Abstract
Materials investigations and materials data are used for the design of nuclear plants, for assessment of possible damage and for the definition of plant life management and plant life extension programmes. This requires the transfer of materials data into design rules and damage assessment procedures. A very important task concerns the conversion of laboratory data which are usually the result of uniaxial tests into multiaxial loading conditions in a machine. Design and safety assessments are done on the basis of design codes describing design procedures and providing also the necessary design data. During operation the design life is consumed and damage (creep, fatigue, corrosion, radiation etc.) develops which needs concepts for damage monitoring (including non-destructive evaluation). Based on the condition of the plant concepts for plant life management and (if required) plant life extension must be developed. The whole chain from multiaxiality to plant life extension is briefly outlined in this chapter.
Access this chapter
Tax calculation will be finalised at checkout
Purchases are for personal use only
References
Tipping PG (ed) (2010) Understanding and mitigating ageing in nuclear power plants. Woodhead Publishing Ltd, Cambridge
Gross D, Hauger W, Schröder J, Wall WA, Bonet J (2011) Engineering mechanics II mechanics of materials. Springer, Berlin
Wikipedia Mechanics http://en.wikipedia.org/wiki/Stress_(mechanics). Accessed 2 Nov 2011
Wikipedia Von Mises http://en.wikipedia.org/wiki/Von_Mises_yield_criterion. Accessed 13 Oct 2011
Michaelsen C, Hoffelner W, Krautzig J (1989) The role of state of stress for the determination of life-time of turbine components. 3rd international conference on biaxial/multiaxial fatigue, Stuttgart, Conference Proceedings, p 20.1
Othman AM, Hayhurst DR, Dyson BF (1993) Skeletal point stresses in circumferentially notched tension bars undergoing tertiary creep modelled with physically based constitutive equations. In: Proceedings of mathematical and physical sciences 441(1912):343–358
Kraus H (1980) Creep analysis. Wiley-Interscience, New York
Hayhurst DR, Leckie FA (1973) The effect of creep constitutive and damage relationships upon the rupture time of a solid circular torsion bar. J Mech Phys Solid 21:431–446
Hayhurst DR (1973) Stress redistribution and rupture due to creep in a uniformly stretched thin plate containing a circular hole. J Appl Mech 40:244–250
Hayhurst DR (1973) The prediction of creep-rupture times of rotating disks using biaxial relationships. J Appl Mech 40:915–920
Neuber H (2001) Kerbspannungslehre, 4th edn. Springer, Berlin
Melton KN, Hoffelner W, Bertilsson JE (1983) Creep-fatigue life-time predictions of notched specimens and components. In: Congress proceedings of international conference advances in life prediction methods, Albany, New York, ASME
Smith RN, Watson P, Topper TH (1970) A stress-strain parameter for the fatigue of metals. J Mater 5(4):767–778
Hoffelner W (1984) On the effect of notches on the high temperature low-cycle-fatigue behaviour of high temperatures alloys. In: Congress proceedings on spring meeting of the French metals society, Paris 22/23 Mai
Terao D (2010) MDEPs approach to achieve global harmonization of nuclear design codes and standards. ANSI NIST nuclear energy standards coordination and standards collaborative. http://publicaa.ansi.org/sites/apdl/Documents/Meetings%20and%20Events/2009%20NESCC/NESCC%20Meeting%20-%20May%2026,%202010/NESCC%2010-019%20-%20MDEP’s%20Approach%20to%20Achieve%20Global%20Harmonization%20of%20Nuclear%20Design%20Codes%20and%20Standards.pdf. Accessed 15 Oct 2011
ASME Boiler and Pressure Vessel Code (2011) Section III: rules for construction of nuclear power plant components
Sims R (2010) Roadmap to develop high temperature gas cooled reactors (HTGRS). ASME Standards Technology LLC
Kernterchnische Anlagen (KTA-rules) (1993) Metallische HTR komponenten. KTA Doc Nrs 3221.x
Pressure Vessel Stresses NAFSEM http://www.nafems.org/resources/knowledgebase/012/. Accessed 3 Nov 2011
Bree J (1967) Elastic-plastic behaviour of thin tubes subjected to internal pressure and intermittent high heat-fluxes with application to fast-nuclear-reactor fuel elements. J Strain Analysis 2:226–238
Riou B (2008) Improvement of ASME section III-NH for grade 91 negligible creep and creep-fatigue. ASME STP-NU-013
Hoffelner W (2009) Creep-fatigue life determination of grade 91 steel using a strain-range separation method. In: Proceedings of the 2009 ASME pressure vessel and piping conference PVP 2009, July 26–30, 2009, Prague, CZ, Paper PVP2009-77705
NIMS metallic materials (2011) Low alloy steels 1 Cr 0.5 Mo http://metallicmaterials.nims.go.jp/metal/view/resultMetalList.html?id=48205401_sc0. Accessed 3 Nov 2011
DIN EN 10222-2 (2000) 13CrMo4-51Cr-0.5Mo
NRIM-Creep Data Sheets No. 14A-1982, 15A-1982, 45-1997 and 6B-2000 (2011) National Research Institute for Metals Tokyo Japan. http://smds.nims.go.jp/MSDS/en/sheet/Creep.html. Accessed 6 Nov 2011
Rieth M (2007) A comprising steady-state creep model for the austenitic AISI 316 L(N) steel. J Nucl Mater 367–370:915–919
NIMS Database (PW required) https://mits.nims.go.jp/db_top_eng.htm
ODIN data information network (PW required) https://odin.jrc.ec.europa.eu/alcor/Main.jsp. Accessed 6 Nov 2011
Ren W (2010) Gen IV materials handbook functionalities and operation (1B)—handbook version 1.1. ORNL/TM-2009/285_1B
IAEA Nuklear Energy Knowledge Resources http://www.iaea.org/inisnkm/nkm/aws/index.html. Accessed 5 Nov 2011
Marriott DL, Westerkamp EJ (2008) In: Proceedings of PVP2008, ASME pressure vessels and piping division conference, 27–31 July 2008, Chicago, Illinois, USA, Paper Nr.: PVP2008-61585
Hoffelner W (2011) Materials databases and knowledge management for advanced nuclear technologies. J Press Vessel Technol 133(1):014505 1–4 doi:10.1115/1.4002262
Koo GH, Lee JH (2008) Development of an ASME-NH program for nuclear component design at elevated temperatures. Int J Press Vessels Pip 85(6):385–393
IAEA (2001) Application of non-destructive testing and in-service inspection to research reactors. Results of a coordinated research project. IAEA-TECDOC-1263
Wüstenberg H, Erhard A, Boehm R (2011) Limiting factors for crack detection by ultrasonic investigation. BAM, Berlin, Germany http://www.ndt.net/article/0198/wues_lim/wues_lim.htm. Accessed 12 Oct 2011
Non-destructive Testing (2011) http://www.ndt-ed.org/AboutNDT/aboutndt.htm. Accessed 3 Nov 2011
Selby G (2008) Flaw characterization techniques for plant components. Nuclear fuels and structural materials for the next generation nuclear reactors embedded topical meeting ANS annual meeting, San Diego
Ultrasonic testing of materials http://www.ndt.net/article/v05n09/berke/berke1.htm. Accessed 4 Nov 2011
Ultrasound phased array (introduction) http://www.ndt.net/article/v07n05/rdtech/rdtech.htm. Accessed 4 Nov 2011
Coleman CE, Cheadle BA, Causey AR, Chow PCK, Davies PH, McManus MD, Rodgers DK, Sagat S, van Drunen G (1989) Evaluation of zircaloy-2 pressure tubes. In: van Swam LFP, Eucken CM (eds) Zirconium in the nuclear industry. ASTM STP 1023 ASTM, pp 35–49
Doig P, Gasper BC (2005) An overview of plant structural integrity assessment. In: Stanley P (ed) Structural integrity assessment. Taylor Francis, pp 163–183
Marder AR (1989) ASM handbook vol 17, nondestructive evaluation and quality control. ASM International, pp 52–56
Acoustic emission testing (displays) http://www.ndt-ed.org/EducationResources/CommunityCollege/Other%20Methods/AE/AE_DateDisplay.htm. Accsessed 4 Nov 2011
Foulds JR, Viswanathan R (2004) Nondisruptive material sampling and mechanical testing. J Nondestr Eval 15(3–4):151–162
Molak RM, Kartal M, Pakiela Z, Manaj W, Turski M, Hiller S, Gungor S, Edwards L, Kurzydlowski KJ (2007) Use of micro tensile test samples in determining the remnant life of pressure vessel steels. Appl Mech Mater 7–8:187–194
Drew M, Humphries S, Thorogood K, Barnett N (2006) Remaining life assessment of carbon steel boiler headers by repeated creep testing. Int J Press Vessels Pip 83:343–348
Foulds JR, Wu M, Srivastav S, Jewett CW, Arlia NG, Williams JF (2006) Small punch testing for irradiation embrittlement—experimental requirements and vision enhancement system. EPRI TR-106638 research project 8046-03, EPRI
Karasawa H, Izumi M, Suzuki T, Nagai S, Tamura M, Fujimori S (2006) Development of under-sodium three dimensional visual inspection technique using matrix arrayed ultrasonic transducer. J Nucl Sci Technol 37(9):769–779
Wallin K (1993) Irradiation damage effects on the fracture toughness transition curve shape for reactor pressure vessel steels. Int J Pres Vess 55:61–79
American Society for Testing and Materials ASTM E 1921-05 (2007) Standard test method for determination of reference temperature, T0, for ferritic steels in the transition range. Annual book of ASTM standards ASTM international, West Conshohocken, pp 1203–1222
Wallin K (1991) Fracture toughness transition curve shape for ferritic structural steels. Joint FEFG/ICF international conference on fracture of engineering materials and structures, Singapore
IAEA (2009) Master curve approach to monitor fracture toughness of reactor pressure vessels in nuclear power plants. IAEA-TECDOC-1631 IAEA, Vienna
Odette GR, Lucas GE (1996) An integrated approach to evaluating the fracture toughness of irradiated nuclear reactor pressure vessels. J Nondestr Eval 15:3–4
IAEA (2001) Reference manual on the IAEA JRQ correlation monitor steel for irradiation damage studies. IAEA-TECDOC-1230
Niffenegger M, Leber HJ (2009) Monitoring the embrittlement of reactor pressure vessel steels by using the Seebeck coefficient. J Nucl Mater 389(1):62–67
Miller MK, Sokolov MA, Nanstad RK, Russel KF (2006) J Nucl Mater 351:216–222
Cammelli S, Degueldre C, Kuri G, Bertsch J (2008) Study of a neutron irradiated reactor pressure vessel steel by X-ray absorption spectroscopy. Nucl Instrum Meth Phys Res B 266:4775–4781
Wikipedia Defence in Depth http://en.wikipedia.org/wiki/Defence_in_depth. Accessed 3 Nov 2011
JRC EUR 23232 EN (2008) A plant life management model including optimized MS-I programme-safety and economics issues. JRC EUR-report, Jan 2008
Bakirov M (2010) Impact of operational loads and creep, fatigue corrosion interactions on nuclear power plant saystems, structures and components (SSC). In: Tipping PG (ed) Understanding and mitigating ageing in nuclear power plants. Woodhead, pp 146–188
Kasahara homepage http://www.n.t.u-tokyo.ac.jp/kasahara/Homepage/Technology.html. Accessed 13 Oct 2011
Hoffelner W (2010) Design related aspects in advanced nuclear fission plants. J Nucl Mater 409(3):112–116
Hoffelner W (2010) Damage assessment in structural metallic materials for advanced nuclear plants. J Mater Sci 45(9):2247–2257. doi:10.1007/s10853-010-4236-7
IAEA (2009) Integrity of reactor pressure vessels in nuclear powre plants: assessment of radiation embrittlement effects in reactor pressure vessel steels. IAEA nuclear energy series no NP-T-3.11. IAEA, Vienna
Sasikala G, Mathew MD, Bahnu Sanakara Rao K, Mannan SL (2000) Creep deformation and fracture behaviour of types 316 L(N) stainless steels and their weld metals. Met Mat Trans A 13A:1175–1185
Brinkman RC (1999) Elevated-temperature mechanical properties of an advanced type 316 stainless steel. ORNL/CP-101053 Oal Ridge National Laboratory
Shah VN, Majumdar S, Natesan K (2003) Review and assessments of codes and procedures for HTGR components. NUREG/CR-6816 ANL 02/36 USNRC
Author information
Authors and Affiliations
Corresponding author
Rights and permissions
Copyright information
© 2013 Springer-Verlag London Limited
About this chapter
Cite this chapter
Hoffelner, W. (2013). Design, Life-Time and Residual Life. In: Materials for Nuclear Plants. Springer, London. https://doi.org/10.1007/978-1-4471-2915-8_8
Download citation
DOI: https://doi.org/10.1007/978-1-4471-2915-8_8
Published:
Publisher Name: Springer, London
Print ISBN: 978-1-4471-2914-1
Online ISBN: 978-1-4471-2915-8
eBook Packages: EngineeringEngineering (R0)