| Title: |
Extended Lead Target for Studying the Perspectives of the Accelerator-Driven Subcritical Reactor. |
| Authors: |
Paraipan, Mihaela; Abduvaliev, Azizbek; Balabekyan, Anahit; Belov, Oleg V.; Ergashev, Feruzjon H.; Javadova, Vafa M.; Korneev, Sergey V.; Kostov, Latchesar K.; Khushvaktov, Jurabek H.; Kulikov, Sergey A.; Solnyshkin, Alexandr A.; Sorokin, Vladimir V.; Tran, Toan N.; Tyutyunnikov, Sergey I. |
| Source: |
Nuclear Science & Engineering; Jun2026, Vol. 200 Issue 6, p1490-1502, 13p |
| Subject Terms: |
Accelerator-driven systems; Ion beams; Energy consumption; Radioactive wastes; Nuclear reactor materials; Fuel cycle; Radioactive substances; Neutron flux |
| Company/Entity: |
Joint Institute for Nuclear Research |
| Abstract: |
An analysis of possible experiments meant to check the results of previous theoretical work about the perspectives of an accelerator-driven subcritical reactor (ADSR) is performed. In previous works, it was shown that ADSRs can represent not only a solution for the problem of nuclear waste but also an efficient source of energy. With beam intensities above 1016 p/s, an energy gain G higher than 15 is achieved, and the use of light ion beams, especially 7Li with energy of 0.25 to 0.3 AGeV interacting in a Be converter instead of 1- to 1.5-GeV protons, ensures G > 20 and allows a significant reduction of the accelerator length. Based on the analysis, an extended lead target was designed and is under construction in the frame of the ADSR project at the Joint Institute for Nuclear Research, Dubna. The target is dedicated to comparative study of the energy efficiency of proton and ion beams on one side and of the influence of the shape of the neutron spectrum on the breeding capability of ADSR on the other side. The target consists of a lead block with dimensions of 80 × 80 × 150 cm, surrounded by a stainless steel blanket 10 cm thick as a substitute for lead-bismuth coolant. The target has a central hole with a radius of 10 cm and length of 120 cm. Converters from various materials, with a total length of 110 cm, are placed in the central hole, ensuring a beam window with a length of 10 cm and holes with a length of 150 cm in the horizontal and vertical directions, at different radii for the placement of the detectors. The fission distribution obtained with uranium foils is analyzed. The breeding capability is estimated with the ratio of the neutron capture rate in 238U to the fission rate in 239Pu. Expected results predicted by simulation for different beams and converter materials are presented. [ABSTRACT FROM AUTHOR] |
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| Database: |
Complementary Index |