CFD investigation of effect of helical wire-wrap parameters on the thermal hydraulic performance of 217 fuel pin bundle

Author:

Gajapathy R.,Velusamy K.,Selvaraj P.,Chellapandi P.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference36 articles.

1. Ahmad, A., Kim, K.Y., 2005. Three dimensional analysis of flow and heat transfer in a wire-wrapped fuel assembly. In: proceedings of ICAPP 05, seoul, Korea.

2. Asty, M., 1993. Fast reactor development programme in France during 1992. In: Proc. 26th Meeting of Int. Working Group on Fast Reactors, Vienna, IAEA-TECDOC-741.

3. CFDEXPERT (2008). Zeus Numerix Pvt. Ltd., Pune, India.

4. Thermal hydraulics of rod bundles: the effect of eccentricity;Chauhan;Nucl. Eng. Des.,2013

5. Chen, B.C., Todreas, N.E., 1985. Prediction of coolant temperature field in a breeder reactor including inter assembly heat transfer, COO-2245-20 TR, Rev. 1.

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