EDN: YLICVK
Authors & Affiliations
Artemov V.G., Nersesian N.S.
Research Institute of Scientific Instruments, Sosnovy Bor, Russia
Nersesian N.S. – Researcher. Contacts: 11/2, Krasnye Forts St., Sosnovy Bor, Leningrad Region, Russia, 188540. Tel.: +7 (813) 696-08-83; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Artemov V.G. – Head of the Laboratory, Cand. Sci. (Tech.).
Abstract
The paper focuses on the methodological aspects of reactivity measurements in experiments on insertion and withdrawal of control rods at a critical facility with small gas cooled fast reactor core. Reactivity in the experiments was measured by an inverse solution of kinetics equation. The critical state of the facility was achieved and reactivity measurement experiments were conducted using an external constant neutron source. The authors discuss the influence of delayed neutron and external neutron source parameters, spatial effect, and interference of control rods on the experiment results. Results of experiment simulations obtained with the SAPFIR_RF&RC code are used to include the methodology considerations of the experiments in the comparison against results of precision calculations performed by the Monte Carlo method with the MCU-FR code.
The numerical simulation of the reactivity measurement experiments was carried out by calculating the neutron flux density in ex-core detectors located around the outside perimeter of the reflector.
For this critical facility, it is found that the use of delayed neutron parameters from BNAB-78 and ROSFOND libraries gives the best agreement with the reactivity measurement results. The results of measurement simulations show that the simulation model represents the experimentally determined dependency of reactivity on the positions of detectors and inserted control rods. Therefore, the results of control rod worth calculations can be used for correction of experimental data to avoid uncertainty due to spatial effect.
Experiments with withdrawal of control rods were used when selecting a neutron source for a reactivity meter. The neutron source selection procedure was carried out in two steps. In the first (preliminary) step, the condition of constant reactivity after the end of control rod motion was checked. In the second (finalizing) step, experiments for determining the differential worth of control rods at different withdrawal positions (method of “excursion” with two periods) were used. Numerical simulation results were used to consider the interference effect. The proposed method and simulation model allow for a very accurate and proper comparison between results of reactivity calculations with MCU-FR program and experimental data.
Keywords
small gas cooled reactor, fast reactor, simulation model, SAPFIR_RF&RC code, reference model, MCU-FR code, differential worth, integral worth, control rod, delayed neutron parameters, nuclear data libraries, BNAB-78, ROSFOND, external neutron source, spatial effect, effect of control rod interference, insertion and overcompensation methods
Article Text (PDF, in Russian)
References
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UDC 621.039.51:006.91
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2024, no. 2, 2:8
