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Control Rod Withdrawal and Sodium Natural Circulation Tests Performed during the PHENIX End-of-Life Experiments (I33012)

The CRP, with the participation of institutes from eight countries, contributed to improving capabilities in sodium cooled reactor simulation through code verification and validation, with particular emphasis on temperature and power distribution calculations and the analysis of sodium natural circulation phenomena.

A new TECDOC 1742 entitled 'Benchmark Analyses on the Control Rod Withdrawal Tests Performed during the PHENIX End-of-Life Experiments' has been recently published.
TECDOC link:


This publication documents the experience gained in a second phase of an IAEA coordinated research project on control rod withdrawal and sodium natural circulation tests performed during the Phenix end-of-life experiments.
Presented in this publication are the benchmark analyses of the control rod withdrawal tests, aimed at the evaluation of control rod efficiencies, and the effects of control rod insertion/withdrawal on key operational and safety parameters such as reactivity, flux and power deformations.

Examples of achieved results are illustrated below:

The comparison of results among participants and against the experimental data carried out within the CRP allowed improving neutronic calculation methods and tools which will be used for the design and analysis of innovative fast reactors.

Illustration of the PHENIX bloc reactor: