Revision of the EU Helium Cooled Pebble Bed blanket for DEMO

被引:5
|
作者
Hermsmeyer, S [1 ]
Dolensky, B [1 ]
Fiek, J [1 ]
Fischer, U [1 ]
Köhly, C [1 ]
Malang, S [1 ]
Pereslavtsev, P [1 ]
Rey, J [1 ]
Xu, Z [1 ]
机构
[1] Forschungszentrum Karlsruhe, D-76021 Karlsruhe, Germany
关键词
D O I
10.1109/FUSION.2003.1426678
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
The Helium Cooled Pebble Bed (HCPB) blanket has been a European DEMO reference concept for nearly a decade. While the recent European Power Plant Conceptual Study (PPCS) confirmed that the HCPB built from the reduced-activation ferritic-martensitic steel Eurofer is an acceptable choice of a blanket relying only on limited technological extrapolation, it became clear that the HCPB needs a major review to adapt it to the PPCS plant lay-out: (i) the selection of an ITER-like modular blanket segmentation requires significant changes to the sector ("banana") segmentation of the previous DEMO regarding blanket box pressurisation and front side access; (ii) the drive to higher blanket efficiency requires a review of the thermal lay-out; (iii) further integration of all in-vessel components within a reactor concept, using modern CAD tools, is needed for the technological credibility of the plant. In addition, the review was an opportunity to (iv) simplify the blanket by introducing modularity for the breeding zone; and, (v) introduce results from recent breeding blanket R&D. This paper presents the revised design and discusses design choices for the First Wall the blanket box stiffened by a grid of plates, the back plate for a modular HCPB breeding insert; at this stage of work the issue of reactor integration is neglected. Furthermore, analysis results are presented (j) on the neutronic behaviour of the blanket concept, using the plant lay-out of the PPCS; (jj) on the thermal-hydraulic lay-out; (jjj) on the structural-mechanical behaviour of the blanket under pressurisation. The new design is an important prerequisite for defining DEMO relevant test blanket modules for ITER, and for future studies on DEMO and power reactors.
引用
收藏
页码:440 / 445
页数:6
相关论文
共 50 条
  • [41] Preliminary design of EU DEMO helium-cooled breeding blanket primary heat transfer system
    Moscato, I.
    Barucca, L.
    Ciattaglia, S.
    Di Maio, P. A.
    Federici, G.
    FUSION ENGINEERING AND DESIGN, 2018, 136 : 1567 - 1571
  • [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] Experimental investigations of flow distribution in coolant system of Helium-Cooled-Pebble-Bed Test Blanket Module
    Ilic, M.
    Schlindwein, G.
    Meyder, R.
    Kuhn, T.
    Albrecht, O.
    Zinn, K.
    FUSION ENGINEERING AND DESIGN, 2016, 103 : 53 - 68
  • [44] 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
  • [45] Methodology for accident analyses of fusion breeder blankets and its application to helium-cooled pebble bed blanket
    Panayotov, Dobromir
    Grief, Andrew
    Merrill, Brad J.
    Humrickhouse, Paul
    Trow, Martin
    Dillistone, Michael
    Murgatroyd, Julian T.
    Owen, Simon
    Poitevin, Yves
    Peers, Karen
    Lyons, Alex
    Heaton, Adam
    Scott, Richard
    FUSION ENGINEERING AND DESIGN, 2016, 109 : 1574 - 1580
  • [46] Thermo-mechanical testing of Li-ceramic for the helium cooled pebble bed (HCPB) breeding blanket
    Dell'Orco, G
    Ancona, A
    DiMaio, A
    Simoncini, M
    Vella, G
    JOURNAL OF NUCLEAR MATERIALS, 2004, 329 : 1305 - 1308
  • [47] Pressurizing behavior on ingress of coolant into pebble bed of blanket of Fusion DEMO reactor
    Tsuru, Daigo
    Enoeda, Mikio
    Akiba, Masato
    FUSION ENGINEERING AND DESIGN, 2007, 82 (15-24) : 2274 - 2281
  • [48] Safety analysis of ITER test blanket module for water cooled blanket with pebble bed breeder
    Enoeda, M
    Kuroda, T
    Moriyama, K
    Ohara, Y
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2001, 38 (11) : 921 - 929
  • [49] TRITIUM RELEASE CHARACTERISTICS OF NEUTRON-IRRADIATED REFERENCE BERYLLIUM PEBBLES FOR THE HELIUM COOLED PEBBLE BED (HCPB) BLANKET
    Vitins, Aigars
    Zubkovs, Vitalijs
    Kizane, Gunta
    Pajuste, Elina
    Kinerte, Valentina
    FUSION SCIENCE AND TECHNOLOGY, 2011, 60 (03) : 1143 - 1146
  • [50] 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