Tritium Behavior in HCPB Breeder Blanket Unit: Modeling and Experiments

被引:14
|
作者
Carella, E. [1 ]
Moreno, C. [1 ]
Urgorri, F. R. [1 ]
Demange, D. [2 ]
Castellanos, J. [1 ]
Rapisarda, D. [1 ]
机构
[1] CIEMAT, Natl Lab Magnet Fus, Madrid, Spain
[2] KIT, Inst Tech Phys, Tritium Lab, Karlsruhe, Germany
关键词
Tritium modeling; HCPB; breeder unit; permeation; tritium residence time; COMPREHENSIVE MODEL; RELEASE; TRANSPORT; DEUTERIUM;
D O I
10.1080/15361055.2017.1289584
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
Tritium behavior in a breeding blanket is a key design issue because of its impact on safety and fuel self-sufficiency best performance. Considering the difficulty in handling and its high cost, it is intended to prepare a simulation tool for tritium transport in the HCPB (Helium Cooled Pebble Bed) breeder blanket unit concept. The objective of this work is to evaluate tritium inventory inside several components of the breeder unit (pebble bed and purge gas) and its permeation into the coolant. Some simplified assumptions have been adopted and the results compared with others studies obtained by different simulation tools. Finally an example in which different experimental values of tritium residence time in ceramic breeder is presented with the purpose to observe the capability of the program to be integrated with experimental campaigns.
引用
收藏
页码:357 / 362
页数:6
相关论文
共 50 条
  • [41] Tritium Breeding Ratio Calculation for ITER Tokamak Using Developed Helium Cooled Pebble Bed Blanket (HCPB)
    Soltani, Behrooz
    Habibi, Morteza
    JOURNAL OF FUSION ENERGY, 2015, 34 (03) : 604 - 607
  • [42] Tritium Breeding Ratio Calculation for ITER Tokamak Using Developed Helium Cooled Pebble Bed Blanket (HCPB)
    Behrooz Soltani
    Morteza Habibi
    Journal of Fusion Energy, 2015, 34 : 604 - 607
  • [43] Tritium breeding capability of water cooled ceramic breeder blanket with different container designs
    Gwon, Hyoseong
    Tanigawa, Hisashi
    Hattori, Kentaro
    Iida, Hiromasa
    Hirose, Takanori
    Kawamura, Yoshinori
    FUSION ENGINEERING AND DESIGN, 2019, 146 : 1886 - 1890
  • [44] Evaluation of nuclear heating, tritium breeding and shielding efficiency of the DEMO HCLL breeder blanket
    Jordanova, J
    Fischer, U
    Pereslavtsev, P
    Poitevin, Y
    Li Puma, A
    Cardella, A
    Adamski, A
    FUSION ENGINEERING AND DESIGN, 2005, 75-79 (SUPPL.) : 963 - 967
  • [45] Study and optimization on tritium production performance of cfetr helium cooled solid breeder blanket
    Zhang B.
    Xie H.
    Lang M.
    Sun Q.
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2018, 52 (09): : 1649 - 1655
  • [46] Neutronics experimental study on tritium production in solid breeder blanket mockup with neutron reflector
    Sato, Satoshi
    Verzilov, Yury
    Ochiai, Kentaro
    Wada, Masayuki
    Kutsukake, Chuzo
    Tanaka, Shigeru
    Abe, Yuichi
    Seki, Masakazu
    Oginuma, Yoshikazu
    Kawabe, Masaru
    Nishitani, Takeo
    Konno, Chikara
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2007, 44 (04) : 657 - 663
  • [47] Hydraulic modeling of a segment of the EU DEMO HCPB breeding blanket back supporting structure
    Bertinetti, Andrea
    Froio, Antonio
    Ghidersa, Bradut-Eugen
    Gonzalez, Francisco Alberto Hernandez
    Savoldi, Laura
    Zanino, Roberto
    FUSION ENGINEERING AND DESIGN, 2018, 136 : 1186 - 1190
  • [48] PROGRESS OF TRITIUM EXTRACTION AND MEASUREMENT METHODS DEVELOPMENT FROM LIQUID BREEDER BLANKET IN KOREA
    Lee, Eo Hwak
    Kim, Suk Kwon
    Yoon, Jae Sung
    Lee, Dong Won
    Cho, Seungyon
    FUSION SCIENCE AND TECHNOLOGY, 2012, 62 (01) : 77 - 82
  • [49] TRITIUM TRANSPORT MODELING AND ANALYSIS FOR HCCB BLANKET OF CFETR
    Zhang, Baorui
    Xia, Zhaoyang
    Zhou, Zhiwei
    PROCEEDINGS OF 2021 28TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING (ICONE28), VOL 3, 2021,
  • [50] MODELING OF TRITIUM RECOVERY FROM CTR SOLID BREEDER
    TERAI, T
    TAKAHASHI, Y
    TANAKA, S
    YAMAWAKI, M
    FUSION ENGINEERING AND DESIGN, 1989, 8 : 349 - 354