Risks of non-conservative design according to ASME B31.1 for high-temperature piping subjected to long-term operation in the creep range
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摘要
This study investigates the risks of non-conservative piping design according to ASME B31.1 for hightemperature piping subjected to long-term operation at high temperature in a creep regime based on a sensitivity analysis of the hold time. Design evaluations of hightemperature piping were conducted over a range of hold times in the creep regime according to ASME B31.1,which implicitly considers the creep effects, and the French high-temperature design code of the RCC-MRx, which explicitly considers the creep effects. Conservatisms were quantified among the codes in terms of the hold times. In the case of B31.1, the design evaluation results do not change depending on the hold time at high temperature,whereas in the case of RCC-MRx, they do. It was shown that the design limits of RCC-MRx were exceeded when the hold time exceeded certain values, whereas those of B31.1 were satisfied regardless of the hold times. Thus, the design evaluations according to B31.1 did not consistently yield conservative results and might lead to non-conservative results in the case of long-term operations in the creep range.
This study investigates the risks of non-conservative piping design according to ASME B31.1 for hightemperature piping subjected to long-term operation at high temperature in a creep regime based on a sensitivity analysis of the hold time. Design evaluations of hightemperature piping were conducted over a range of hold times in the creep regime according to ASME B31.1,which implicitly considers the creep effects, and the French high-temperature design code of the RCC-MRx, which explicitly considers the creep effects. Conservatisms were quantified among the codes in terms of the hold times. In the case of B31.1, the design evaluation results do not change depending on the hold time at high temperature,whereas in the case of RCC-MRx, they do. It was shown that the design limits of RCC-MRx were exceeded when the hold time exceeded certain values, whereas those of B31.1 were satisfied regardless of the hold times. Thus, the design evaluations according to B31.1 did not consistently yield conservative results and might lead to non-conservative results in the case of long-term operations in the creep range.
This study investigates the risks of non-conservative piping design according to ASME B31.1 for hightemperature piping subjected to long-term operation at high temperature in a creep regime based on a sensitivity analysis of the hold time. Design evaluations of hightemperature piping were conducted over a range of hold times in the creep regime according to ASME B31.1,which implicitly considers the creep effects, and the French high-temperature design code of the RCC-MRx, which explicitly considers the creep effects. Conservatisms were quantified among the codes in terms of the hold times. In the case of B31.1, the design evaluation results do not change depending on the hold time at high temperature,whereas in the case of RCC-MRx, they do. It was shown that the design limits of RCC-MRx were exceeded when the hold time exceeded certain values, whereas those of B31.1 were satisfied regardless of the hold times. Thus, the design evaluations according to B31.1 did not consistently yield conservative results and might lead to non-conservative results in the case of long-term operations in the creep range.
引文
1.ASME B31.1,ASME Code for Power Piping,ASME(2016)
2.ASME Boiler and Pressure Vessel Code,Section III,Rules for Construction of Nuclear Power Plant Components,Division 5,High temperature reactors,ASME(2017)
3.ASME Boiler and Pressure Vessel Code,Section II Part D,ASME(2017)
4.M.J.Cohn,F.Faham,D.Patel,Ranking of creep damage in main steam piping system girth welds considering multiaxial stress ranges.J.Press.Vessel Technol.138(4),041202(2016).https://doi.org/10.1115/1.4033077
5.M.J.Cohn,Creep life evaluations of ASME B31.1 allowance for variation from normal operation.PRESs VES P,Transactions of ASME,August,138,ASME 041405-1*4(2016)
6.Abram et al.,Status of Fast Reactor Research and Technology Development,IAEA-TECDOC-1691,IAEA(2012)
7.J.-H.Eoh,J.-W.Lee,H.Kim et al.,Sodium Thermal-hydraulic test for design validation of prototype Gen-IV sodium-cooled fast reactor,April 8-11,Charlotte,NC,USA,2018 ICAPP(2018)
8.H.-Y.Lee,K.-N.Song,Y.-W.Kim et al.,An evaluation of creepfatigue damage for prototype process heat exchanger of the NHDD plant.J.Press.Vessel Technol.133(5),051208(2011).https://doi.org/10.1115/1.4003466
9.RCC-MRx,Tome 1,Section III Subsection B,Class 1 N1RXReactor Components its Auxiliary Systems and Supports,AFCEN(2015)
10.H.-Y.Lee,Comparison of elevated temperature design codes of ASME subsection NH and RCC-MRx.Nucl.Eng.Des.308,142-153(2016).https://doi.org/10.1016/j.nucengdes.2016.08.024
11.H.-Y.Lee,J.-B.Kim,J.-H.Eoh et al.,High temperature design and damage evaluation of Mod.9Cr-1Mo steel heat exchanger.No.PVP2011-57756,p.409-416.ASME 2011 Pressure Vessels and Piping Conference,Baltimore,Maryland,July 17-21(2011).https://doi.org/10.1115/pvp2011-57756
12.H.-Y.Lee,J.-B.Kim,H.-Y.Park,Creep-fatigue damage evaluation of sodium to air heat exchanger in sodium test loop facility.Nucl.Eng.Des.250,308-316(2012).https://doi.org/10.1016/j.nucengdes.2012.05.034
13.H.-Y.Lee,H.Kim,J.-B.Kim et al.,Design and integrity evaluation of a finned-tube sodium-to-air heat exchanger in a sodium test facility.J.Press.Vessel Technol.139(3),031203(2016).https://doi.org/10.1115/1.4035038
14.H.-Y.Lee,M.-G.Won,S.-K.Son et al.,Development of a program for high-temperature design evaluation according to RCC-MRx.Nucl.Eng.Des.324,181-195(2017).https://doi.org/10.1016/j.nucengdes.2017.08.034
15.RCC-MRx,Section III Tome 1,Subsection Z,Appendix A3,AFCEN(2015)
16.ASME B31.3,ASME Code for Process Piping,ASME(2016)
2.ASME Boiler and Pressure Vessel Code,Section III,Rules for Construction of Nuclear Power Plant Components,Division 5,High temperature reactors,ASME(2017)
3.ASME Boiler and Pressure Vessel Code,Section II Part D,ASME(2017)
4.M.J.Cohn,F.Faham,D.Patel,Ranking of creep damage in main steam piping system girth welds considering multiaxial stress ranges.J.Press.Vessel Technol.138(4),041202(2016).https://doi.org/10.1115/1.4033077
5.M.J.Cohn,Creep life evaluations of ASME B31.1 allowance for variation from normal operation.PRESs VES P,Transactions of ASME,August,138,ASME 041405-1*4(2016)
6.Abram et al.,Status of Fast Reactor Research and Technology Development,IAEA-TECDOC-1691,IAEA(2012)
7.J.-H.Eoh,J.-W.Lee,H.Kim et al.,Sodium Thermal-hydraulic test for design validation of prototype Gen-IV sodium-cooled fast reactor,April 8-11,Charlotte,NC,USA,2018 ICAPP(2018)
8.H.-Y.Lee,K.-N.Song,Y.-W.Kim et al.,An evaluation of creepfatigue damage for prototype process heat exchanger of the NHDD plant.J.Press.Vessel Technol.133(5),051208(2011).https://doi.org/10.1115/1.4003466
9.RCC-MRx,Tome 1,Section III Subsection B,Class 1 N1RXReactor Components its Auxiliary Systems and Supports,AFCEN(2015)
10.H.-Y.Lee,Comparison of elevated temperature design codes of ASME subsection NH and RCC-MRx.Nucl.Eng.Des.308,142-153(2016).https://doi.org/10.1016/j.nucengdes.2016.08.024
11.H.-Y.Lee,J.-B.Kim,J.-H.Eoh et al.,High temperature design and damage evaluation of Mod.9Cr-1Mo steel heat exchanger.No.PVP2011-57756,p.409-416.ASME 2011 Pressure Vessels and Piping Conference,Baltimore,Maryland,July 17-21(2011).https://doi.org/10.1115/pvp2011-57756
12.H.-Y.Lee,J.-B.Kim,H.-Y.Park,Creep-fatigue damage evaluation of sodium to air heat exchanger in sodium test loop facility.Nucl.Eng.Des.250,308-316(2012).https://doi.org/10.1016/j.nucengdes.2012.05.034
13.H.-Y.Lee,H.Kim,J.-B.Kim et al.,Design and integrity evaluation of a finned-tube sodium-to-air heat exchanger in a sodium test facility.J.Press.Vessel Technol.139(3),031203(2016).https://doi.org/10.1115/1.4035038
14.H.-Y.Lee,M.-G.Won,S.-K.Son et al.,Development of a program for high-temperature design evaluation according to RCC-MRx.Nucl.Eng.Des.324,181-195(2017).https://doi.org/10.1016/j.nucengdes.2017.08.034
15.RCC-MRx,Section III Tome 1,Subsection Z,Appendix A3,AFCEN(2015)
16.ASME B31.3,ASME Code for Process Piping,ASME(2016)