Experimental and operational validation of burn-up calculations for the Syrian MNSR

Author:

Omar H.,Haddad Kh.,Ghazi N.,Alsomel N.

Publisher

Elsevier BV

Subject

Waste Management and Disposal,Energy Engineering and Power Technology,Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Reference15 articles.

1. A general description of lattice code WIMSD;Askew;Journal of the British Nuclear Energy Society,1966

2. Experimental and calculation research of heat generation field and burnup of fuel IRT;Bushuev;Atomnaya Energiya (Moscow),2000

3. Control rod worth calculation for VVER-1000 nuclear reactor using WIMS and CITATION codes;Fadaei;Progress in Nuclear Energy,2009

4. Burn up calculations for the Iranian miniature reactor: a reliable and safe research reactor;Faghihi;Nuclear Engineering and Design,2009

5. Fowler, T.B., Vondy, D.R., 1971. Nuclear Reactor Core Analysis Code CITATION. ORNL-TM-2496.

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