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1. Verification of neutron-induced fission product yields evaluated by a tensor decompsition model in transport-burnup simulations

   Neutron-induced fission is an important research object in basic science. Moreover, its product yield data are an indispensable nuclear data basis in...

   Qu-Fei Song, Long Zhu, ... Jun Su in Nuclear Science and Techniques

   Article 01 February 2023
   

2. Selecting Burnup Algorithms in OpenMC Using the Calculated Benchmark of LEU Assembly and MOX Fuel

   Abstract

   OpenMC is a state-of-the-art Monte Carlo neutron transport simulation code that uses the Python programming language as an API. OpenMC...

   H. A. Tanash, D. A. Solovyov, ... N. V. Schukin in Physics of Atomic Nuclei

   Article 01 December 2023
   

3. PMAXS Library Generation for the Benchmark on Rostov-2 VVER-1000 Reactor

   Abstract

   Recently, the OECD/NEA organization developed a benchmark problem based on a specific experiment conducted during the Rostov-2 first start-up...

   Mohsen Kheradmand Saadi, S. Di Pasquale, V. Giusti in Moscow University Physics Bulletin

   Article 01 April 2024
   

4. Multiphysics simulation of VVER-1200 fuel performance during normal operating conditions

   Nuclear fuel performance modeling and simulation are critical tasks for nuclear fuel design optimization and safety analysis under normal and...

   Khaled M. Yassin, Mohamed H. Hassan, ... Said A. Agamy in Nuclear Science and Techniques

   Article Open access 25 February 2023
   

5. k_eff uncertainty quantification and analysis due to nuclear data during the full lifetime burnup calculation for a small-sized prismatic high temperature gas-cooled reactor

   To benefit from recent advances in modeling and computational algorithms, as well as the availability of new covariance data, sensitivity and...

   Rong-Rui Yang, Yuan Yuan, ... Guang-Hao Liu in Nuclear Science and Techniques

   Article 18 November 2021
   

6. Time History of Performance Parameters of WWR-K Reactor during Gradual Replacement of the Water Reflector by a Beryllium One

   The water-cooled WWR-K research reactor has been operating since 2016 using low-enrichment uranium fuel. In order to maintain high levels of...

   D. S. Sairanbayev, S. N. Koltochnik, ... K. Tsuchiya in Russian Physics Journal

   Article 10 April 2021

7. Development of multi-group Monte-Carlo transport and depletion coupling calculation method and verification with metal-fueled fast reactor

   The accurate modeling of depletion, intricately tied to the solution of the neutron transport equation, is crucial for the design, analysis, and...

   Hui Guo, Yi-Wei Wu, ... Han-Yang Gu in Nuclear Science and Techniques

   Article 14 November 2023
   

8. The Development of the Combined Fission Matrix Theory in Burnup Calculation

   High accuracy and efficiency of nuclear reactor core burnup calculation are both necessary. The Monte Carlo method has been shown to have high...

   Ruishuang Gao, **ao**g Liu, Donghao He in Proceedings of the 23rd Pacific Basin Nuclear Conference, Volume 3

   Conference paper 2023
   

9. Comparative Assessment of the Range of Spectral Regulation of Reactivity Margin for Fuel Burnup in Pressurized Water Reactors Using Zirconium Displacers for Uranium and Thorium Fuel Cycles

   Abstract

   The excess reactivity in WWER-type pressurized water reactors is compensated using strong neutron absorbers. This leads to useless neutron...

   A. I. Elazaka, V. I. Savander, G. V. Tikhomirov in Physics of Atomic Nuclei

   Article 01 December 2022
   

10. Challenges and Prospects in Applying Engineering Few-Group RBMK-1000 Reactor Calculations

    Abstract

    An approach is proposed to expand the range of operational neutronic problems to be solved through combining various models of neutron...

    N. A. Grushin, I. E. Ivanov, ... N. V. Shchukin in Physics of Atomic Nuclei

    Article 01 December 2022
    

11. Neutronics Models for Integrated Testing of Transport NPP on Land-Based Prototype Testing Facilities

    An approach to providing computational support for tests of TNPPs on prototype stands using software tools for the integrated modeling of neutronics...

    V. G. Artemov, L. M. Artemova, ... A. V. Piskarev in Atomic Energy

    Article 01 June 2022

12. Comparative Analysis of Methods for Axial Profiling of the WWER-1200 Fuel Assembly Using an Example of Model Z49A2

    Abstract

    To improve the parameters of reactors and reduce the cost of generated electricity, we carry out research aimed at determining the most...

    E. A. Gerdt, R. A. Vnukov in Physics of Atomic Nuclei

    Article 01 December 2022
    

13. Investigating core axial power distribution with multi-concentration gadolinium in PWR

    Core axial power distribution is an essential topic in pressurized water reactor (PWR) reactivity control. Traditional PWRs limit stability against...

    **g-Gang Li, **g-Han Peng, ... Yun-Fan Ma in Nuclear Science and Techniques

    Article 08 November 2022
    

14. Test Results of Variance Reduction Techniques Applied to the Deep Penetration Problem

    Abstract

    Currently, there is a lack of computer power to perform high-precision reactor core analysis. In full-scale simulation of nuclear reactor...

    E. V. Bogdanova, G. V. Tikhomirov in Physics of Atomic Nuclei

    Article 01 December 2022
    

15. A Monte Carlo Code Developed for Radiation Shielding Calculations Based on RMC

    In this paper, a new developed Monte Carlo method code, intended to be used in shielding calculations, will be introduced. This code was developed on...

    Dongchuan Ying, Huanwen Lyu, ... Feng **ao in Proceedings of the 23rd Pacific Basin Nuclear Conference, Volume 3

    Conference paper 2023
    

16. A Monte Carlo method for quantitatively calculating the neutron sensitivity of rhodium self-powered neutron detectors in reactors

    Purpose

    Self-powered neutron detectors (SPNDs) with rhodium emitters exhibit high thermal neutron sensitivity and extensively equipped in nuclear...

    **ong Wu, Jieqiong Jiang, ... Shijie Luo in Radiation Detection Technology and Methods

    Article 11 December 2023
    

17. Conceptual design and neutronic analysis of a megawatt-level vehicular microreactor based on TRISO fuel particles and S-CO₂ direct power generation

    With global warming, the demand for diversified energy sources has increased significantly. Transportable microreactors are important potential...

    Fang-Yuan Zhang, Gui-Feng Zhu, ... Hong-Jie Xu in Nuclear Science and Techniques

    Article 01 June 2022
    

18. Simulation of a Transient Process in VVER-1200 by Means of the Athlet/BIPR-VVER Coupled Neutronics and Thermohydraulic Code

    The results of a simulation, performed using the code ATHLET/BIPR-VVER (Russia, Germany), of tests on connecting a single main circulation pump (MCP)...

    A. V. Baikov, A. A. Dubov, ... B. E. Shumskii in Atomic Energy

    Article 30 January 2020

19. SP3-coupled global variance reduction method based on RMC code

    A global variance reduction (GVR) method based on the SPN method is proposed. First, the global multi-group cross-sections are obtained by Monte...

    Qing-Quan Pan, Teng-Fei Zhang, ... Kan Wang in Nuclear Science and Techniques

    Article 16 November 2021
    

20. RTM-2 Software Package for Life Cycle Modeling of Fast Reactors in Closed NFC

    A complex of nuclear fuel cycle technologies based on fast reactors operating in a closed NFC is under development as part of the of the Proryv...

    A. V. Egorov, E. A. Rodina, ... Yu. G. Syrtsova in Atomic Energy

    Article 01 April 2022