Subject
Waste Management and Disposal,Energy Engineering and Power Technology,Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering
Reference35 articles.
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4. MCNP-A General Monte Carlo Code for Neutron and Photon Transport;Briesmeister,1986
5. Biases in the Estimation of keff and its Errors by Monte Carlo Methods;Brissenden;Ann. Nucl. Energy,1986
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