EDN: MPWDEV
Authors & Affiliations
Bezhunov G.M.1, Bogdanov S.A.1, Volnistov D.V.1, Lachugin A.V.2, Masterov A.V.1, Nikolaev S.A.1, Rykov N.S.1, Kocherygin M.V.2, Samokhvalov L.A.2, Tipochenkov E.T.3, Chernov V.A.1
1 A.I. Leipunsky Institute for Physics and Power Engineering, Obninsk, Russia
2 Scientific and Production Firm “Sosny”, Dimitrovgrad, Russia
3 Scientific and Production Association “KVANT”, Obninsk, Russia
Bezhunov G.M.1 – Leading Researcher, Cand. Sci. (Phys.-Math.)ю Contacts: 1, pl. Bondarenko, Obninsk, Kaluga region, 249033, Russia. Tel.: +7 (484) 399-70-00 (add. 43-22); e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Bogdanov S.A.1 – Deputy Head of Department, Cand. Sci. (Phys.-Math.).
Masterov A.V.1 – Leading Research Engineer.
Nikolaev S.A.1 – Head of Laboratory.
Rykov N.S.1 – Leading Research Engineer.
Chernov V.A.1 – Leading Researcher, docent.
Kocherigin M.V.2 – Lead Engineer.
Lachugin A.V.2 – Chief Engineer.
Samokhvalov L.A.2 – Lead Engineer.
Tipochenkov E.T.3– Head of Design Department.
Abstract
A system for measuring the mass of fissile nuclides (FN) and the activity of individual nuclides in solid radioactive waste (SRW) in containers up to 500 liters, including high-level waste, has been developed, manufactured, and tested. The measuring system includes a pulsed neutron generator (PNG) with a neutron yield of 108 s–1, a neutron moderating unit with counters of super cadmium neutrons and a measuring cavity for placing containers, a time pulse analyzer, an industrial computer with a code for accumulating and processing time spectra of pulses from neutron registration.
Experimental and computational research has been performed for models of SRW containers with a volume of 100 liters and 500 liters with graphite and steel matrices of various densities with a FN content of 5 to 245 g using certified objects and well-characterized samples that include uranium and plutonium compounds of various geometric sizes. The parameters of the measuring system, including the response values in units of counts per second per gram of FN in the container and per neutron of the PNG, are determined. The measurement time at a PNG trigger frequency of 20 Hz with a neutron yield of ~107 n/pulse is 200 s.
The influence of various factors on the measurement results is estimated: the moisture content of the matrix, the chemical composition and density of the matrices, the heterogeneity of the arrangement of FN in space, the presence of internal neutron sources, burnup and initial enrichment of uranium in the spent nuclear fuel.
Measurements of the mass of fissile nuclides in the containers using the developed system are possible for the case of highly active SRW with the presence of gamma-emitting nuclides and spontaneous neutron sources with an intensity of up to 5·107 s–1 in the container. The specific activities of the nuclides Cs-137 and Co-60 are determined using a certified measurement method developed by Scientific and Production Center ASPECT, Dubna, and Laboratory of Spectrometry and Radiometry (LSRM), Mendeleevo, using 3 gamma-spectrometric modules with CdZnTe detectors manufactured by JSC Scientific and Production Center ASPECT, Dubna.
The obtained results were used in the development of a methodology for measuring the specific activity and quantity of nuclear material in containers with solid radioactive waste, developed and certified by IPPE.
The methodological work was carried out by IPPE specialists, the design work and manufacture of setup were carried out by “Sosny” specialists, the design and manufacture of neutron detectors and secondary electronic equipment were carried out by “KVANT” specialists.
Keywords
solid radioactive waste, AMB reactors, fissile nuclides, active neutron method, pulsed neutron generator, boron neutron detectors, time analysis, prompt fission neutrons, neutron detection efficiency, MCNP, high-level waste, gamma spectrometry
Article Text (PDF, in Russian)
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UDC 621.039:53.082.79
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2025, no. 4, 4:10
