Effects of HFIR neutron irradiation on fracture toughness properties of standard and Ni-doped F82H

Chen, Xiang; Sokolov, Mikhail A.; Robertson, Janet; Ando, Masami; Geringer, Josina W.; Tanigawa, Hiroyasu; Kato, Yutai

doi:10.1016/j.jnucmat.2020.152501

Effects of HFIR neutron irradiation on fracture toughness properties of standard and Ni-doped F82H

Journal Article · Wed Sep 09 04:00:00 EDT 2020 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2020.152501· OSTI ID:1661236

^[1]; ^[1]; Robertson, Janet ^[1]; Ando, Masami ^[2]; Geringer, Josina W. ^[1]; Tanigawa, Hiroyasu ^[2]; ^[1]

Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
National Inst. for Quantum and Radiological Science and Technology, Chiba (Japan)

F82H is the Japanese reference reduced-activation ferritic-martensitic (RAFM) steel for fusion blanket applications. The harsh environment of a fusion reactor, such as neutron irradiation and He/H damage, can result in significant degradation of F82H fracture toughness. Therefore, understanding the fracture toughness behavior of F82H in the fusion environment is critical to ensure the long-term safe operation of the fusion reactor. Here, we summarize seven irradiation campaigns of the High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory (ORNL) covering five variants of F82H steels, including F82H IEA, F82H Mod3, F82H doped with 1.4% natural Ni, F82H doped with 1.4% ⁵⁸Ni, and F82H doped with 1.4% ⁶⁰Ni. The irradiation temperatures covered the range from 220 °C to 530 °C and the neutron irradiation dose spanned 4 dpa to 70 dpa. The effects of neutron irradiation temperature, dose, materials composition, Ni doping, and He production on F82H fracture toughness are discussed. Our results showed that irradiation embrittlement monotonically decreased with increasing irradiation temperature until 400 °C for F82H IEA and F82H Mod3. F82H Mod3 showed better fracture toughness than F82H IEA both before and after neutron irradiation. We determined that 1.4% Ni alloying can be applied to F82H for simulating He effect in a fission reactor without jeopardizing the fracture toughness of the material. However, more studies are needed to understand the effect of high dose (>20 dpa) and He production on F82H fracture toughness.

View Accepted Manuscript (DOE)

Research Organization:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE Office of Science (SC), Fusion Energy Sciences (FES); USDOE Office of Science (SC), Basic Energy Sciences (BES)

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 1661236

Alternate ID(s):: OSTI ID: 1810955

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Journal Issue: n/a Vol. 542; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

References (32)

Embrittlement of reduced-activation ferritic/martensitic steels irradiated in HFIR at 300°C and 400°C Klueh, R. L.; Sokolov, M. A.; Shiba, K. Journal of Nuclear Materials, Vol. 283-287 https://doi.org/10.1016/S0022-3115(00)00086-6	journal	December 2000
Development of an extensive database of mechanical and physical properties for reduced-activation martensitic steel F82H Jitsukawa, S.; Tamura, M.; van der Schaaf, B. Journal of Nuclear Materials, Vol. 307-311 https://doi.org/10.1016/S0022-3115(02)01075-9	journal	December 2002
On the transition toughness of two RA martensitic steels in the irradiation hardening regime: a mechanism-based evaluation Odette, G. R.; Rathbun, H. J.; Rensman, J. W. Journal of Nuclear Materials, Vol. 307-311 https://doi.org/10.1016/S0022-3115(02)01166-2	journal	December 2002
Tensile properties and transition behaviour of RAFM steel plate and welds irradiated up to 10 dpa at 300 °C Rensman, J.; van Hoepen, J.; Bakker, J. B. M. Journal of Nuclear Materials, Vol. 307-311 https://doi.org/10.1016/S0022-3115(02)01196-0	journal	December 2002
Low-activation ferritic and martensitic steels for fusion application Kohyama, A.; Hishinuma, A.; Gelles, D. S. Journal of Nuclear Materials, Vol. 233-237 https://doi.org/10.1016/S0022-3115(96)00327-3	journal	October 1996
Metallurgical characterization of the reduced activation ferritic/martensitic steel Eurofer'97 on as-received condition Fernández, P.; Lancha, A. M.; Lapeña, J. Fusion Engineering and Design, Vol. 58-59 https://doi.org/10.1016/S0920-3796(01)00563-4	journal	November 2001
Materials design data for reduced activation martensitic steel type F82H Tavassoli, A. -A. F.; Rensman, J. -W; Schirra, M. Fusion Engineering and Design, Vol. 61-62 https://doi.org/10.1016/S0920-3796(02)00255-7	journal	November 2002
Mechanical characterization of EUROFER97 irradiated (0.32 dpa, 300°C) Lucon, Enrico; Decréton, Marc; van Walle, Eric Fusion Engineering and Design, Vol. 69, Issue 1-4 https://doi.org/10.1016/S0920-3796(03)00075-9	journal	September 2003
Effects of specimen size on fracture toughness of phosphorous added F82H steels Kim, Byung Jun; Kasada, Ryuta; Kimura, Akihiko Fusion Engineering and Design, Vol. 86, Issue 9-11 https://doi.org/10.1016/j.fusengdes.2011.04.001	journal	October 2011
Application of small specimen test technique to evaluate fracture toughness of reduced activation ferritic/martensitic steel Han, Wentuo; Yabuuchi, Kiyohiro; Kasada, Ryuta Fusion Engineering and Design, Vol. 125 https://doi.org/10.1016/j.fusengdes.2017.01.040	journal	December 2017
Reduced activation martensitic steels as a structural material for ITER test blanket Shiba, K.; Enoeda, M.; Jitsukawa, S. Journal of Nuclear Materials, Vol. 329-333 https://doi.org/10.1016/j.jnucmat.2004.04.018	journal	August 2004
Mechanical properties of the European reference RAFM steel (EUROFER97) before and after irradiation at 300 °C Lucon, Enrico; Chaouadi, Rachid; Decréton, Marc Journal of Nuclear Materials, Vol. 329-333 https://doi.org/10.1016/j.jnucmat.2004.04.023	journal	August 2004
A master curve analysis of F82H using statistical and constraint loss size adjustments of small specimen data Odette, G. R.; Yamamoto, T.; Kishimoto, H. Journal of Nuclear Materials, Vol. 329-333 https://doi.org/10.1016/j.jnucmat.2004.04.255	journal	August 2004
Radiation hardening and -embrittlement due to He production in F82H steel irradiated at 250°C in JMTR Wakai, E.; Jitsukawa, S.; Tomita, H. Journal of Nuclear Materials, Vol. 343, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2004.10.167	journal	August 2005
On the effects of irradiation and helium on the yield stress changes and hardening and non-hardening embrittlement of ∼8Cr tempered martensitic steels: Compilation and analysis of existing data Yamamoto, Takuya; Odette, G. Robert; Kishimoto, Hirotatsu Journal of Nuclear Materials, Vol. 356, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2006.05.041	journal	September 2006
Status of reduced activation ferritic/martensitic steel development Baluc, N.; Gelles, D. S.; Jitsukawa, S. Journal of Nuclear Materials, Vol. 367-370 https://doi.org/10.1016/j.jnucmat.2007.03.036	journal	August 2007
Plastic flow properties and fracture toughness characterization of unirradiated and irradiated tempered martensitic steels Spätig, P.; Bonadé, R.; Odette, G. R. Journal of Nuclear Materials, Vol. 367-370 https://doi.org/10.1016/j.jnucmat.2007.03.038	journal	August 2007
Evaluation of fracture toughness master curve shifts for JMTR irradiated F82H using small specimens Yamamoto, T.; Odette, G. R.; Gragg, D. Journal of Nuclear Materials, Vol. 367-370 https://doi.org/10.1016/j.jnucmat.2007.03.046	journal	August 2007
Fracture toughness characterization of JLF-1 steel after irradiation in HFIR to 5dpa Sokolov, M. A.; Kimura, A.; Tanigawa, H. Journal of Nuclear Materials, Vol. 367-370 https://doi.org/10.1016/j.jnucmat.2007.03.100	journal	August 2007
Application of the master curve to inhomogeneous ferritic/martensitic steel Sokolov, M. A.; Tanigawa, H. Journal of Nuclear Materials, Vol. 367-370 https://doi.org/10.1016/j.jnucmat.2007.03.105	journal	August 2007
Fracture toughness and Charpy impact properties of several RAFMS before and after irradiation in HFIR Sokolov, M. A.; Tanigawa, H.; Odette, G. R. Journal of Nuclear Materials, Vol. 367-370 https://doi.org/10.1016/j.jnucmat.2007.03.165	journal	August 2007
3D finite element and experimental study of the size requirements for measuring toughness on tempered martensitic steels Mueller, P.; Spätig, P. Journal of Nuclear Materials, Vol. 389, Issue 3 https://doi.org/10.1016/j.jnucmat.2009.01.311	journal	June 2009
On the fracture toughness of irradiated F82H: Effects of loss of constraint and strain hardening capacity Yamamoto, T.; Odette, G. R.; Sokolov, M. A. Journal of Nuclear Materials, Vol. 417, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2010.12.102	journal	October 2011
Heat treatment effect on fracture toughness of F82H irradiated in HFIR Okubo, N.; Sokolov, M. A.; Tanigawa, H. Journal of Nuclear Materials, Vol. 417, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2011.05.020	journal	October 2011
Evaluation of grain boundary embrittlement of phosphorus added F82H steel by SSTT Kim, Byung Jun; Kasada, Ryuta; Kimura, Akihiko Journal of Nuclear Materials, Vol. 421, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2011.11.063	journal	February 2012
Application of master curve method to the evaluation of fracture toughness of F82H steels Kim, Byung Jun; Kasada, Ryuta; Kimura, Akihiko Journal of Nuclear Materials, Vol. 442, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.03.079	journal	November 2013
Recent status and improvement of reduced-activation ferritic-martensitic steels for high-temperature service Tan, L.; Katoh, Y.; Tavassoli, A. -A. F. Journal of Nuclear Materials, Vol. 479 https://doi.org/10.1016/j.jnucmat.2016.07.054	journal	October 2016
Method for analyzing passive silicon carbide thermometry with a continuous dilatometer to determine irradiation temperature Campbell, Anne A.; Porter, Wallace D.; Katoh, Yutai Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 370 https://doi.org/10.1016/j.nimb.2016.01.005	journal	March 2016
Ni-Doped F82H to Investigate He Effects in HFIR Irradiation Sawai, Tomotsugu; Ando, Masami; Wakai, Eiichi Fusion Science and Technology, Vol. 44, Issue 1 https://doi.org/10.13182/FST03-A334	journal	July 2003
Development of the Toughness-Improved Reduced-Activation F82H Steel for DEMO Reactor Shiba, K.; Tanigawa, H.; Hirose, T. Fusion Science and Technology, Vol. 62, Issue 1 https://doi.org/10.13182/FST12-A14127	journal	August 2012
Charpy Impact Properties of Reduced-Activation Ferritic/Martensitic Steels Irradiated in HFIR up to 20 dpa Tanigawa, H.; Shiba, K.; Sokolov, M. A. Fusion Science and Technology, Vol. 44, Issue 1 https://doi.org/10.13182/FST44-206	journal	July 2003
Heat Treatment Effects on Microstructures and DBTT of F82H Steel Doped with Boron and Nitrogen Okubo, Nariaki; Wakai, Eiichi; Matsukawa, Shingo MATERIALS TRANSACTIONS, Vol. 46, Issue 2 https://doi.org/10.2320/matertrans.46.193	journal	January 2005

Similar Records

Heat Treatment Effect on Fracture Toughness of F82H Irradiated in HFIR

Journal Article · Fri Dec 31 23:00:00 EST 2010 · Journal of Nuclear Materials · OSTI ID:1031013

Ni-Doped F82H to Investigate He Effects in HFIR Irradiation

Journal Article · Tue Jul 15 00:00:00 EDT 2003 · Fusion Science and Technology · OSTI ID:20849513

Irradiation hardening in F82H irradiated at 573 K in the HFIR

Journal Article · Fri Dec 31 23:00:00 EST 2010 · Journal of Nuclear Materials · OSTI ID:1031011

Related Subjects

36 MATERIALS SCIENCE
F82H
Fracture Toughness
He Effect
Irradiation Embrittlement
Ni doping
Reduced Activation Ferritic-Martensitic Steel

Effects of HFIR neutron irradiation on fracture toughness properties of standard and Ni-doped F82H

Citation Formats

References (32)

Similar Records

Related Subjects