WEKO3
アイテム
CONCEPTUAL DESIGN OF BLANKET MATERIALS TEST MODULES FOR A-FNS
https://repo.qst.go.jp/records/77349
https://repo.qst.go.jp/records/77349812e4335-3627-435f-ae22-440d24839981
| Item type | 会議発表用資料 / Presentation(1) | |||||
|---|---|---|---|---|---|---|
| 公開日 | 2019-11-07 | |||||
| タイトル | ||||||
| タイトル | CONCEPTUAL DESIGN OF BLANKET MATERIALS TEST MODULES FOR A-FNS | |||||
| 言語 | ||||||
| 言語 | eng | |||||
| 資源タイプ | ||||||
| 資源タイプ識別子 | http://purl.org/coar/resource_type/c_c94f | |||||
| 資源タイプ | conference object | |||||
| アクセス権 | ||||||
| アクセス権 | metadata only access | |||||
| アクセス権URI | http://purl.org/coar/access_right/c_14cb | |||||
| 著者 |
Kwon, Saerom
× Kwon, Saerom× Sato, Satoshi× Nakamura, Makoto× Ota, Masayuki× Park, ChangHo× Oyaizu, Makoto× Ochiai, Kentaro× Kasugai, Atsushi× Kwon, Saerom× Satoshi, Sato× Makoto, Nakamura× Masayuki, Ota× Park, ChangHo× Makoto, Oyaizu× Kentaro, Ochiai× Atsushi, Kasugai |
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| 抄録 | ||||||
| 内容記述タイプ | Abstract | |||||
| 内容記述 | Advanced Fusion Neutron Source (A-FNS) is based on a 40 MeV, 125 mA deuteron accelerator with liquid Li target. Now, we are performing conceptual designs of A-FNS and its test modules. A-FNS provides 8 kinds of test modules for fusion reactor materials. In this study, we newly design the test modulus on Blanket Functional Material Test Module (BFMTM), Tritium Release Test Module (TRTM), and Activated Corrosion Product Module (ACPM). In the BFMTM, we irradiate the small rectangular test specimens of lithium titanate oxide and beryllide, which are the functional materials of the Japanese DEMO blanket. It is located at behind of the other test module, which is designed for irradiation test of the blanket structural material, F82H. We design the rectangular vessel, the honeycomb vessel and the cylindrical capsules for BFMTM. The honeycomb vessel concept is similar to a fuel rod of a fast breeder reactor. Total 47 cylindrical capsules (5 rows in beam direction, 9-10 capsules in each row) are installed in the honeycomb vessel, and the honeycomb vessel is installed in the rectangular vessel. The irradiation temperatures are controlled from 300 to 1000 ºC by an electrical heater and helium gas. The helium gas flow, its temperature and the temperatures of the capsules are measured by the on-line measurement. After the irradiation, all specimens are delivered to PIE facility by remote handling. Nuclear performance has been calculated using MCNP. The maximum neutron irradiation damage of Be is 0.8 dpa/fpy in the capsule, and the design target of 2 dpa can be achieved by 3 fpy irradiation. In the TRTM, we irradiate the small pebbles of the functional materials of the DEMO blanket and measure the tritium release and recovery properties by the on-line measurement. It is located at 30 cm away from the BFMTM in beam direction. The pebbles are packed in the cylindrical capsules of nickel alloy. The electrical heater is surrounding the capsules. Tritium permeation gap and helium flow gap are installed around the pebble packed vessels. Rig cylinders of SS316L or F82H are provided between the gaps. The irradiation temperatures are controlled from 300 to 1000 ºC, the interval temperature is 100 ºC. Total 16 cylindrical capsules (8 capsules each irradiation temperature for lithium titanate oxide and ones for beryllide) are installed in the module. We evaluated tritium production rates in each capsule by MCNP and confirmed that the values were measurable using a commercially instrument such as an ionization chamber. In the ACPM, we irradiate the F82H cooling water pipes. High-temperature and high-pressure water (300 ºC, 15 MPa), which are same condition as the DEMO blanket, flows in the pipes. We measure the ACPs in the F82H pipes by the on-line measurement of the water quality. The location of ACPM is same to that of BSMTM under three damage conditions, 4, 6 and 10 dpa/fpy. The irradiation time conditions are 100, 400, 900, 1600 and 3000 hours. The water quality measurement system is installed at a downstream area of each capsule to trap and measure the sample by ICP-MS. After the irradiation, the pipe specimens are delivered to PIE facility and are measured ACPs (elution ion, particulate oxide, etc.). |
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| 会議概要（会議名, 開催地, 会期, 主催者等） | ||||||
| 内容記述タイプ | Other | |||||
| 内容記述 | 第19回核融合炉材料に関する国際会議(ICFRM-18)への出席 | |||||
| 発表年月日 | ||||||
| 日付 | 2019-11-26 | |||||
| 日付タイプ | Issued | |||||
