High-Temperature Creep Properties of NIFS-Heat-2 High-Purity Low-Activation Vanadium Alloy

Nagasaka, T; Muroga, T; Tanaka, Teruya; Sagara, A; Sagara, A; Fukumoto, K.; Zheng, P. F.; Kurtz, Richard J.

doi:10.1088/1741-4326/ab1c8f

High-Temperature Creep Properties of NIFS-Heat-2 High-Purity Low-Activation Vanadium Alloy

Journal Article · 02 September 2019 · Nuclear Fusion

DOI:https://doi.org/10.1088/1741-4326/ab1c8f· OSTI ID:1571520

Nagasaka, T ^[1]; Muroga, T ^[2]; Tanaka, Teruya ^[2]; Sagara, A ^[2]; Sagara, A ^[2]; Fukumoto, K. ^[3]; Zheng, P. F. ^[4]; ^[5]

National Institute for Fusion Science, Oroshi, Toki, Gifu Japan
National Institute for Fusion Science
University of Fukui
Southwestern Institute of Physics
BATTELLE (PACIFIC NW LAB)

A low-activation vanadium alloy with the composition of V-4 mass% Cr-4 mass% Ti is an alternative to reduced-activation ferritic/martensitic (RAFM) steels for blanket structural material in fusion reactors. The NIFS-HEAT-2 (NH2) is the world’s highest-purity V-4Cr-4Ti alloy among over-30 kg-scale heats. The processes to purify this heat have successfully enhanced workability, weldability and low-activation characteristics, however degradation of high-temperature strength was a concern. The present study evaluated high-temperature creep properties of NH2, and confirmed no degradation under projected blanket service stresses.

Research Organization:: Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)

Sponsoring Organization:: USDOE

DOE Contract Number:: AC05-76RL01830;

OSTI ID:: 1571520

Report Number(s):: PNNL-SA-138898

Journal Information:: Nuclear Fusion, Journal Name: Nuclear Fusion Journal Issue: 9 Vol. 59

Country of Publication:: United States

Language:: English

References (13)

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