Progress of the conceptual design of the European DEMO breeding blanket, tritium extraction and coolant purification systems

被引：50

作者：

Cismondi, F. ^{[1
]}

Spagnuolo, G. A. ^{[2
]}

Boccaccini, L., V ^{[2
]}

Chiovaro, P. ^{[3
]}

Ciattaglia, S. ^{[1
]}

Cristescu, I ^{[2
]}

Day, C. ^{[2
]}

Del Nevo, A. ^{[4
]}

Di Maio, P. A. ^{[3
]}

Federici, G. ^{[1
]}

Hernandez, F. ^{[2
]}

Moreno, C. ^{[5
]}

Moscato, I ^{[3
]}

Pereslavtsev, P. ^{[2
]}

Rapisarda, D. ^{[5
]}

Santucci, A. ^{[4
]}

Utili, M. ^{[4
]}

机构：

[1] EUROfus Consortium, Programme Management Unit, Garching, Germany

[2] Karlsruhe Inst Technol, Karlsruhe KIT, Karlsruhe, Germany

[3] Univ Palermo, Dipartimento Ingn, Viale Sci, I-90128 Palermo, Italy

[4] ENEA, Fus & Technol Nucl Safety & Secur Dept, Rome, Italy

[5] CIEMAT, Fus Technol Div, Madrid, Spain

来源：

FUSION ENGINEERING AND DESIGN | 2020年 / 157卷

关键词：

Breeding blanket; Coolant purification; Tritium extraction and removal; PERMEATION; PBLI;

D O I：

10.1016/j.fusengdes.2020.111640

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：

In the frame of the EUROfusion consortium activities the Helium Cooled Pebble Bed (HCPB) and the Water Cooled Lithium Lead (WCLL) concepts are being developed as possible candidates to become driver Breeding Blanket (BB) for the EU DEMO, which aims at the tritium self-sufficiency and net electricity production. The two BB design options encompass water or helium as coolants and solid ceramic with beryllium/beryllides or PbLi as tritium breeder and neutron multipliers. The BB segments have evolved towards a more stable conceptual design taking into account multiple feasibility aspects and requirements imposed by interfacing systems. Possible solutions to improve shielding capabilities of Helium cooled BB are investigated and the impact of water coolant activation is assessed by studying the spatial distribution of 16N and 17N isotopes dose rates, in particular in proximity of isolation valves. The reference and back-up technologies for the Tritium Extraction and Removal (TER) from the helium purge gas and the PbLi are developed addressing key feasibility aspects and implications on the tokamak layout and with considerable R&D efforts. As the BB internals offer an ideal environment (high temperatures, thin structural material) to promote the tritium permeation, studies are devoted to establish a tritium balance in the different systems during operation, with special care to the permeation rate and inventory in the coolant. Those are the key parameters for the feasibility assessment and technology selection for the Coolant Purification Systems (CPS).

引用

页数：11

共 40 条

[1] Objectives and status of EUROfusion DEMO blanket studies [J].

Boccaccini, L. V. ;

Aiello, G. ;

Aubert, J. ;

Bachmann, C. ;

Barrett, T. ;

Del Nevo, A. ;

Demange, D. ;

Forest, L. ;

Hernandez, F. ;

Norajitra, P. ;

Porempovic, G. ;

Rapisarda, D. ;

Sardain, P. ;

Utili, M. ;

Vala, L. .

FUSION ENGINEERING AND DESIGN, 2016, 109 :1199-1206

[2] Tritium modelling in HCPB breeder blanket at a system level [J].

Carella, Elisabeta ;

Moreno, Carlos ;

Roca Urgorri, Fernando ;

Rapisarda, David ;

Ibarra, Angel .

FUSION ENGINEERING AND DESIGN, 2017, 124 :687-691

[3]

Catanzaro I., 2019

[4]

Chiovaro P., 2019, ASSESSMENT DOSE RATE

[5]

Chiovaro P., 2019, INVESTIGATION DEMO C

[6] The coolant purification system of the European test blanket modules: Preliminary design [J].

Ciampichetti, A. ;

Aiello, A. ;

Coccoluto, G. ;

Ricapito, I. ;

Liger, K. ;

Demange, D. ;

Moreno, C. .

FUSION ENGINEERING AND DESIGN, 2010, 85 (10-12) :2033-2039

[7] Progress in EU Breeding Blanket design and integration [J].

Cismondi, F. ;

Boccaccini, L. V. ;

Aiello, G. ;

Aubert, J. ;

Bachmann, C. ;

Barrett, T. ;

Barucca, L. ;

Bubelis, E. ;

Ciattaglia, S. ;

Del Nevo, A. ;

Diegele, E. ;

Gasparotto, M. ;

Di Gironimo, G. ;

Di Maio, P. A. ;

Hernandez, F. ;

Federici, G. ;

Fernandez-Berceruelo, I. ;

Franke, T. ;

Froio, A. ;

Gliss, C. ;

Keep, J. d ;

Loving, A. ;

Martelli, E. ;

Maviglia, F. ;

Moscato, I. ;

Mozzillo, R. ;

Poitevin, Y. ;

Rapisarda, D. ;

Savoldi, L. ;

Tarallo, A. ;

Utili, M. ;

Vala, L. ;

Veres, G. ;

Zanino, R. .

FUSION ENGINEERING AND DESIGN, 2018, 136 :782-792

[8] Design of a Permeator-Against-Vacuum mock-Up for the tritium extraction from PbLi at low speed [J].

D'Auria, Vincenzo ;

Dulla, Sandra ;

Ravetto, Piero ;

Savoldi, Laura ;

Utili, Marco ;

Zanino, Roberto .

FUSION ENGINEERING AND DESIGN, 2017, 121 :198-203

[9]

Day C., 2019, SMART 3 LOOP FUELCYC, DOI [10.1016/j.fusengdes.2019.04.019., DOI 10.1016/J.FUSENGDES.2019.04.019]

[10] Recent progress in developing a feasible and integrated conceptual design of the WCLL BB in EUROfusion project [J].

Del Nevo, A. ;

Arena, P. ;

Caruso, G. ;

Chiovaro, P. ;

Di Maio, P. A. ;

Eboli, M. ;

Edemetti, F. ;

Forgione, N. ;

Forte, R. ;

Froio, A. ;

Giannetti, F. ;

Di Gironimo, G. ;

Jiang, K. ;

Liu, S. ;

Moro, F. ;

Mozzillo, R. ;

Savoldi, L. ;

Tarallo, A. ;

Tarantino, M. ;

Tassone, A. ;

Utili, M. ;

Villari, R. ;

Zanino, R. ;

Martelli, E. .

FUSION ENGINEERING AND DESIGN, 2019, 146 :1805-1809

← 1 2 3 4 →