NSR Query Results

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NSR database version of April 27, 2024.

Search: Author = A.N.Gudkov

Found 12 matches.

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1992GU17      Radiochim.Acta 57, 69 (1992)

A.N.Gudkov, S.V.Krivasheev, A.B.Koldobski, V.V.Kovalenko, E.Yu.Bobkov, V.M.Givun

Yields of Delayed Neutron Precursors in the Fission of Actinides

NUCLEAR REACTIONS ²²⁹Th, ^{233,235,236,238}U, ²³⁷Np, ^240,241,242Pu, ²⁴¹Am, ²⁴⁹Cf(n, F), E=fast; measured cumulative yields for ^87,89Br, ^137,138,139I, ^93,94Rb, delayed neutron precursors.

Data from this article have been entered in the EXFOR database. For more information, access X4 dataset41157.

1989BO51      At.Energ. 67, 408 (1989); Sov.At.Energy 67, 904 (1989)

E.Yu.Bobkov, A.N.Gudkov, A.N.Dyumin, A.B.Koldobsky, M.Ya.Kondratko, S.V.Krivasheev, A.V.Mosesov, L.M.Nikitin, V.A.Smolin, A.A.Solonkin

Measurement of Delayed-Neutron Group Yields following the Fission of ²³⁵U, ²³⁶U, ²³⁸U, ²³⁷Np, ²⁴²Pu by 14.7 MeV Neutrons

NUCLEAR REACTIONS ^235,236,238U, ²³⁷Np, ²⁴²Pu(n, F), E=14.7 MeV; measured delayed neutron spectra following fission.

Data from this article have been entered in the EXFOR database. For more information, access X4 dataset41055.

1989GU15      Yad.Fiz. 49, 1551 (1989)

A.N.Gudkov, A.B.Koldobsky, S.V.Krivasheev, N.A.Lebedev, V.A.Pchelin

Delayed Neutron Yields for Thermal Neutron-Induced Fission of ²²⁹Th

NUCLEAR REACTIONS ²²⁹Th(n, F), E=thermal; measured absolute delayed neutron yields fllowing fission; deduced even-odd effects. Other data input.

Data from this article have been entered in the EXFOR database. For more information, access X4 dataset41730.

1989GU21      At.Energ. 66, 100 (1989); Sov.At.Energy 66, 115 (1989)

A.N.Gudkov, V.M.Zhivun, A.V.Zvonarev, V.V.Kovalenko, A.B.Koldobsky, Yu.F.Koleganov, S.V.Krivasheev, V.B.Pavlovich, N.S.Piven, E.V.Semenova

Measurement of the Delayed-Neutron Yields in the Fission of ²³³U, ²³⁶U, ²³⁷Np, ²⁴⁰Pu, and ²⁴¹Pu by Neutrons from the Spectrum of a Fast Reactor

NUCLEAR REACTIONS ^233,236U, ²³⁷Np, ^240,241Pu(n, F), E=reactor; measured delayed neutron yields following fission.

Data from this article have been entered in the EXFOR database. For more information, access X4 dataset41026.

1989GU24      At.Energ. 67, 218 (1989); Sov.At.Energy 67, 702 (1989)

A.N.Gudkov, S.V.Krivasheev, A.B.Koldobsky, E.Yu.Bobkov, Yu.F.Koleganov, A.V.Zvonarev, V.B.Pavlovich

Determining Delayed-Neutron Group Yields for Fast Neutron ²³⁵U and ²⁴¹Am Fission

NUCLEAR REACTIONS ²³⁵U, ²⁴¹Am(n, F), E=fast; measured delayed neutron yields following fission.

Data from this article have been entered in the EXFOR database. For more information, access X4 dataset41057.

1988GU18      At.Energ. 65, 208 (1988); Sov.At.Energy 65, 765 (1988)

A.N.Gudkov, V.M.Zhivun, A.B.Koldobsky, S.V.Krivasheev, V.G.Nesterov, N.S.Piven, E.V.Semenova, G.N.Smirenkin

Measurement of the Yield of Fission Products of ²³⁵U and ²³⁹Pu by the Method of Semiconductor Gamma Spectrometry

NUCLEAR REACTIONS ²³⁵U, ²³⁹Pu(n, F), E=3 MeV; measured fission product cumulative yields.

Data from this article have been entered in the EXFOR database. For more information, access X4 dataset41025.

1986GU20      At.Energ. 61, 379 (1986); Sov.At.Energy 61, 956 (1986)

A.N.Gudkov, A.N.Davletshin, V.M.Zhivun, V.V.Kovalenko, A.B.Koldobsky, S.V.Krivasheev, N.S.Piven, A.O.Tipunkov, S.V.Tikhonov, V.A.Tolstikov

Determination of the Radiative Capture Cross Section of ²³⁶U for Neutrons of Energies 0.96 MeV and 3.30 MeV

NUCLEAR REACTIONS ²³⁶U(n, γ), E ≈ 0.96, 3.3 MeV; measured capture σ. Activation technique.

Data from this article have been entered in the EXFOR database. For more information, access X4 dataset40886.

1985GU12      Yad.Fiz. 41, 573 (1985)

A.N.Gudkov, V.M.Zhivun, V.V.Kovalenko, A.B.Koldobski, V.M.Kolobashkin, S.V.Krivasheev, N.S.Piven, E.B.Semenova, V.A.Khristoforov

Measurement of Cumulative and Independent Yields of Products from Fission of ^242mAm Induced by Thermal Neutrons

NUCLEAR REACTIONS ^242mAm(n, F)⁸⁸Kr/⁹¹Sr/⁹²Sr/⁹²Y/¹⁰¹Mo/¹⁰¹Tc/¹⁰⁴Tc/¹⁰⁵Ru/¹⁰⁵Rh/¹²⁸Sb/¹²⁹Sb/¹³⁰Sb/¹³¹Sb/¹³²Te/¹³²I/¹³³Te/^133mTe/¹³⁴I/¹³⁴Te/¹³³I/¹³⁵I/¹³⁵Xe/¹³⁶Xe/¹³⁸Xe/¹³⁹Xe/¹³⁹Ba/¹⁴⁰Ba/¹⁴⁰La/¹⁴²La/¹⁴³Ce, E=thermal; measured residual cumulative, independent fission yields. Activation technique.

Data from this article have been entered in the EXFOR database. For more information, access X4 dataset40869.

1983GU18      At.Energ. 54, 404 (1983); Sov.At.Energy 54, 414 (1983)

A.N.Gudkov, V.M.Zhivun, A.V.Zvonarev, A.F.Zolotov, A.B.Koldobsky, Yu.F.Koleganov, V.M.Kolobashkin, S.V.Krivasheev, N.S.Piven

Determination of the Yield Figures of the Products Resulting from the ²⁴²Pu and ²⁴¹Am Fission by Fast Neutrons with the Aid of Semiconductor Spectrometry

NUCLEAR REACTIONS ²⁴²Pu, ²⁴¹Am(n, F)/⁸⁵Kr/^85mKr/⁸⁸Kr/⁹¹Sr/⁹²Sr/⁹²Y/⁹³Y/⁹⁵Zr/⁹⁷Zr/¹⁰⁵Ru/¹⁰⁴Tc/¹⁰⁵Rh/¹²⁸Sb/¹²⁹Sb/¹³⁰Sb/^130mSb/¹³¹Te/^131mTe/¹³⁴Te/¹³¹I/¹³²I/¹³³I/¹³⁴I/¹³⁵I/¹³⁵Xe/¹³⁹Ba/¹⁴⁰Ba/¹⁴⁰La/¹⁴²La/¹⁴³Ce/¹⁴³Nd/¹⁴⁹Nd, E=fast; calculated residuals yields following fission. Semi-conductor γ-spectroscopy.

Data from this article have been entered in the EXFOR database. For more information, access X4 dataset40678.

1982GO17      At.Energ. 53, 117 (1982); Sov.At.Energy 53, 576 (1982)

A.G.Golovanov, A.N.Gudkov, V.V.Kazantsev, V.V.Kovalenko, A.B.Koldobsky, V.M.Kolobashkin, S.I.Lifanov, A.I.Slyusarenko

Determination of the Cumulative Yields of Short-Lived Products of Thermal-Neutron ²³⁹Pu Fission by Means of the γ-Spectrometric Method under Cyclic Conditions

NUCLEAR REACTIONS ²³⁹Pu(n, F)⁹⁹Nb/¹⁰¹Nb/¹⁰²Nb/¹³⁶I/^136mI/¹⁰⁰Zr/¹⁴³Ba/¹⁴⁴La, E=thermal; measured residuals cumulative yield. Activation technique.

Data from this article have been entered in the EXFOR database. For more information, access X4 dataset41743.

1981GU13      At.Energ. 50, 355 (1981); Sov.At.Energy 50, 331 (1981)

A.N.Gudkov, V.M.Zhivun, V.V.Kovalenko, A.B.Koldobskii, V.M.Kolobashkin, V.N.Kosyakov, S.V.Krivasheev

Yields of Products of the Thermal-Neutron-Induced Fission of ²⁴⁹Cf Measured by Semiconductor γ Spectrometry

NUCLEAR REACTIONS, Fission ²⁴⁹Cf(n, F), E=thermal; measured absolute yields for ⁸⁹Rb, ^91,92Sr, ⁹⁴Y, ⁹⁷Zr, ⁹⁸Nb, ^99,101Mo, ^{99m,101,104,105}Tc, ¹⁰³Ru, ¹⁰⁵Rh, ¹¹²Pd, ¹¹⁵Ag, ^117mCd, ^{122,127,128m,129,130m,131}Sb, ^{132,134,135,131}I, ^{133m,133,134,131m,131,132}Tl, ^135m,135,138Xe, ^138,136,133Cs, ^{139,140,141,142}Ba, ^140,142La, ^143,146Ce, ^148,149,151Nd, ^150,151Pm, ¹⁵⁶Eu. Activation techniques.

Data from this article have been entered in the EXFOR database. For more information, access X4 dataset41729.

1980GU23      At.Energ. 48, 401 (1980); Sov.At.Energy 48, 418 (1980)

A.N.Gudkov, V.M.Zhivun, A.V.Zvonarev, V.V.Kovalenko, A.B.Koldobskii, Yu.F.Koleganov, V.M.Kolobashkin, V.G.Liforov, N.S.Piven, V.A.Tolstikov, A.O.Tipunkov

Measurement of ²³⁶U Fission Product Yields in a Fast Reactor

NUCLEAR REACTIONS, Fission ²³⁶U(n, F), E=fast; measured Eγ, Iγ; deduced cumulative yields for ^85m,87,88Kr, ^91,92,93Sr, ^92,94Y, ⁹⁷Zr, ^99,101Mo, ¹⁰⁵Ru, ^130mSb, ^{131m,132,133m,134}Te, ^{131,133,134,135}I, ^135,138Xe, ¹³⁸Cs, ^139,140,141Ba, ¹⁴²La, ¹⁴³Ce. Ge(Li) spectrometer.

Data from this article have been entered in the EXFOR database. For more information, access X4 dataset41727.