] / prepared by V.K. Luk

Pretest round robin analysis of a prestressed concrete containment vessel model [microform] / prepared by V.K. Luk
マイクロ図書
2000<YCA-Y 3.N 88:25/6678>
国立国会図書館
  • 件名...els -- Testing Nuclear reactors -- Containment -- Testing Prestressed concre...
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