Thermal-hydraulic analyses of transients in an actinide-burner reactor cooled by forced convection of lead

Thermal-hydraulic analyses of transients in an actinide-burner reactor cooled by forced convection of lead–bismuth

Published:2003-09 Issue:2 Volume:224 Page:149-160
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Davis Cliff B.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference11 articles.

1. Boardman, C.E., Dubberly, A.E., Carroll, D.G., Hui, M., Fanning, A.W., Kwant, W., 2000. A description of the S-PRISM plant, ICONE-8168. In: Proceedings of ICONE-8, Baltimore, MD, April 2–6.

2. Carlson, K.E., Roth, P.A., Ransom, V.H., 1986. ATHENA Code Manual, vol. I. Code Structure, System Models, and Solution Methods. Idaho National Engineering Laboratory, EGG-RTH-7397.

3. Davis, C.B., Shieh, A.S., 2000. Overview of the use of ATHENA for thermal-hydraulic analysis of systems with lead–bismuth coolant. In: Proceedings of ICONE-8, Baltimore, MD, April 2–6.

4. Core power limits for a lead–bismuth natural circulation actinide burner reactor;Davis;Nucl. Eng. Des.,2002

5. Dostal, V., Todreas, N.E., Hejzlar, P., Kazimi, M.S., 2001. Power Conversion Cycle Selection for the LBE Cooled Reactor with Forced Circulation. Massachusetts Institute of Technology, MIT-ANP-TR-084.

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