MatDB Online analysis of HTR materials data from European R&D

Nuclear Engineering and Design

Volumn 251, Issue , 2012, Pages 317-324

  Over, H H ^a   Hahner P ^a  

^a JOINT RESEARCH CENTRE   (Italy)

Author keywords

[No Author keywords available]

Indexed keywords

CO-GENERATION; CONVENTIONAL TECHNOLOGY; CROSS-CUTTING; DATA CONTENTS; DATA MANAGEMENT TOOLS; DOCUMENT MANAGEMENT; ECONOMIC OPERATIONS; ELECTRICITY GENERATION; EUROPEAN RESEARCH; EVALUATION EXAMPLE; FREE OF CHARGE; GENERATION IV; HIGH TEMPERATURE; HOT GAS TEMPERATURES; MATERIAL QUALIFICATION; ON-LINE ANALYSIS; PROCESS HEAT; REACTOR DESIGNS; REACTOR SYSTEMS; RESEARCH CENTRES; STORAGE SYSTEMS; TEST DATA; WEB-ENABLED MATERIALS;

DATA TRANSFER; ELECTRIC GENERATORS; HYDROGEN; INFORMATION MANAGEMENT; INFORMATION SERVICES; MATERIALS; ONLINE SYSTEMS;

HIGH TEMPERATURE REACTORS;

EID: 84865657947     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2011.09.063     Document Type: Conference Paper

References (24)

1. ASME Boiler & Pressure Vessel Code Section III, Division 1, Subsection NH-Code Cases N-47 through N-51 (1332-1336, 1974 Edition).
2. S. Chandra, R. Cotgrove, S.R. Holdsworth, M. Schwienheer, and M.W. Spindler Creep Rupture Data Assessments of Alloy 617 ECCC Creep Conference, London, 12-14 September 2005
3. Dietz, W.; 1994. Structural materials, In: Brian R.T. Frost (Nuclear materials, Vol. Editor, VCH Weinheim), Materials Science and Technology, Vol 10B, chapter 8; pp. 53-178, ISBN 3-527-29236-5, VCH-Verlagsgesellschaft Weinheim.
4. ECCC, Creep Data Validation and Assessment Procedures, Pub. European Tech. Develop. Ltd. on behalf of ECCC Management Committee, 2003.
5. D.R. Eno, G.A. Young, and T.L. (Sam) Sham A unified view of engineering creep parameters Proceedings of the ASME 2008 Pressure Vessel and Piping Division Conference, PVP 2008-61129 Chicago, IL, July 27-31 2008
6. Ensign, C.R.; Manson, S.S. 1971. Specialized Model for Analysis of Creep-Rupture Data by Minimum Commitment, Station Function Approach with General Time-Temperature-Stress Relation to Include All Commonly Used Parameters, NASA-TM-X-52999, January 1.
7. French Code RCC-MR, 2002 version, Design and Construction Rules for mechanical components of Fast Breeder Reactor nuclear islands and high temperature applications.
8. Jülich, K.F.A. 1988. Endbericht zum Verbund-Forschungsvorhaben des BMFT, Auslegungskriterien für hochtemperaturbelastete metallische und keramische Komponenten sowie des Spannbeton-Reaktordruckbehälters zukünftiger HTR-Anlagen, Band IIB, 'Teil B: Metallische Komponenten', August.
9. F.R. Larson, and J. Miller A time-temperature relationship for rupture and creep stresses Trans. ASME 74 1952 765 775
10. n = 0.91%, ̇ = 0.001 / s R = 0.05 and 0.053 Hz on Udimet, JRC Petten Institute for Energy. < http://dx.doi.org/10.5290/ 1000000010021 >.
11. n = 0.57%, ̇ = 0.001 / s R = 0.05 and 0.088 Hz on Udimet, JRC Petten Institute for Energy. < http://dx.doi.org/10.5290/ 1000000010068 >.
12. n = 0.665%, ̇ = 0.001 / s R = 0.05 and 0.075 Hz on Udimet, JRC Petten Institute for Energy. < http://dx.doi.org/10.5290/ 1000000010069 >.
13. n = 0.76%, ̇ = 0.001 / s R = 0.05 and 0.066 Hz on Udimet, JRC Petten Institute for Energy. < http://dx.doi.org/10.5290/ 1000000010070 >.
14. n = 0.855%, ̇ = 0.001 / s R = 0.05 and 0.058 Hz on Udimet, JRC Petten Institute for Energy. < http://dx.doi.org/10.5290/ 1000000010071 >.
15. n = 0.76%, ̇ = 0.001 / s R = 0.05 and 0.0083 Hz on Udimet, JRC Petten Institute for Energy. < http://dx.doi.org/10.5290/ 1000000010076 >.
16. S. Maloy, B. Rogers, W. Ren, and P. Rittenhouse Status of materials handbooks for particle accelerator and nuclear reactor applications J. Nucl. Mater. 377 June (1) 2008 94 96
17. N088-Updated Version Final CWA WS ELSSI EMD for Approval, A Guide to the Development and Use of Standards-Compliant Data Formats for Engineering Materials Test Data, CEN WS ELSSI-EMD, 2010-10-6.
18. F.H. Norton Creep of Steel at High Temperatures' 1929 McGraw Hill New York
19. H.H. Over, and W. Dietz The web-enabled database of JRC-EC, a useful tool for managing European GEN IV materials data J. Nucl. Mater. NUMA43285 March 2008
20. R.K. Penny, and D.L. Mariott Design for Creep 1995 Chapman & Hall London, UK
21. Radhakrishnan, V.M. 1992. On Bilinearity of Manson-Coffin Low-Cycle-Fatigue Relationship, NASA Technical Memorandum 105840, October 1992.
22. W. Ren Development of digital materials database for design and construction of new power plants Proceedings of 2008 International Congress on Advances in Nuclear Power Plants (ICAPP'08), American Nuclear Society Annual Meeting, pap 8019, Anaheim CA, USA, June 8-12 2008
23. M. Yamazaki, and Y. Xu Current status of NIMS structural materials database Proceedings of the ASME 2009 Pressure Vessel and Piping Division Conference, PVP 2009 77482 Czech Republic, Prague, 26-30 July 2009
24. P. Yvon, and F. Carré Structural materials challenges for advanced reactor systems J. Nucl. Mater. 385 March (2) 2009 217 222