Search Results - "Ivanov, K. N."

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  1. 1

    Advances in the Pennsylvania State University NEM code by Thompson, S.A., Ivanov, K.N.

    Published in Annals of nuclear energy (01-08-2016)
    “…•SP3 – approximation, which updates the code with some transport capabilities.•Semi-analytical nodal expansion developments with the application of polynomial…”
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    Journal Article
  2. 2

    Development of an iterative diffusion-transport method based on MICROX-2 cross section libraries by Hou, J., Choi, H., Ivanov, K.N.

    Published in Annals of nuclear energy (01-03-2015)
    “…•Innovative Iterative Diffusion Transport (IDT) method is developed.•A 2-dimensional (2-D) pin-by-pin lattice program, NEMA, is also developed.•The developed…”
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  3. 3

    Signal Processing of Distributed Optoacoustic Sensors by Means of Neural Networks in the Automotive Transport Monitoring Problem by Nazarenko, P. A., Levashkin, S.P., Zakharova, O. I., Ivanov, K. N., Kushukov, S. V.

    “…Artificial neural network (ANN) models are used as a tool for an automotive transport monitoring. The solution of the problem of recognition of distributed…”
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  4. 4

    Investigation of spatial coupling aspects for coupled code application in PWR safety analysis by Todorova, Nadejda K, Ivanov, Kostadin N

    Published in Annals of nuclear energy (2003)
    “…The simulation of nuclear power plant accident conditions requires three-dimensional (3-D) modeling of the reactor core to ensure a realistic description of…”
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  5. 5

    Self-shielding models of MICROX-2 code: Review and updates by Hou, J., Choi, H., Ivanov, K.N.

    Published in Annals of nuclear energy (01-02-2014)
    “…•The MICROX-2 code has been improved to expand its application to advanced reactors.•New fine-group cross section libraries based on ENDF/B-VII have been…”
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  6. 6

    Temporal adaptive algorithm for TRAC-BF1/NEM/COBRA-TF coupled calculations in BWR safety analysis by Solı́s, Jorge, Avramova, Maria N, Ivanov, Kostadin N

    Published in Annals of nuclear energy (01-12-2002)
    “…A temporal adaptive algorithm was developed to perform the synchronization and optimization of the performance of TRAC-BF1/NEM/COBRA-TF three-dimensional…”
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  7. 7

    Improved verification methodology for TRAC-PF1/NEM using NEA/OECD core transient benchmarks by Ziabletsev, Dmitri N., Ivanov, Kostadin N.

    Published in Annals of nuclear energy (01-09-2000)
    “…This paper describes the verification methodology of TRAC-PF1/NEM based on the NEA/OECD core transient benchmarks. The necessity of verification of the coupled…”
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  8. 8

    Modeling the dynamics of the retentivity process of journals among the most authoritative scientific serials by Libkind, A. N., Markusova, V. A., Libkind, I. A., Jansz, M., Ivanov, K. N.

    “…The article examines the process of journal retention over time as the most authoritative sources of scientific papers. Formal concepts of retentivity are…”
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    New genetic algorithms (GA) to optimize PWR reactors by Alim, Fatih, Ivanov, Kostadin N., Yilmaz, Serkan, Levine, Samuel H.

    Published in Annals of nuclear energy (2008)
    “…In this paper, the GARCO–PSU (Genetic Algorithm Reactor Code Optimization–Pennsylvania State University) code simultaneously optimizes the core loading pattern…”
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  12. 12

    Improved cross-section modeling methodology for coupled three-dimensional transient simulations by Watson, Justin K., Ivanov, Kostadin N.

    Published in Annals of nuclear energy (01-05-2002)
    “…The purpose of this paper is to introduce a more accurate and sophisticated methodology for use in three-dimensional coupled neutronic/thermal hydraulic…”
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  13. 13

    Helios, current coupling collision probability method, applied for solving the NEA C5G7 MOX benchmark by Ivanov, Boyan D., Ivanov, Kostadin N., Stamm'ler, Rudi J.J.

    “…As part of an effort to test the ability of current transport codes to treat reactor core problems without spatial homogenization, the lattice code HELIOS was…”
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  14. 14

    Minimizing the gamma radiation effects to spent fuel pool walls by Tippayakul, Chanatip, Levine, Samuel, Ivanov, Kostadin N., Mahgerefteh, Moussa

    Published in Annals of nuclear energy (01-03-2004)
    “…This paper presents the study of the gamma exposure to the spent fuel pool walls from spent fuel assemblies. The Monte Carlo code, MCNP4C, was used to model…”
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  15. 15

    Age-related immunological characteristics in typhoid fever and their significance in the clinical manifestations of the disease by Postovit, V A, Ivanov, K N

    “…The results of the comparison of the pattern of specific typhoid exanthema, as well as the time of its appearance, in elderly and senile patients and in young…”
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  16. 16

    Nodal kinetics model upgrade in the Penn State coupled TRAC/NEM codes by Beam, Tara M., Ivanov, Kostadin N., Baratta, Anthony J., Finnemann, Herbert

    Published in Annals of nuclear energy (01-09-1999)
    “…The Pennsylvania State University currently maintains and does development and verification work for its own versions of the coupled three-dimensional…”
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  17. 17

    HELIOS: analysis of MOX critical experiments by Kriangchaiporn, Nateekool, Ivanov, Kostadin N., Stamm’ler, Rudi J.J.

    Published in Annals of nuclear energy (01-09-2002)
    “…Thirty UO 2–PuO 2 fueled light-water moderated lattice critical experiments have been analyzed with HELIOS at the Nuclear Engineering Program of the…”
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  18. 18

    Work Hardening of Steel with a Bainite Structure by V. E. Gromov, E. N. Nikitina, Yu. F. Ivanov, K. V. Aksyonova, E. V. Kornet

    Published in Uspehi fiziki metallov (Online) (01-12-2015)
    “…The analysis of constructional steel 30Cr2Ni2MoV (in mass %: C — 0.3; Cr ≤ 2; Ni ≤ 2; Mo ≤ 1; V ≤ 1, Fe — the rest) under compression up to fracture after air…”
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  19. 19

    Developing and modeling of the “Laguna Verde” BWR CRDA benchmark by Solís-Rodarte, Jorge, Fu, Haoying, Ivanov, Kostadin N., Matsui, Yusuke, Hotta, Akitoshi

    Published in Annals of nuclear energy (01-03-2002)
    “…Reactivity initiated accidents (RIA) and design basis transients are one of the most important aspects related to nuclear power reactor safety. These events…”
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  20. 20

    Features and performance of a coupled three-dimensional thermal-hydraulic/kinetics TRAC-PF1/NEM pressurized water reactor (PWR) analysis code by Ivanov, Kostadin N., Macian-Juan, Rafael, Irani, Adi, Baratta, Anthony J.

    Published in Annals of nuclear energy (1999)
    “…This paper summarizes the current status of the Pennsylvania State University (PSU) version of the coupled three-dimensional (3-D) thermal-hydraulic/kinetics…”
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