“…In view of the previous results on fine-grained W-0.3TiC (grain size: 0.9 lm) and pure W irradiated at 563 K to 9 Â 10 23 n/m 2 (E > 1 MeV) where DHV was 30 for W-0.3TiC and 63 for pure W [27], we can say that the UFG microstructure in W-0.5TiC is very effective in improving the resistance to radiation hardening. In addition, 3 MeV He-ion irradiations at 823 K to 2 Â 10 23 He/m 2 showed that surface damage resistance for UFG W-0.3TiC-H 2 is more than ten times as high as that for the commercially available W materials [15].…”
Section: Development Of Radiation-resistant Ultra-fine Grained Tungsmentioning
confidence: 98%
“…In order to overcome such a weak point, cladding with corrosion resistant material was applied to tungsten target. Typical example is a tantalum-clad tungsten target for KENS [15] and ISIS [28]. However, tantalum is highly activated by thermal neutrons [18] and its decay heat is a problem during target exchange [19].…”
Section: Crn Film Formation On Tungstenmentioning
confidence: 99%
“…However, there are two severe problems: (1) irradiated tungsten showed fairly harden and brittle in the tensile and bending tests [10,11], although the compression test showed that tungsten had some ductility even after 23 dpa irradiation [12], (2) was easily corroded by flowing water with high velocity [13,14] or high temperature [15]. To the former problem, we have investigated the methods to develop the tungsten alloy which has radiation induced ductility upgrade.…”
Section: Introductionmentioning
confidence: 99%
“…Such high activities bring us difficulty of exchanging the used target into the new one [19]. On the other hand, CrN has advantages for stronger corrosion resistance [15] and lower neutron-induced activity than tantalum. Accordingly, we had tried to make CrN coating on a tungsten plate with the arc-ion-plasma type PVD (AIP) technique and the ion-beam-enhanced deposition (IBED), and fundamental mechanical properties were also measured [1].…”
“…In view of the previous results on fine-grained W-0.3TiC (grain size: 0.9 lm) and pure W irradiated at 563 K to 9 Â 10 23 n/m 2 (E > 1 MeV) where DHV was 30 for W-0.3TiC and 63 for pure W [27], we can say that the UFG microstructure in W-0.5TiC is very effective in improving the resistance to radiation hardening. In addition, 3 MeV He-ion irradiations at 823 K to 2 Â 10 23 He/m 2 showed that surface damage resistance for UFG W-0.3TiC-H 2 is more than ten times as high as that for the commercially available W materials [15].…”
Section: Development Of Radiation-resistant Ultra-fine Grained Tungsmentioning
confidence: 98%
“…In order to overcome such a weak point, cladding with corrosion resistant material was applied to tungsten target. Typical example is a tantalum-clad tungsten target for KENS [15] and ISIS [28]. However, tantalum is highly activated by thermal neutrons [18] and its decay heat is a problem during target exchange [19].…”
Section: Crn Film Formation On Tungstenmentioning
confidence: 99%
“…However, there are two severe problems: (1) irradiated tungsten showed fairly harden and brittle in the tensile and bending tests [10,11], although the compression test showed that tungsten had some ductility even after 23 dpa irradiation [12], (2) was easily corroded by flowing water with high velocity [13,14] or high temperature [15]. To the former problem, we have investigated the methods to develop the tungsten alloy which has radiation induced ductility upgrade.…”
Section: Introductionmentioning
confidence: 99%
“…Such high activities bring us difficulty of exchanging the used target into the new one [19]. On the other hand, CrN has advantages for stronger corrosion resistance [15] and lower neutron-induced activity than tantalum. Accordingly, we had tried to make CrN coating on a tungsten plate with the arc-ion-plasma type PVD (AIP) technique and the ion-beam-enhanced deposition (IBED), and fundamental mechanical properties were also measured [1].…”
“…Molybdenum also has good strength at high temperatures, and is less dense than tungsten and tantalum. In addition, it has a relatively low thermal neutron cross section [1][2][3]. These qualities make molybdenum attractive for the use in the nuclear industry [4][5][6][7].…”
A target assembly, composed of several collinear molybdenum (Mo)‐based and tungsten (W)‐based cylindrical blocks, will reside in the core of the new beam dump facility (BDF) being designed at the European Laboratory for Particle Physics (CERN). The target blocks will be protected from the cooling water erosion‐corrosion by a tantalum (Ta)‐based cladding.
In order to obtain intimate and reliable bonding between the several cylinders composing each target block and with the cladding, hot isostatic pressing (HIP) assisted diffusion bonding technique was explored. Several down‐scaled target block prototypes were conceived to investigate the bondings. Starting from the previously gained experience in Ta cladding on W from neutron spallation targets, here, we present results on Ta cladding on TZM (Mo alloy), Ta2.5W (Ta alloy) cladding on TZM and W, and on TZM to TZM and W to W self‐bondings. The resulting interfaces were systematically characterized with electron microscopy, tensile testing, and thermal conductivity measurements.
Successful diffusion bonding was achieved for all the studied material combinations, resulting in homogeneous and defect‐free interfaces, strong interfacial bondings, and limited interfacial thermal contact resistance. The HIP parameters and diffusion interfacial aids were of great importance to optimize the interface and bulk material properties.
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