Abstract
A primary concern in the development of accelerator-driven systems (ADS) with liquid leadbismuth eutectic (LBE) spallation target and Gen-IV lead-cooled fast reactors (LFRs) is the compatibility of the candidate structural steels with the heavy liquid metal (HLM) coolant In the accelerator-driven system MYRRHA, the envisaged primary coolant is liquid LBE, a potentially corrosive environment for various nuclear grade steels. The inherent LBE corrosiveness is the driving force behind diverse research incentives aiming at the development of corrosion-resistant materials for specific applications. I3ue to their superb corrosion resistance in contact with liquid LBE, MAX phases are currently being assessed as candidate materials for the construction of pump impellers suitable for MYRRHA and Gen-IV LFRs. In the case of the MYRRHA nuclear system, the pump impeller will be called to operate reliably at ∼270°C in contact with moderately-oxygenated (concentration of dissolved oxygen: [O] ≥ 7×10-7 mass%), fast-flowing LBE (LBE flow velocity: v ≈ 10-20 m/s locally on the impeller surface). Selected MAX phases are currently being screened with respect to their capability of meeting the targeted material property requirements, especially the enhanced erosion resistance requested by this particular application. This work gives a state-of-the-art overview of the processing and characterisation of selected MAX phases that are screened as candidate structural materials for the MYRRHA pump impeller. All considered MAX phases were produced via a powder metallurgical route and their performance was assessed by various mechanical tests in air/vacuum and corrosion/erosion tests in liquid LBE.
| Language | English |
|---|---|
| Title of host publication | Ceramic Materials for Energy Applications V |
| Subtitle of host publication | Ceramic Engineering and Science Proceedings 2015 |
| Editors | Josef Matyáš, Yutai Katoh, Hua-Tay Lin, Alberto Vomiero, Jingyang Wang, Soshu Kirihara |
| Publisher | American Ceramic Society |
| Pages | 19-34 |
| Number of pages | 16 |
| Volume | 36 |
| Edition | 7 |
| ISBN (Electronic) | 9781119211709 |
| ISBN (Print) | 9781119211693 |
| DOIs | |
| Publication status | Published - 25 Dec 2015 |
| Externally published | Yes |
| Event | Ceramic Materials for Energy Applications V - 39th International Conference on Advanced Ceramics and Composites, ICACC 2015 - Daytona Beach, United States Duration: 25 Jan 2015 → 30 Jan 2015 |
Publication series
| Name | Ceramic Engineering and Science Proceedings |
|---|---|
| Publisher | American Ceramic Society |
| ISSN (Electronic) | 1940-6339 |
Conference
| Conference | Ceramic Materials for Energy Applications V - 39th International Conference on Advanced Ceramics and Composites, ICACC 2015 |
|---|---|
| Country | United States |
| City | Daytona Beach |
| Period | 25/01/15 → 30/01/15 |
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Corrosion‐Resistant Ternary Carbides For Use in Heavy Liquid Metal Coolants. / Lambrinou, K.; Lapauw, T.; Jianu, A.; Weisenburger, A.; Ejenstam, J.; Szakálos, P.; Wallenius, J.; Ström, E.; Vanmeensel, K.; Vleugels, J.
Ceramic Materials for Energy Applications V: Ceramic Engineering and Science Proceedings 2015. ed. / Josef Matyáš; Yutai Katoh; Hua-Tay Lin; Alberto Vomiero; Jingyang Wang; Soshu Kirihara. Vol. 36 7. ed. American Ceramic Society, 2015. p. 19-34 (Ceramic Engineering and Science Proceedings).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution
TY - GEN
T1 - Corrosion‐Resistant Ternary Carbides For Use in Heavy Liquid Metal Coolants
AU - Lambrinou, K.
AU - Lapauw, T.
AU - Jianu, A.
AU - Weisenburger, A.
AU - Ejenstam, J.
AU - Szakálos, P.
AU - Wallenius, J.
AU - Ström, E.
AU - Vanmeensel, K.
AU - Vleugels, J.
PY - 2015/12/25
Y1 - 2015/12/25
N2 - A primary concern in the development of accelerator-driven systems (ADS) with liquid leadbismuth eutectic (LBE) spallation target and Gen-IV lead-cooled fast reactors (LFRs) is the compatibility of the candidate structural steels with the heavy liquid metal (HLM) coolant In the accelerator-driven system MYRRHA, the envisaged primary coolant is liquid LBE, a potentially corrosive environment for various nuclear grade steels. The inherent LBE corrosiveness is the driving force behind diverse research incentives aiming at the development of corrosion-resistant materials for specific applications. I3ue to their superb corrosion resistance in contact with liquid LBE, MAX phases are currently being assessed as candidate materials for the construction of pump impellers suitable for MYRRHA and Gen-IV LFRs. In the case of the MYRRHA nuclear system, the pump impeller will be called to operate reliably at ∼270°C in contact with moderately-oxygenated (concentration of dissolved oxygen: [O] ≥ 7×10-7 mass%), fast-flowing LBE (LBE flow velocity: v ≈ 10-20 m/s locally on the impeller surface). Selected MAX phases are currently being screened with respect to their capability of meeting the targeted material property requirements, especially the enhanced erosion resistance requested by this particular application. This work gives a state-of-the-art overview of the processing and characterisation of selected MAX phases that are screened as candidate structural materials for the MYRRHA pump impeller. All considered MAX phases were produced via a powder metallurgical route and their performance was assessed by various mechanical tests in air/vacuum and corrosion/erosion tests in liquid LBE.
AB - A primary concern in the development of accelerator-driven systems (ADS) with liquid leadbismuth eutectic (LBE) spallation target and Gen-IV lead-cooled fast reactors (LFRs) is the compatibility of the candidate structural steels with the heavy liquid metal (HLM) coolant In the accelerator-driven system MYRRHA, the envisaged primary coolant is liquid LBE, a potentially corrosive environment for various nuclear grade steels. The inherent LBE corrosiveness is the driving force behind diverse research incentives aiming at the development of corrosion-resistant materials for specific applications. I3ue to their superb corrosion resistance in contact with liquid LBE, MAX phases are currently being assessed as candidate materials for the construction of pump impellers suitable for MYRRHA and Gen-IV LFRs. In the case of the MYRRHA nuclear system, the pump impeller will be called to operate reliably at ∼270°C in contact with moderately-oxygenated (concentration of dissolved oxygen: [O] ≥ 7×10-7 mass%), fast-flowing LBE (LBE flow velocity: v ≈ 10-20 m/s locally on the impeller surface). Selected MAX phases are currently being screened with respect to their capability of meeting the targeted material property requirements, especially the enhanced erosion resistance requested by this particular application. This work gives a state-of-the-art overview of the processing and characterisation of selected MAX phases that are screened as candidate structural materials for the MYRRHA pump impeller. All considered MAX phases were produced via a powder metallurgical route and their performance was assessed by various mechanical tests in air/vacuum and corrosion/erosion tests in liquid LBE.
KW - Corrosion-resistant ternary carbine
KW - Erosion test
KW - Nuclear grade steel
KW - Accelerator-driven system
UR - http://www.scopus.com/inward/record.url?scp=84959575951&partnerID=8YFLogxK
U2 - 10.1002/9781119211709.ch3
DO - 10.1002/9781119211709.ch3
M3 - Conference contribution
SN - 9781119211693
VL - 36
T3 - Ceramic Engineering and Science Proceedings
SP - 19
EP - 34
BT - Ceramic Materials for Energy Applications V
A2 - Matyáš, Josef
A2 - Katoh, Yutai
A2 - Lin, Hua-Tay
A2 - Vomiero, Alberto
A2 - Wang, Jingyang
A2 - Kirihara, Soshu
PB - American Ceramic Society
ER -