Fabrication of Be/CuCrZr/SS mock-ups for ITER first wall

被引：23

作者：

Park, Jeong-Yong ^{[1
]}

Choi, Byung-Kwon ^{[1
]}

Lee, Jung-Suk ^{[1
]}

Lee, Dong Won ^{[2
]}

Hong, Bong Guen ^{[2
]}

Jeong, Yong Hwan ^{[1
]}

机构：

[1] Korea Atom Energy Res Inst, Fus Technol Div, Taejon 305353, South Korea

[2] Korea Atom Energy Res Inst, Fus Engn Div, Taejon 305353, South Korea

来源：

FUSION ENGINEERING AND DESIGN | 2009年 / 84卷 / 7-11期

关键词：

ITER first wall; Be; CuCrZr; Stainless steel; Joining; HIP; BE/CU-ALLOY; HIP;

D O I：

10.1016/j.fusengdes.2008.12.052

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

Three types of the mock-ups consisting of Be, CuCrZr and stainless steel (SS) were fabricated by a HIP joining method to demonstrate the fabricability of the ITER first wall. The effects of the mock-up design and the interlayer type on the joining strength of the Be/CuCrZr joint were investigated on the basis of the shear test results for the Be/CuCrZr joint specimens. The joining strength of the Be/CuCrZr ranged from 78 MPa to 204 MPa depending on the types of mock-ups and interlayers. The highest shear strength was obtained from the Be/CuCrZr joint specimens which were taken from the Be/CuCrZr/SS mock-ups with three 80 mm x 80 mm x 10 mm Be tiles and a Cr/Cu interlayer. The effect of the size and the number of Be tiles used in the mock-ups was not as significant as the interlayer selection. Even though the shear test is considered to be very useful to elucidate which interlayer is the most applicable for the joining of Be and CuCrZr, the final interlayer selection should be based on the results obtained from the high heat flux test for the mock-ups fabricated in this work. (C) 2008 Elsevier B.V. All rights reserved.

引用

页码：1468 / 1471

页数：4

共 50 条

[31] High heat flux testing of mock-ups for a full tungsten ITER divertor
Gavila, P.
Riccardi, B.
Constans, S.
Jouvelot, J. L.
Vastra, I. Bobin
Missirlian, M.
Richou, M.
FUSION ENGINEERING AND DESIGN, 2011, 86 (9-11) : 1652 - 1655
[32] Visualizing digital mock-ups
Deitz, D
MECHANICAL ENGINEERING, 1995, 117 (10) : 22 - 22
[33] In-pile testing of ITER first wall mock-ups at relevant thermal loading conditions in the LVR-15 nuclear research reactor
Kysela, Jan
Entler, Slavomir
Vsolak, Rudolf
Klabik, Tomas
Zlamal, Ondrej
Bellin, Boris
Zacchia, Francesco
FUSION ENGINEERING AND DESIGN, 2015, 98-99 : 1271 - 1275
[34] Neutron irradiation effects on the low cycle thermal fatigue performance of first wall mock-ups
Dorow-Gerspach, D.
Loewenhoff, Th.
Pintsuk, G.
Wirtz, M.
NUCLEAR MATERIALS AND ENERGY, 2024, 38
[35] MOCK-UPS FOR DESIGN STUDIES
BALMER, T
DESIGN NEWS, 1973, 28 (06) : 66 - 67
[36] Fabrication and high heat flux test of the first wall mock-ups for the Korean He Cooled Test Blanket (KO HCML TBM)
Lee, Dong Won
Kim, Suk Kwon
Bae, Young Dug
Chang, Doo Hee
Hong, Bong Guen
FUSION ENGINEERING AND DESIGN, 2009, 84 (7-11) : 1164 - 1169
[37] High heat flux testing of EU tungsten monoblock mock-ups for the ITER divertor
Gavila, P.
Riccardi, B.
Pintsuk, G.
Ritz, G.
Kuznetsov, V.
Durocher, A.
FUSION ENGINEERING AND DESIGN, 2015, 98-99 : 1305 - 1309
[38] Mock-Ups as "Interactive Laboratories": Mixed Methods Research Using Inpatient Unit Room Mock-Ups
Watkins, Nicholas
Myers, Donald
Villasante, Ronald
HERD-HEALTH ENVIRONMENTS RESEARCH & DESIGN JOURNAL, 2008, 2 (01) : 66 - 81
[39] Method design, manufacture and tests of the porous beryllium mock-ups for the ITER breeding blanket
Davydov, D.A.
Solonin, M.I.
Markuchkin, Yu.E.
Gorokhov, V.A.
Gorlevsky, V.V.
Journal of Nuclear Materials, 1999, 271-272 : 435 - 439
[40] Experimental investigation of tritium effect on cryosorption panel mock-ups for ITER vacuum pumps
Russian Federal Nuclear Cent, Sarov, Russia
Fusion Eng Des, Pt A (971-976):

← 1 2 3 4 5 →