Antusch, S.

Commin, L.

Hoffmann, J.

Rieth, M.

English

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Institute for Applied Materials (IAM-AWP) WP12-MAT-01-HHFM-02-02/KIT  (ii) Structural Materials Development WP12 Reporting period: February 2012 - January 2013 Investigators:  M. Rieth, L. Commin, J. Hoffmann, S. Antusch KIT - IAM Development of a Reduced Activation (austenitic) Stainless Steel (RASS) EFDA HHFM Monitoring, Garching 2013 M. Rieth, L. Commin, J. Hoffmann, S. Antusch, et al. Institute for Applied Materials (IAM-AWP) MOTIVATION Water cooled divertor development (5-10 MW/m²) There is an operating window for austenitic SS Goal: Reduced Activation Stainless Steel (RASS) with properties comparable to 316 but with better irradiation resistance EFDA HHFM Monitoring, Garching 2013 M. Rieth, L. Commin, J. Hoffmann, S. Antusch, et al. INVESTIGATION Study of Fast Breeder claddings Preliminary Activation Calculations Basic Characterisation and PM Studies Institute for Applied Materials (IAM-AWP) M. Rieth, L. Commin, J. Hoffmann, S. Antusch, et al. EFDA HHFM Monitoring, Garching 2013  The phase points of typical steels for nuclear applications are indicated in the diagram. Schaeffler Diagram (chrome and nickel equivalents)  Institute for Applied Materials (IAM-AWP) M. Rieth, L. Commin, J. Hoffmann, S. Antusch, et al. EFDA HHFM Monitoring, Garching 2013  Swelling of austenitic steels depending on irradion temperature during ion irradiation (40 dpa, 10 appm He). Swelling is clearly reduced in cold-worked (cw) compared to solution annealed steels. The steel 15-15-V-Nb (1.4988) steel belongs to the same steel class as 1.4970 or 1.4981. Swelling of austenitic steels depending on dose during fast neutron irradiation at 500 °C. All steels have been cold-worked (cw) prior to irradiation.  Source: H.-J. Bergmann, W. Dietz, K. Ehrlich, G. Mühling, M. Schirra, FZKA 6864, ISSN 0947-8620, 2003. Institute for Applied Materials (IAM-AWP) M. Rieth, L. Commin, J. Hoffmann, S. Antusch, et al. EFDA HHFM Monitoring, Garching 2013 Irrad. Dose Irradiation Temperature 60 °C 80 °C 200 °C 225 °C 325 °C 400 °C unirrad. 0.5 0.4 0.33 0.31 0.3 0.32 5 dpa 0.35 0.22 0.18 0.08 0.09 0.14 7 dpa 0.3  0.13  0 0.05 10 dpa 0.28  0.11 0.05 0 0.04 15 dpa 0.26  0.08  0 0.03  Uniform elongation (i.e. strain to necking) before and after neutron irradiation of 316L(N) steels. Parameters are irradiation temperature and neutron dose (details are given in [1, 2]). [1] J.P. Robertson, I. Ioka, A.F. Rowcliffe, M.L. Grossbeck and S. Jitsukawa, Temperature dependence of deformation behavior of type 316 stainless steel after low temperature neutron irradiation, ASTM STP (1997) 1325. [2] P.H. Dubuisson, J.L. Seran, P. Soulat, Irradiation Embrittlement of Reactor Internal Materials, in “Effect of Irradiation on Water Reactor Internals,” Study Contract COSU CT94-074, Vol.3, June 1997, p.15. Ductility of 316L(N) Steel after Neutron Irradiation Institute for Applied Materials (IAM-AWP) M. Rieth, L. Commin, J. Hoffmann, S. Antusch, et al. EFDA HHFM Monitoring, Garching 2013 High Level Waste Low Level Waste Reduced Activation 1.4970 L. El-Guebaly Institute for Applied Materials (IAM-AWP) M. Rieth, L. Commin, J. Hoffmann, S. Antusch, et al. EFDA HHFM Monitoring, Garching 2013 Base Material: 1.4981 Rod (40 mm, forged) Powder Production by Atomisation (Nanoval) Institute for Applied Materials (IAM-AWP) M. Rieth, L. Commin, J. Hoffmann, S. Antusch, et al. EFDA HHFM Monitoring, Garching 2013 1.4981 HIP 100 MPa, 1100 °C, 2 h + hot rolled + 800 °C, 2 h L-S T-S Institute for Applied Materials (IAM-AWP) M. Rieth, L. Commin, J. Hoffmann, S. Antusch, et al. EFDA HHFM Monitoring, Garching 2013 1.4981-ODS mixed with ZrO2 + HIP @ 1100 °C, 2 h 1.4981 Rod 1070 °C, 1 h Institute for Applied Materials (IAM-AWP) Conclusions and Assessment RASS is feasible – Main concern: short term activity Swelling is no concern for RASS under DEMO WC divertor conditions Ductility is the limiting factor for WC application – Max. dose: ~5 dpa PM processing is easily applicable to this material EFDA HHFM Monitoring, Garching 2013 M. Rieth, L. Commin, J. Hoffmann, S. Antusch, et al. Many thanks to all involved in this task! Since Ti stabilization becomes ineffective at lower irradiation temperatures, and since Eurofer/F82H-type steels perform better at temperatures above 350 °C, it seems to be unnecessary to follow the Ti stabilizing concept for RASS. Therefore, future activities could be restricted to investigate RASS with simple chemical compositions, that is, Fe-Cr-Ni-Mn-W plus variations or minor contents of other elements (C, Si, N). 

Development of a reduced activation (austenitic) stainless steel (RASS)

https://publikationen.bibliothek.kit.edu/230093747/3816423

Development of a reduced activation (austenitic) stainless steel (RASS)

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