طراحی و تجزیه و تحلیل عملکرد از اجزای ساختاری برای TBM سرامیک رفلکتور هلیم خنک کره ای در ITER
|کد مقاله||سال انتشار||مقاله انگلیسی||ترجمه فارسی||تعداد کلمات|
|28321||2013||6 صفحه PDF||سفارش دهید||محاسبه نشده|
Publisher : Elsevier - Science Direct (الزویر - ساینس دایرکت)
Journal : Fusion Engineering and Design, Volume 88, Issues 9–10, October 2013, Pages 1866–1871
Korea has developed a Helium Cooled Ceramic Reflector (HCCR) Test Blanket Module (TBM) testing in ITER, which was considered one of the fusion DEMO-relevant blankets in Korea. The design and performance analysis of the TBM body have been carried out considering the uniqueness of the KO TBM and design requirements by the IO and KO design concept: (1) KO TBM has 4 sub-modules considering a post irradiation test (PIE) and its delivery. (2) A first wall (FW) design was changed into a 15 × 11 rectangular shape and its performance was confirmed by thermal-hydraulic and thermo-mechanical analyses using commercial ANSYS code. The results showed that the revised design model satisfied 1.5Sm and 3Sm of the allowable stress (Sm) in the RCC-MR code at the maximum stress region of the components for mechanical and thermo-mechanical analyses, respectively. (3) Considering the tritium breeding and cooling, a breeding zone (BZ) design was investigated. Three Li and Be layers, and one graphite layer, were proposed by the iteration, and the appropriate temperature distribution was obtained. The design for other components such as a side wall (SW) and back manifold (BM) is on-going considering 9 MPa of channel pressure and its functions of flow distribution as a manifold.
One of the main engineering performance goals of ITER is to test and validate the design concepts of the tritium breeding blankets relevant to a power producing reactor. The tests will focus on modules including a demonstration of the breeding capability that will lead to a tritium self sufficiency and extraction of heat suitable for an electricity generation ,  and . Korea has developed a Helium Cooled Molten Lithium (HCML) Test Blanket Module (TBM) and Helium Cooled Solid Breeder (HCSB) TBM for testing in the ITER. Recently, solid-type HCSB TBM was decided as a leading concept in the National Fusion Committee and the other is developing as the breeding blanket for DEMO. The name of the solid type TBM was changed to a Helium Cooled Ceramic Reflector (HCCR) considering the unique concept using a graphite reflector . In this study, the overall design procedure of the main components of TBM such as a first wall (FW) and an array of breeding zone (BZ) including its performance analysis was introduced. Until the performance analysis results satisfied the design requirement, the geometries and arrays of BZ were modified, and finally the optimized design was obtained.
نتیجه گیری انگلیسی
To develop the fusion reactor, we have participated in the TBM program in the ITER. According to the recent national decision to lead the solid-type HCCR TBM, the design and performance analysis for TBM body have been carried out considering the uniqueness of the KO TBM and design requirements by the IO and KO design concept: (1) KO TBM has 4 sub-modules considering PIE and its delivery. (2) The FW design was changed into a 15 × 11 rectangular shape. Through a thermo-mechanical analysis using the commercial ANSYS code, the revised design model satisfied 1.5Sm and 3Sm of the allowable stress (Sm) in the RCC-MR code at the maximum stress region of the components. (3) For the BZ design, three Li and Be layers, and one graphite layer were proposed by the iteration, and the appropriate temperature distribution was obtained. Considering the functions of SW and BW, such as the flow manifold and assembling part, the flow scheme and mechanical analysis are on-going.