Nuclear Technology / Volume 168 / Number 2 / November 2009 / Pages 405-410
Shielding / Special Issue on the 11th International Conference on Radiation Shielding and the 15th Topical Meeting of the Radiation Protection and Shielding Division (Part 2) / Radiation Protection / dx.doi.org/10.13182/NT09-A9217
NAÏADE 1 shielding experiments were performed in the shielding laboratory at the Commissariat à l'Energie Atomique (French Atomic Energy Commission) in Fontenay aux Roses during the period 1965-1970. These experiments consisted of studying either the pure thermal neutron attenuation or the fission neutron attenuation in various materials such as water, iron, graphite, concrete, and multilayer shields. A reassessment of the experimental results was made between 2003 and 2005, and the results were evaluated again during the period 2007-2008. For each experimental configuration, the fission neutron source of a converter was calculated by using the TRIdimensionel POLYcinétique (TRIPOLI-4) Monte Carlo code. A part of the experimental results has been compared to the results of TRIPOLI-4. This work will be continued to analyze other benchmarks with integration into the Shielding INtegral Benchmark Archive Database (SINBAD).