HELIUM-COOLED, FLIBE BREEDER, BERYLLIUM MULTIPLIER BLANKET.

被引：0

作者：

Moir, Ralph W. ^{[1
]}

Lee, Joseph D. ^{[1
]}

Maninger, R.Carroll ^{[1
]}

Neef Jr., William S. ^{[1
]}

Sherwood, Albert E. ^{[1
]}

Berwald, David H. ^{[1
]}

DeVan, Jackson H. ^{[1
]}

Jung, Jungchung ^{[1
]}

机构：

[1] Lawrence Livermore Natl Lab,, Livermore, CA, USA, Lawrence Livermore Natl Lab, Livermore, CA, USA

来源：

Fusion Technology | 1985年 / 8卷 / 1 pt 1期

关键词：

BERYLLIUM AND ALLOYS;

D O I：

10.13182/fst85-a24678

中图分类号：

学科分类号：

摘要：

The concept described for the blanket surrounding a fusion reaction chamber is based on the use of molten fluoride salts to convert fusion energy into electricity and to breed the tritium fuel for the fusion power plant. Helium cools the first-wall and the blanket internals, which consists of a bed of beryllium balls in which neutrons are multiplied. The neutrons are used to breed tritium and also to release extra energy in exothermic nuclear reactions. Tritium is bred in the molten Flibe salt (LiF plus BeF//2) that flows slowly (approximately 0. 1 m/s) in steel tubes and is removed from the salt and the helium by processing both streams.

引用

页码：133 / 148

共 50 条

[41] THERMAL-HYDRAULIC LOCA ANALYSIS OF CHINESE HELIUM-COOLED SOLID BREEDER TEST BLANKET MODULE FOR ITER
Liu, Haibo
Feng, Kaiming
FUSION SCIENCE AND TECHNOLOGY, 2008, 54 (04) : 970 - 977
[42] Assessment of the activation, decay heat, and waste disposal of the US helium-cooled ceramic breeder test blanket module in ITER
Youssef, Mahmoud Z.
Ying, Alice
FUSION ENGINEERING AND DESIGN, 2008, 83 (10-12) : 1764 - 1770
[43] Design and thermal-hydraulic evaluation of helium-cooled ceramic breeder blanket for China fusion engineering test reactor
Lei, Mingzhun
Xu, Shuling
Guo, Chao
Liu, Sumei
Song, Yuntao
Lu, Kun
Pei, Kun
Xu, Kun
INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2018, 42 (04) : 1657 - 1663
[44] Attachment system for helium-cooled blanket of RF DEMO fusion reactor
Leshukov, A
Blinov, Y
Kovalenko, V
Shatalov, G
Strebkov, Y
Strizhov, A
FUSION ENGINEERING AND DESIGN, 2002, 61-62 : 333 - 338
[45] TRITIUM CONTROL IN A HELIUM-COOLED CERAMIC BLANKET FOR A FUSION-REACTOR
DONNE, MD
DORNER, S
FUSION TECHNOLOGY, 1986, 9 (03): : 484 - 491
[46] PASSIVE SAFETY IN A HELIUM-COOLED TRITIUM BREEDING BLANKET WITH STEEL STRUCTURE
CROSSWAIT, KM
MEYER, JE
JOURNAL OF FUSION ENERGY, 1993, 12 (1-2) : 41 - 45
[47] WALL-LOADING LIMITATIONS IN A HELIUM-COOLED FUSION REACTOR BLANKET
MITCHELL, JT
BOOTH, JA
NUCLEAR FUSION, 1974, : 399 - 399
[48] OPTIMAL DESIGN FOR HELIUM COOLED SOLID BREEDER BLANKET OF CFETR
Nogueron, Jose A.
Zhang, Baorui
Zhou, Zhiwei
PROCEEDINGS OF THE 2020 INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING (ICONE2020), VOL 2, 2020,
[49] Conceptual design on interface between ITER and tritium extraction system of Chinese helium-cooled solid breeder test blanket module
Zhang Long
Luo Tianyong
Feng Kaiming
FUSION ENGINEERING AND DESIGN, 2010, 85 (10-12) : 2213 - 2216
[50] Helium-cooled lithium lead: Activation analysis of the test blanket module in ITER
Petrizzi, L.
Auditore, L.
Cambi, G.
Cepraga, D. G.
Villari, R.
FUSION ENGINEERING AND DESIGN, 2008, 83 (7-9) : 1244 - 1248

← 1 2 3 4 5 →