Dina Chernikova

The Inclusion of Photofission, Photonuclear, (n, xn), (n, n ' x gamma), and (n, x gamma) Reactions in the Neutron-Gamma Feynman-Alpha Variance-to-Mean Formalism

A potential alternative/complement to the traditional thermal neutron based counting in Nuclear Safeguards and Security

The effect of capture gammas, photofission and photonuclear neutrons to the neutron-gamma Feynman variance-to-mean ratios (neutron, gamma and total)

Novel passive and active tungsten-based identifiers for maintaining the continuity of knowledge of spent nuclear fuel copper canisters

The neutron-gamma Feynman variance to mean approach: Gamma detection and total neutron-gamma detection (theory and practice)

Characterization of strong 241Am sources

Characterization of strong 241Am sources

Experimental and numerical investigations of radiation characteristics of Russian portable/compact pulsed neutron generators: ING-031 ING-07, ING-06 and ING-10-20-120

A unique tungsten-based tagging approach for maintaining of continuity of knowledge of nuclear waste copper canisters

A method for discrimination of neutron and gamma pile-up events in scintillation detectors with a simultaneous identification of malfunctioning ones

A new concept for safeguarding and labeling of long-term stored waste and its place in the scope of existing tagging techniques

A general analytical solution for the variance-to-mean Feynman-alpha formulas for a two-group two-point, a two-group one-point and a one-group two-point cases

Passive and Active Ways of Unique Tagging/Labeling of Long-term Stored Nuclear Waste Copper Canisters

2013

Pulse shape discrimination of neutrons and gamma rays using Kohonen artificial neural networks

Application of the two-group - one-region and two-region - one-group Feynman-alpha formulas in safeguards and accelerator-driven system (ADS)

A method for nondestructive assay of nuclear materials in facilities with a pulse neutron generator and a digital technology for discrimination between neutrons and photons

Sensitivity of the neutronic design of an Accelerator-Driven System (ADS) to the anisotropy of yield of the neutron generator and variation of nuclear data libraries

A Comparison of Artificial Neural Network Performance: the Case of Neutron/Gamma Pulse Shape Discrimination

Derivation of two-group two-region Feynman-alpha formulas and their application to Safeguards and accelerator-driven system (ADS)

Monitoring fissile and matrix materials in closed containers by means of pulsed neutron sources

A direct method for evaluating the concentration of boric acid in a fuel pool using scintillation detectors for joint-multiplicity measurements

Testing a direct method for evaluating the concentration of boron in a fuel pool using scintillation detectors, and a 252Cf and an 241Am-Be source

Testing of small detectors with glass rod light guides for multiplicity measurement purposes

Sensitivity of nonstationary neutron spectra in lead to nuclear data variations

Two-point theory for the differential self-interrogation Feynman-alpha method

Derivation and quantitative analysis of the differential self-interrogation Feynman-alpha method

Development of the Neutron-Gamma-Neutron (NGN) approach for the fresh and spent fuel assay

Analysis of 235U, 239Pu and 241Pu content in a spent fuel assembly using Lead Slowing Down Spectrometer and time intervals matrix

Time intervals matrix analysis of 235U and 239Pu content in a spent fuel assembly using Lead Slowing down Spectrometer

2011

Derivation and quantitative analysis of the differential self-interrogation Feynman-alpha method