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Dive into the research topics where D. Yu. Chuvilin is active.

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Featured researches published by D. Yu. Chuvilin.


Fusion Engineering and Design | 1989

Calculated neutron transport verifications by integral 14 MeV-neutron source experiments with multiplying assemblies

V. A. Zagryadskii; D. V. Markovskii; V.M. Novikov; D. Yu. Chuvilin; G.E. Shatalov

This paper is devoted to a comparison of the experimental and calculated leakage neutron spectra and total neutron leakages from U, Th, Pb and Be spherical assemblies and also to a comparison of experimental and calculated reaction rates in U and Th assemblies. It was shown that the calculation with ENDF/B-IV data describes the shape of the neutron spectrum better for all considered materials. The full multiplication of neutrons for the U assembly is reproduced more accurately by the calculation with ENDL-75 data, and for Th, Be and Pb assemblies, by the calculation with ENDF/B-IV data.


symposium on fusion technology | 1993

NEUTRON LEAKAGE SPECTRA FROM Be, Al, Fe, Ni, Pb, LiPb, Bi, U AND Th SPHERES WITH T(d, n) AND 252Cf NEUTRON SOURCES

S.P. Simakov; A.A. Androsenko; P.A. Androsenko; B.V. Devkin; S.I. Dubrovina; M.G. Kobozev; A.A. Lychagin; V.A. Talalaev; D. Yu. Chuvilin; V.A. Zagryadskij

This paper presents the results of time-of-flight measurements of neutron leakage spectra from Be, Al, Fe, Ni, Pb, LiPb, Bi, U and Th spheres with central 14MeV neutron source and from U and Th sphere with 252Cf source. Description of experimental set-up, measuring and correction procedures are given. The obtained data are discussed and compared with transport calculations and evaluated data files.


Crystallography Reports | 2011

Flexible polyvinyl chloride neutron guides for transporting ultracold and very cold neutrons

S. S. Arzumanov; L. N. Bondarenko; P. Geltenbort; V. I. Morozov; V.V. Nesvizhevsky; Yu. N. Panin; A. N. Strepetov; D. Yu. Chuvilin

The transmission of ultracold neutrons (UCNs) through flexible polyvinyl chloride (PVC) tubes with lengths of up to 3 m and an internal diameter of 6–8 mm has been studied. High UCN transmission is found even for arbitrarily bent tubes (single bend, double bend, triple bend, figure eight, etc.). The transmission can be improved significantly by coating the inner surface of the tube with a thin layer of liquid fluorine polymer. The prospects of these neutron guides in fundamental and applied research are discussed.


Journal of Radioanalytical and Nuclear Chemistry | 2003

An interleaved approach to production of 99Mo and 89Sr medical radioisotopes

D. Yu. Chuvilin; J. D. Meister; S. S. Abalin; R. M. Ball; G. Yu. Grigoriev; V. E. Khvostionov; D.V. Markovskij; H. W. Nordyke; V. A. Pavshook

More than half of the worlds annual production of radionuclides is used for medical purposes such as diagnostic imaging of diseases and patient therapy. Using aqueous homogeneous solution reactor technology, production quantities of medical radioisotopes 99Mo and89Sr, can be extracted from one reactor cycle. 99Mo may be produced directly from UO2SO4 uranyl sulfate in an aqueous homogeneous solution nuclear reactor in a manner that produces high purity radionuclides, making efficient use of the reactors uranium fuel solution. The process is relatively simple, economical, and waste free, eliminating uranium targets. The short-lived radioisotope 99mTc is eluted from 99Mo for diagnostic imaging. Radioisotope 89Sr infusion is a therapeutic modality that reduces reliance on narcotic analgesia through palliation of metastatic bone pain caused by metastases of the cancer to the bone. Painful disseminated osseous metastases are common with carcinomas of the lung, prostate, and breast. Synergistic interleaving of two manufacturing processes, one producing 99Mo and another producing 89Sr in the same production cycle of an aqueous homogeneous solution reactor makes full and efficient use of the time for both the neutron irradiation stage and the extraction stage of each radionuclide. Interleaving the capture of 89Sr radioisotope with production processing of 99Mo radioisotope is achieved, since the extraction and subsequent elimination of radionuclide impurities occurs during separate parts of the reactor cycle. The process applies to either HEU or LEU nuclear fuels in an aqueous homogeneous solution reactor.


symposium on fusion technology | 2003

Integral benchmark experiments with 14-MeV neutrons for testing the nuclear data of vanadium

D.V. Markovskij; A.I. Blokhin; V.A. Chirkin; D. Yu. Chuvilin; A.V. Livke; V.I. Nagorny; Yu.Ya. Nefedov; R.A. Orlov; M.V. Savin; V.I. Semenov; A.E. Shmarov; A.M. Shvetsov; V.A. Zagryadsky; A.K. Zhitnik

Abstract The measurements of the gamma-ray and neutron leakage spectra from three vanadium spheres with diameters 10, 24 and 34 cm irradiated by a central 14-MeV neutron source were carried out in the frame of the ISTC Project #910 in collaboration with Forschungszentrum Karlsruhe. The neutron leakage spectra were measured by scintillation detectors and by a gas proportional counter. The gamma-ray leakage spectra were measured with the help of a crystal NaI(Tl). Analysis of these experiments was performed with the available and newly evaluated nuclear data files prepared in the frame of the project activities. A comparison of experimental and calculated neutron and gamma-ray leakage spectra from three vanadium spheres is given.


Radiochemistry | 2014

Determination of the labeling yield and stability of the complexes Bi-BSA-DOTA and Bi-BSA-DTPA

P. P. Boldyrev; S. M. Deev; V. A. Golovachenko; V. A. Zagryadskii; A. S. Zakharov; V. I. Nikolaev; R. F. Nurtdinov; M. A. Proshin; D. Yu. Chuvilin; Yu. A. Yashin

Labeling of a biochemical compound (conjugate) with α-emitting isotopes was studied with the aim to develop a biochemical substance for targeted delivery of α-emitting isotopes to a cancer cell. The 212Bi (212Pb/212Bi) and 213Bi (225Ac/213Bi) isotope generators were developed. A procedure for preparing the conjugate (monoclonal antibody + chelator) with α-emitting isotopes 212Bi and 213Bi and methods for identification of the labeled conjugate (γ-ray spectrometry and protein staining) are presented. The procedure for calibration of the gel filtration column (GFC) for correcting the GFC certificate data, obligatory in such operations, is described. DTPA as chelating agent appeared to be preferable over DOTA, with 70–80% incorporation of 212Bi and 213Bi into the conjugate reached.


International Conference on Nuclear Data for Science and Technology | 2007

Benchmarking of Uranium‐238 Evaluations against Spherical Transmission and (n,xn)‐Reaction Experimental Data

S.P. Simakov; M. G. Kobosev; A.A. Lychagin; V.A. Talalaev; D. Yu. Chuvilin; V. M. Maslov

The double differential cross sections for the U(n,xn) reaction at 14 MeV and neutron leakage spectra from the uranium sphere of 24 cm outer and 8 cm inner diameters with the central T‐D and 252Cf neutron sources measured at the Institute of Physics and Power Engineering were used for benchmarking the evaluated cross sections from ENDF‐B6, JEFF‐3.0, and “Maslov” libraries and preliminary versions of JEFF‐3.1 and ENDF‐B7 evaluations for 238U.


Fusion Engineering and Design | 1993

Measurement of 14 MeV neutron transmission through beryllium

J. Půlpán; M. Králík; T. Novotný; D. Yu. Chuvilin; S. A. Konakov

Abstract A transmission experiment with 14 MeV neutrons on a beryllium spherical shell of 5 cm thickness is reported. The neutron leakage spectrum in the 1.2–16 MeV range was measured by a proton recoil spectrometer based on the NE-213 scintillator. Comparison with calculations revealed that nuclear data from LASL-SUB and JENDL-3.1 libraries cause overestimation of the neutron leakage spectrum in the energy intervals 1.2–8 MeV and 12.5–16 MeV. Data from ENDF/B-VI and IV libraries overestimate the leakage spectrum in 3–8 MeV and 12.5–16 MeV intervals.


Radiochemistry | 2016

A modified electrochemical procedure for isolating 177Lu radionuclide

P. P. Boldyrev; A. V. Kurochkin; M. A. Proshin; D. Yu. Chuvilin; Yu. A. Yashin

A cell for isolating 177Lu from a neutron-irradiated 176Yb target was developed. The procedure involves a combination of two processes: contact reduction of Yb from acetate–chloride solution on sodium amalgam, followed by electrolysis of the solution on a mercury cathode. The process conditions were chosen so that the adjustment of the working solution characteristics (composition, pH, etc.) in going from contact reduction to electrolysis was not required. Both processes are performed in one cell, which reduces the 177Lu loss. On an installation consisting of two cells, the decontamination factor of the 177Lu solution from Yb of up to 106 was reached, which is necessary for obtaining a 177Lu preparation of high specific activity.


Russian Journal of Physical Chemistry A | 2010

Removal of nanoaerosol during the bubbling of the salt melt of beryllium and lithium fluorides for the preparation of reactor radioisotopes

A. V. Zagnit’ko; D. Yu. Chuvilin

The parameters of aerosol particles formed in the course of the spontaneous thermal condensation of vapors and bubbling a 66LiF-34BeF2 (mol %) eutectic salt mixture with helium have been studied. For this purpose, a vertical bubbling mode at T ≈ 900 K and an ampule device for obtaining reactor radioisotopes for medical applications were used. The rate of the bulk removal and the chemical composition of aerosols were measured. The size distribution of the aerosol particles was bimodal, and the mass concentration of the particles exceeded by far the maximum permissible concentration (MPC). The characteristics of regenerated nickel multilayer nanofilters for ultrahigh filtration of aerosols from the salt liquid melt were analyzed.

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