Preliminary transient thermal analysis for safety of the dual-cooled waste transmutation blanket for the FDS-I

Fusion Engineering and Design

Volumn 81, Issue 8-14 PART B, 2006, Pages 1397-1401

  Bai, Y ^a   Chen, H ^a   Ke, Y ^a   Wang, W H ^a   Zheng, S L ^a  

^a INSTITUTE OF PLASMA PHYSICS   (China)

Author keywords

DWT blanket; FDS I; Safety; Thermal; Transient

Indexed keywords

ACCIDENT PREVENTION; HELIUM; LITHIUM COMPOUNDS; PLASMAS; THERMOANALYSIS;

DUAL-COOLED WASTE TRANSMUTATION (DWT) BLANKET; ENERGY GAIN; TRANSIENT;

FUSION REACTORS;

EID: 32544453052     PISSN: 09203796     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.fusengdes.2005.09.080     Document Type: Article

References (9)

1. Y.C. Wu, J.P. Qian, and J.N. Yu The fusion-driven hybrid system and its material selection J. Nucl. Mater. 307-311 2002 1629 1636
2. Y. Wu, S. Zheng, X. Zhu, W. Wang, H. Wang, and S. Liu Conceptual design of the fusion-driven subcritical system FDS-I Fusion Eng. Des. 81 2006 1305 1311
3. V. Tang, and R.R. Parker Temperature transients of a fusion-fission ITER pebble bed reactor in loss of coolant accident Fusion Eng. Des. 65 2003 11 26
4. Q. Huang, J. Li, and Y. Chen Study of irradiation effects in China low activation martensitic steel CLAM J. Nucl. Mater. 329-333 2004 268 272
5. E.A. Mogahed, L. El-Guebaly, A. Abdou, P. Wilson, D. Henderson The ARIES Team Loss of Coolant Accident and Loss of Flow Accident Analysis of the ARIES-AT Design, Presented at the 14th Topical Meeting on the Technology of Fusion Energy Park City, UT, October 15-19 2000
6. ITER EDA Documentation Series No. 24, ITER Technical Basis, IAEA, Vienna, 2002.
7. ANSYS User's Manual, rev. 5.5, Swanson Analysis System, 2000.
8. Q. Huang, M. Chen, L. Peng, X. Zhu, Y. Chen, and Y. Wu Activation characteristics of the dual-cooled waste transmutation blanket for the Fusion-Driven Subcritical System (FDS) Chinese J. Nucl. Sci. Eng. 24 2004 269 276
9. H.Y. Khater, E.A. Mogahed, D.K. Sze, M.S. Tillack, X.R. Wang The ARIES Team ARIES-ST safety design and analysis Fusion Eng. Des. 65 2003 285 301