Thermal-Fatigue Analysis of W-joined Ferritic-Martensitic Steel Mockup for Fusion Reactor Components
Creators
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
- 2. Gentec Co., Daejeon (Korea, Republic of)
- 3. Chonbuk National University, Chonbuk (Korea, Republic of)
Description
Through the ITER blanket first wall (BFW) development project in Korea, the joining methods were developed with a beryllium (Be) layer as a plasma-facing material, a copper alloy (CuCrZr) layer as a heat sink, and type 316L austenitic stainless steel (SS316L) as a structural material. And joining methods were developed such as Be as an armor and FMS as a structural material, or W as an armor and FMS as a structural material were developed through the test blanket module (TBM) program. As a candidate of PFC for DEMO, W/FMS joining methods have been developed and a new Ti interlayer was applied differently from the previous work. In the present study, the W/FMS PFC development was introduced with the following procedure to apply to the PFCs for a fusion reactor: (1) Three W/FMS mockups were fabricated using the developed HIP followed by a post-HIP heat treatment (PHHT). (2) Because the High Heat Flux (HHF) test should be performed over the thermal lifetime of the mockup under the proper test conditions to confirm the joint's integrity, the test conditions were determined through a preliminary analysis. In this study, commercial ANSYS-CFX for thermalhydraulic analysis and ANSYS-mechanical for the thermo-mechanical analysis are used to evaluate the thermal-lifetime of the mockup to determine the test conditions. Also, the Korea Heat Load Test facility with an Electron Beam (KoHLT-EB) will be used and its water cooling system is considered to perform the thermal-hydraulic analysis especially for considering the two-phase analysis with a higher heat flux conditions. From the analysis, the heating and the cooling conditions were determined for 0.5- and 1.0-MW/m2 heat fluxes, respectively. Elastic-plastic analysis is performed to determine the lifetime and finally, the 1.0 MW/m2 heat flux conditions are determined up to 4,306 cycles. The test will be done in the near future and the measured temperatures will be compared with the present simulation results
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS 2015 Fall Meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [3 p.]
Conference
- Title
- 2015 Fall meeting of the KNS
- Dates
- 28-30 Oct 2015
- Place
- Kyungju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 47085466
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BUILDING MATERIALS; FABRICATION; FATIGUE; HEAT FLUX; ITER TOKAMAK; MOCKUP; REACTOR COMPONENTS; TEST FACILITIES; THERMONUCLEAR REACTORS
- Descriptors DEC
- CLOSED PLASMA DEVICES; MATERIALS; MECHANICAL PROPERTIES; STRUCTURAL MODELS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS
Optional Information
- Notes
- 8 refs, 8 figs, 1 tab