Effects of various types of reflectors on the 99Mo production in the VVER-Ts reactor targets

Author:

Kochnov Oleg Yu.,Danilov Pavel A.

Abstract

The effects from introducing various types of reflectors in the VVR-Ts reactor core on the 99Мо production were analyzed. Earlier the effects of only the beryllium reflector on the VVR-Ts reactor core characteristics, such as reactivity margin, neutron flux in experimental channels, and activity of the accumulated 99Мо, were calculated. The calculations are based on a generated precision model of the core which comprises one experimental channel where targets are irradiated for the 99Мо production. The model was built using the SCALE code. The code allows a fairly broad range of calculations to be performed, from criticality estimation to radiological assessment tasks. As the result of the computational analysis of the model, such characteristics were obtained as the effective multiplication factor, the power density in the 99Мо production targets, the neutron flux in the target raw material, and the quantity of the produced 99Мо after 120 hours of irradiation. The data was compared with the results of similar calculations of the VVR-Ts reactor core parameters. Further, the list of the materials used extensively as the reactor core reflector or moderator was formed based on reference literature. A number of models were obtained and analyzed on its basis, in which the water space on the core periphery was substituted for the investigated materials.

Publisher

Pensoft Publishers

Subject

General Medicine

Reference16 articles.

1. Estimation of the 99Mo production increase using advanced design targets in the VVR-ts reactor.;Fomin;Proc. of the 2nd International Conference of Young Scientists, Specialists and Post-Graduate Students “Innovative Small and Super Small Nuclear Reactors”, 15–17 May. Rosatom State Corporation, National Research Nuclear University “MEPhI”. Moscow. NIYaU MIFI Publ.,2017

2. Effects of the beryllium reflector placed in the VVR-ts reactor core on its neutronic performance. Izvestiya Vysshykh Uchebnykh Zavedeniy.;Kochnov;Yadernaya Energetika,,2012

3. Оценка энерговыделения в мишени с урансодержащим материалом при производстве 99Мо с использованием мишеней усовершенствованной конструкции на реакторе ВВР-ц

4. Assessment of the Increasing in 99Mo Production for Different WWR–c Reactor Core Compositions

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