Integral molten salt reactor neutron physics study using Monte Carlo N-particle code-Reference-Cited by-同舟云学术

Integral molten salt reactor neutron physics study using Monte Carlo N-particle code

Published:2020-08 Issue: Volume:365 Page:110718
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Carter John P.,Borrelli R.A.

Funder

U.S. Department of Energy

Office of Nuclear Energy

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

Reference62 articles.

1. World Nuclear Association, 2019. Generation IV Nuclear Reactors, Tower House, 10 Southampton Street, London, WC2E 7HA, United Kingdom.

2. LeBlanc, D., et al., 2018. Fuel Cycle Flexibility of Terrestrial Energy’s Integral Molten Salt Reactor (IMSR). 38th Annual Conference of the Canadian Nuclear Society and 42nd Annual CNS/CNA Student Conference. 3 June 2018: Print.

3. McCoy, H.E., et al., 2017. New develops in materials for molten salt reactors. Nucl. Appl. Technol. 8(1970) 156–169.

4. A Quick Guide to MCNP;Holden,2018

5. Lucas, 2010. Greg MCNP Tutorial. UW – Engineering Physics Department: Spring. Print.

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