PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY
Series: Nuclear and Reactor Constants

since 1971

Русский (РФ)

ISSN 2414-1038 (online)

ANALYSIS OF SPATIAL EFFECTS IN THE BFS-88 ASSEMBLY FOR MEASURING CONTROL RODS EFFICIENCY WITH A REACTIMETER

EDN: RXYEXS

Authors & Affiliations

Zhirnov A.P., Moiseev A.V., Soldatov E.O., Lamanov S.A., Voitekhova V.V., Davydov V.K., Khakhulin V.I.
N.A. Dollezhal Research & Development Institute of Power Engineering, Moscow, Russia

Zhirnov A.P. – Head of Department.
Moiseev А.V. – Scientific Supervisor of the BREST-OD-300 Project, Cand. Sci. (Phys.-Math.).
Soldatov E.О. – Head of Group. Contacts: 1, bld. 3, pl. Akademika Dollezhalya, Moscow, Russia, 107140. Tel.:+7 (499) 763-04-57; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Lamanov S.A. – Engineer of 2nd Category.
Voitekhova V.V. – Engineer of the 2nd Category.
Davidov V.K. – Senior Researcher.
Khakhulin V.I. – Engineer of the 2nd Category.

Abstract

Physical start-up of fast reactors with lead coolant includes fuel assembly loading, formation of the starting load, work on bringing the reactor to a critical state and measuring the neutron-physical characteristics. The paper performs calculations of the physical start-up of the BR-1200 reactor using the design code system. The estimation of the neutron flux density in the simulation zone showed that an additional detector system must be used to carry out a controlled set of critical mass. The neutron- physical characteristics calculation was performed using the MCU-BR and FACT-BR software packages. The study defines the order of FA loading and coupling CPS CR. During control rods efficiency measurement using detectors the spatial effects are manifested which may affect the experimental values. Spatial effects are analyzed using FACT-BR by resetting the corresponding rod and solving the reversed integra-differential equation of kinetics. Calculation modelling of neutron-physical characteristics of a fast reactor with a lead coolant is performed taking into account calculation errors and uncertainties of the material composition of the core, fuel and FA. In the work, a total error of 0.7 % is accepted. To compensate for this uncertainty, constant reactivity compensators are used. In the process of physical start-up of the reactor, in order to determine its neutron-physical characteristics, it is necessary to carry out complex experimental studies in accordance with the approved program. The paper presents proposals for the program of experiments at the stage of physical start-up: to determine the critical parameters of the core, the temperature effect of reactivity, the efficiency of the CPS and passive feedback system, the relative distribution of energy release over fuel assemblies.

Keywords
fast reactor, criticality, neutron-physical characteristics, lead coolant, physical start-up, neutron flux density detectors, permanent reactivity compensator

Article Text (PDF, in Russian)

References

UDC 621.039.51

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2026, no. 1, 1:4