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Abstract <p>The IBR-4 pulsed reactor with a power of 4 MW and a pulse repetition frequency of 10 1/s is considered as a pulsed neutron source to replace the IBR-2M reactor, which will be decommissioned by the end of the 2030s. The IBR-4 design is based on the MBIR reactor implementing the principles of continuity of succesful solutions used in the IBR-2 and IBR-2M reactors. The IBR-4 core ensures the nuclear safety of the reactor and minimizes low-frequency fluctuations in pulse energy. The IBR-4 design is a development of the basic design of the core with the addition of beryllium reflectors and small-volume water moderators. The&#xa0;IBR-4 reactor makes it possible to obtain thermal neutron flux densities on the surface of the water moderator for the extracted neutron beams at a level of 1.2 × 10<sup>14</sup> n/(cm<sup>2</sup> s), and, in the region close to the surface of the moderator, 3.0 × 10<sup>14</sup> n/(cm<sup>2</sup> s). Thus, IBR-4 is a powerful pulsed source of thermal neutrons.</p>

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Preliminary Computations for the Pulsed Reactor IBR-4. Optimization of the Neutron Flux

  • 期刊论文

  • 发表日期：

    2025年2月1日

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  • Yu. N. Pepelyshev,
  • A. V. Vinogradov,
  • A. D. Rogov,
  • D. Sumkhuu

摘要

Abstract

The IBR-4 pulsed reactor with a power of 4 MW and a pulse repetition frequency of 10 1/s is considered as a pulsed neutron source to replace the IBR-2M reactor, which will be decommissioned by the end of the 2030s. The IBR-4 design is based on the MBIR reactor implementing the principles of continuity of succesful solutions used in the IBR-2 and IBR-2M reactors. The IBR-4 core ensures the nuclear safety of the reactor and minimizes low-frequency fluctuations in pulse energy. The IBR-4 design is a development of the basic design of the core with the addition of beryllium reflectors and small-volume water moderators. The IBR-4 reactor makes it possible to obtain thermal neutron flux densities on the surface of the water moderator for the extracted neutron beams at a level of 1.2 × 1014 n/(cm2 s), and, in the region close to the surface of the moderator, 3.0 × 1014 n/(cm2 s). Thus, IBR-4 is a powerful pulsed source of thermal neutrons.