Structure and mechanical properties of improved cast stainless steels for nuclear applications

Kenik, Edward A.; Busby, Jeremy T.; Gussev, Maxim N.; Maziasz, Philip J.; Hoelzer, David T.; Rowcliffe, Arthur F.; Vitek, John M.

doi:10.1016/j.jnucmat.2016.10.045

Title: Structure and mechanical properties of improved cast stainless steels for nuclear applications

Journal Article · Thu Oct 27 04:00:00 UTC 2016 · Journal of Nuclear Materials

DOI: https://doi.org/10.1016/j.jnucmat.2016.10.045 · OSTI ID:1362206

Kenik, Edward A. ^[1]; Busby, Jeremy T. ^[1]; Gussev, Maxim N. ^[2]; Maziasz, Philip J. ^[1]; Hoelzer, David T. ^[1]; Rowcliffe, Arthur F. ^[1]; Vitek, John M. ^[1]

Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Materials Science and Technology Division
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Nuclear Fuel and Isotopes Division

Casting of stainless steels is a promising and cost saving way of directly producing large and complex structures, such a shield modules or divertors for the ITER. Here, a series of modified high-nitrogen cast steels has been developed and characterized. The steels, based on the cast equivalent of 316 composition, have increased N (0.14-0.36%) and Mn (2-5.1%) content; copper was added to one of the heats. Mechanical tests were conducted with non-irradiated and neutron irradiated specimens at 0.7 dpa. It was established that alloying by nitrogen significantly improves the yield stress of non-irradiated steels and the deformation hardening rate. Manganese tended to decrease yield stress, but increased radiation hardening. Furthermore, the role of copper on mechanical properties was negligibly small. Analysis of structure was conducted using SEM-EDS and the nature and compositions of the second phases and inclusions were analyzed in detail. We show that the modified steels, compared to reference material, exhibit significantly reduced elemental inhomogeneity and second phase formation.

View Accepted Manuscript (DOE)

Cite

Export

Save

Research Organization:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States). Joint Institute for Computational Sciences (JICS)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE)

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 1362206

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Journal Issue: C Vol. 483; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

References (32)

A Review of the Stages of Work Hardening Rollett, Anthony D.; Kocks, U. F. Solid State Phenomena, Vol. 35-36 https://doi.org/10.4028/www.scientific.net/ssp.35-36.1	journal	September 1993
High-Interstitial Stainless Austenitic Steel Castings Berns, Hans; Nabiran, Nilofar; Mujica, Laís steel research international, Vol. 84, Issue 2 https://doi.org/10.1002/srin.201100332	journal	August 2012
Magnetic properties of SUS 304 austenitic stainless steel after tensile deformation at elevated temperatures Zhang, Lefu; Takahashi, Seiki; Kamada, Yasuhiro Journal of Materials Science, Vol. 40, Issue 9-10 https://doi.org/10.1007/s10853-005-2112-7	journal	May 2005
The Effect of Chemical Composition and Heat Treatment Conditions on Stacking Fault Energy for Fe-Cr-Ni Austenitic Stainless Steel Yonezawa, Toshio; Suzuki, Ken; Ooki, Suguru Metallurgical and Materials Transactions A, Vol. 44, Issue 13 https://doi.org/10.1007/s11661-013-1943-0	journal	August 2013
Development of high manganese high nitrogen low activation austenitic stainless steels Bott, A. H.; Pickering, F. B.; Butterworth, G. J. Journal of Nuclear Materials, Vol. 141-143 https://doi.org/10.1016/0022-3115(86)90147-9	journal	November 1986
Stress-strain relations of irradiated stainless steels below 673 K Jitsukawa, S.; Grossbeck, M. L.; Hishinuma, A. Journal of Nuclear Materials, Vol. 191-194 https://doi.org/10.1016/0022-3115(92)90580-E	journal	September 1992
Miniature tensile test specimens for fusion reactor irradiation studies Klueh, R. L. Nuclear Engineering and Design. Fusion, Vol. 2, Issue 3 https://doi.org/10.1016/0167-899X(85)90028-X	journal	January 1985
A new high-molybdenum, high-nitrogen stainless steel Wállen, B.; Liljas, M.; Stenvall, P. Materials & Design, Vol. 13, Issue 6 https://doi.org/10.1016/0261-3069(92)90002-Y	journal	January 1992
Work-hardening behaviour of nitrogen-alloyed austenitic stainless steels Soussan, A.; Degallaix, S.; Magnin, T. Materials Science and Engineering: A, Vol. 142, Issue 2 https://doi.org/10.1016/0921-5093(91)90655-7	journal	August 1991
Overview: high-nitrogen alloying of stainless steels Simmons, J. W. Materials Science and Engineering: A, Vol. 207, Issue 2, p. 159-169 https://doi.org/10.1016/0921-5093(95)09991-3	journal	March 1996
The microstructure and associated tensile properties of irradiated fcc and bcc metals Victoria, M.; Baluc, N.; Bailat, C. Journal of Nuclear Materials, Vol. 276, Issue 1-3 https://doi.org/10.1016/S0022-3115(99)00203-2	journal	January 2000
Competing mechanisms and modeling of deformation in austenitic stainless steel single crystals with and without nitrogen Karaman, I.; Sehitoglu, H.; Maier, H. J. Acta Materialia, Vol. 49, Issue 19 https://doi.org/10.1016/S1359-6454(01)00296-8	journal	November 2001
On the stress dependence of partial dislocation separation and deformation microstructure in austenitic stainless steels Byun, T. S. Acta Materialia, Vol. 51, Issue 11 https://doi.org/10.1016/S1359-6454(03)00117-4	journal	June 2003
Plastic instability in polycrystalline metals after low temperature irradiation Byun, T. S.; Farrell, K. Acta Materialia, Vol. 52, Issue 6 https://doi.org/10.1016/j.actamat.2003.12.023	journal	April 2004
Correlation between stacking fault energy and deformation microstructure in high-interstitial-alloyed austenitic steels Lee, Tae-Ho; Shin, Eunjoo; Oh, Chang-Seok Acta Materialia, Vol. 58, Issue 8 https://doi.org/10.1016/j.actamat.2010.01.056	journal	May 2010
Simulation of polycrystal deformation with grain and grain boundary effects Lim, H.; Lee, M. G.; Kim, J. H. International Journal of Plasticity, Vol. 27, Issue 9 https://doi.org/10.1016/j.ijplas.2011.03.001	journal	September 2011
Damage and dynamic strain aging in a thermal aged cast duplex stainless steel Calonne, V.; Berdin, C.; Saint-Germain, B. Journal of Nuclear Materials, Vol. 327, Issue 2-3 https://doi.org/10.1016/j.jnucmat.2004.02.010	journal	May 2004
Effects of oversized solutes on radiation-induced segregation in austenitic stainless steels Hackett, M. J.; Busby, J. T.; Miller, M. K. Journal of Nuclear Materials, Vol. 389, Issue 2 https://doi.org/10.1016/j.jnucmat.2009.02.010	journal	May 2009
Economic benefits of advanced materials in nuclear power systems Busby, J. T. Journal of Nuclear Materials, Vol. 392, Issue 2 https://doi.org/10.1016/j.jnucmat.2009.03.018	journal	July 2009
Analysis of tensile deformation and failure in austenitic stainless steels: Part II – Irradiation dose dependence Kim, Jin Weon; Byun, Thak Sang Journal of Nuclear Materials, Vol. 396, Issue 1 https://doi.org/10.1016/j.jnucmat.2009.08.009	journal	January 2010
Development of high performance cast stainless steels for ITER shield module applications Busby, J. T.; Maziasz, P. J.; Rowcliffe, A. F. Journal of Nuclear Materials, Vol. 417, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2010.12.152	journal	October 2011
Description of strain hardening behavior in neutron-irradiated fcc metals Gussev, M. N.; Byun, T. S.; Busby, J. T. Journal of Nuclear Materials, Vol. 427, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2012.04.017	journal	August 2012
Crack initiation behavior of neutron irradiated model and commercial stainless steels in high temperature water Stephenson, Kale J.; Was, Gary S. Journal of Nuclear Materials, Vol. 444, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.10.008	journal	January 2014
Analysis of structure and deformation behavior of AISI 316L tensile specimens from the second operational target module at the Spallation Neutron Source Gussev, M. N.; McClintock, D. A.; Garner, F. A. Journal of Nuclear Materials, Vol. 468 https://doi.org/10.1016/j.jnucmat.2015.07.013	journal	January 2016
Irradiation response of delta ferrite in as-cast and thermally aged cast stainless steel Li, Zhangbo; Lo, Wei-Yang; Chen, Yiren Journal of Nuclear Materials, Vol. 466 https://doi.org/10.1016/j.jnucmat.2015.08.006	journal	November 2015
Influence of hot forging and alloying with Al on the electrochemical behavior and mechanical properties of austenitic stainless steel Farahat, Ahmed I. Z.; Hamdy, Abdel Salam Materials & Design, Vol. 57 https://doi.org/10.1016/j.matdes.2014.01.018	journal	May 2014
Effect of copper on the formation of strain-induced martensite in two austenitic stainless steels AISI 304 Gilapa, Leonidas Cayo Mamani; de Oliveira, Carlos Augusto Silva; da Silva, Manoel Ribeiro Materials Science and Engineering: A, Vol. 622 https://doi.org/10.1016/j.msea.2014.10.059	journal	January 2015
Surface-layer microstructure control for metastable austenitic stainless steel to prevent hydrogen permeation Tsuchiyama, T.; Takebe, Hidenori; Tsuboi, Koichi Scripta Materialia, Vol. 62, Issue 10 https://doi.org/10.1016/j.scriptamat.2010.01.042	journal	May 2010
Stacking fault energy of cryogenic austenitic steels Qi-Xun, Dai; Xiao-Nong, Wang An-Dong, Cheng; Xin-Min, Luo Chinese Physics, Vol. 11, Issue 6 https://doi.org/10.1088/1009-1963/11/6/315	journal	May 2002
Radiation-Hardening and Recovery in Mild Steels and the Effects of Interstitial Nitrogen Little, E. A.; Harries, D. R. Metal Science Journal, Vol. 4, Issue 1 https://doi.org/10.1179/msc.1970.4.1.188	journal	January 1970
Influence of nitrogen and grain size on deformation behaviour of austenitic stainless steels Nyström, M.; Lindstedt, U.; Karlsson, B. Materials Science and Technology, Vol. 13, Issue 7 https://doi.org/10.1179/mst.1997.13.7.560	journal	July 1997
Effect of Alloying Elements on the Mechanical Properties of the Stable Austenitic Stainless Steel. Ohkubo, Naoto; Miyakusu, Katsuhisa; Uematsu, Yoshihiro ISIJ International, Vol. 34, Issue 9 https://doi.org/10.2355/isijinternational.34.764	journal	January 1994

Similar Records

Stress Corrosion Cracking Behavior of Cast Stainless Steels

Conference · Thu Jan 01 04:00:00 UTC 2009 · OSTI ID:1014219

Teysseyre, Sebastien; Busby, Jeremy T; Was, Gary

Tensile behavior of irradiated manganese-stabilized stainless steel

Technical Report · Tue Oct 01 04:00:00 UTC 1996 · OSTI ID:414884

Klueh, R. L.

Comparison of the irradiated tensile properties of a high-manganese austenitic steel and type 16 stainless steel

Conference · Sat Jan 01 04:00:00 UTC 1983 · OSTI ID:5783951

Klueh, R L; Grossbeck, M L

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
36 MATERIALS SCIENCE

Title: Structure and mechanical properties of improved cast stainless steels for nuclear applications

Citation Formats

References (32)

Similar Records

Related Subjects