Safety requirement assessment of fuel sample test in Tehran research reactor
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- 作者：Farrokh Khoshahval ; f_khoshahval@sbu.ac.ir" class="auth_mail" title="E-mail the corresponding author ; Amin Davari
- 关键词：Fuel rod sample ; Neutronic and thermo-hydraulic analysis ; MCNP ; CFD
- 刊名：Progress in Nuclear Energy
- 出版年：2016
- 出版时间：August 2016
- 年：2016
- 卷：91
- 期：Complete
- 页码：208-216
- 全文大小：2697 K
文摘
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The effect of adding a fuel rod sample to TRR core are investigated.
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The maximum fuel rod sample enrichment should not exceed the value of 1.5%.
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Insertion of this fuel rod sample has not substantial effect on the safety criteria of TRR main core.