Development of a neutronics analysis code for pebble-bed HTRs-Reference-Cited by-同舟云学术

Development of a neutronics analysis code for pebble-bed HTRs

Published:2018-04 Issue: Volume:329 Page:192-197
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

She Ding,Guo Jiong,Liu Zhihong,Shi Lei

Funder

National Natural Science Foundation

National S&T Major Project

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

Reference18 articles.

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3. Gougar, H.D., Ougouag, A.M., Terry, W.K., 2004. Advanced Core Design and Fuel Management for Pebble-bed Reactors (No. INEEL/EXT-04-02245). Idaho National Laboratory (INL).

4. Hébert, A., 2014. The Version5 Dragon/Donjon Distribution. http://www.polymtl.ca/merlin (accessed 18.09.17).

5. Kunitomi, K., Sun, Y., Ball, S., Brey, H.L., Methnani, M., 2003. Evaluation of High Temperature Gas Cooled Reactor Performance: Benchmark Analysis Related to Initial Testing of the HTTR and HTR-10. International Atomic Energy Agency, Report No. IAEA-TEDOC-1382, 227–322.

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