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Showing 1-20 of 1,350 results
  1. Study on the Influence of Stretch-Out Operation on the Deposition of Corrosion Products and Source Term Level in the Primary Circuit of Pressurized Water Reactor

    Corrosion products in the primary circuit of Pressurized Water Reactor (PWR) during operation will cause Chalk Rivers Unidentified Deposit (CRUD),...
    Conference paper Open access 2023
  2. Technological Upgrading Analysis on Diversity Transformation of Reactor Protection System in a Fast Reactor Project

    There are three reactivity control methods in pressurized water reactor, including control rod, combustible poison, chemical compensation. Due to the...
    Liu **ngQing, Zhang HaiBin, ... Chen DeLin in Proceedings of the 23rd Pacific Basin Nuclear Conference, Volume 3
    Conference paper 2023
  3. Ensuring the possibility of using thorium as a fuel in a pressurized water reactor (PWR)

    The possibility of utilizing thorium as a fuel in a pressurized water reactor (PWR) has been proven from the neutronic perspective in our previously...

    Mohamed Y. M. Mohsen, Mohamed A. E. Abdel-Rahman, A. Abdelghafar Galahom in Nuclear Science and Techniques
    Article 10 December 2021
  4. Theoretical analysis of long-lived radioactive waste in pressurized water reactor

    Background

    The accelerator-driven subcritical transmutation system (ADS) is an advanced technology for the harmless disposal of nuclear waste. A...

    Ze-**n Fang, Meng Yu, ... Long Zhu in Nuclear Science and Techniques
    Article 14 July 2021
  5. 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
  6. Verification and Validation of a Thermohydraulics-Neutronics Software Package for Calculating Transient Regimes in Heavy-Water Reactor Installations

    A software package was developed for coupled thermohydraulic and three-dimensional neutronics calculations of a core in transient regimes of...

    A. V. Davydov, R. V. Kozlov, ... M. G. Shkokov in Atomic Energy
    Article 01 October 2022
  7. Double-Ended Shear Fracture Accident of Short Casing Inner Tube in Small Modular Reactor

    The double-ended shear fracture accident is one of the key accidents that determines the operating power and affects the safety margin of nuclear...
    Conference paper 2023
  8. Review on synergistic damage effect of irradiation and corrosion on reactor structural alloys

    The synergistic damage effect of irradiation and corrosion of reactor structural materials has been a prominent research focus. This paper provides a...

    Hui Liu, Guan-Hong Lei, He-Fei Huang in Nuclear Science and Techniques
    Article Open access 01 March 2024
  9. Research on the Alarm Threshold for Steam Generator Tube Leak Monitoring of Small Modular Reactor

    On the basis of fully learning from the existing principles of leak monitoring alarm thresholds setting of the steam generator tube in pressurized...
    Ming-ming **a, Jun-long Wang, ... **n Chen in Proceedings of the 23rd Pacific Basin Nuclear Conference, Volume 1
    Conference paper Open access 2023
  10. Reactor Theory

    Nuclear reactor, or simply the reactor, is able to maintain a controlled, self-sustaining nuclear fission chain reaction in order to achieve the use...
    Chapter 2022
  11. Reactor Nuclear Measurements and Radiation Monitoring

    Reactor operation monitoring consists of three parts: power (neutron flux) monitoring, radiation monitoring, and monitoring of thermal parameters.
    Chapter 2023
  12. Research on Public Communication of Small Reactor

    Based on the conclusions of small reactor environmental impact assessment and social stability risk assessment of small reactors, this paper conducts...
    Conference paper Open access 2023
  13. Scientific and technical aspects of develo** a RITM-200N innovative reactor for SNPPs

    The RITM-200N reactor represents a modification of a RITM-200 icebreaker reactor, which is designed on the basis of proven ship reactor construction...

    V. V. Petrunin, N. V. Sheshina, ... A. A. Bezrukov in Atomic Energy
    Article 01 May 2023
  14. Techno-Economic Prognosis for the Manufacture of Fuel Assemblies with Mixed Uranium-Plutonium Fuel for the VVER-SKD Power Reactor

    Techno-economic prognostications for the manufacture of fuel assemblies with mixed uranium-plutonium fuel for the VVER-SKD power reactor, which is...

    M. V. Kormilitsyn, L. A. Kormilitsyna, ... T. D. Shchepetina in Atomic Energy
    Article 01 July 2022
  15. Maintaining and Improving the Accuracy of Feed-Water Flow Measurement and Thermal Power Determination in NPP Reactor Units

    An analysis of the error of the feed-water flow rate measured in NPP reactor units with the help of regular flow meters based on restrictive devices...

    A. S. Timonin, S. N. Eshchenko, ... V. M. Gurevich in Atomic Energy
    Article 01 July 2022
  16. 600-MWe high-temperature gas-cooled reactor nuclear power plant HTR-PM600

    The HTR-PM600 high-temperature gas-cooled reactor nuclear power plant is based on the technology of the high-temperature gas-cooled reactor...

    Zuo-Yi Zhang, Yu-Jie Dong, ... Hai-Tao Wang in Nuclear Science and Techniques
    Article Open access 16 August 2022
  17. Preliminary Study on Improving the Automation Level of Large Commercial Pressurized Water Reactor

    Digital instrumentation and control (I&C) system has been widely applied on large commercial pressurized water reactors (PWR), which brings...
    Conference paper 2021
  18. Research on Nuclear Seawater Desalination Technology Based on Small Modular Reactor ACP100

    Seawater desalination technology is an important way to solve the shortage of fresh water resources. The combination of nuclear technology and...
    Conference paper 2023
  19. Alara Methodology for Reactor Building Shielding Design in HPR1000 PWR

    The reactor building is the area with highest radiation risk in nuclear power plant (NPP) and a systematic shielding design optimization procedure is...
    Guanghao Zeng, Yonghai Zhou, ... Weifeng Lv in Proceedings of the 23rd Pacific Basin Nuclear Conference, Volume 3
    Conference paper 2023
  20. Conceptual design and safety characteristics of a new multi-mission high flux research reactor

    Research reactors with neutron fluxes higher than 10 14 n cm −2 s −1 are widely used in nuclear fuel and material irradiation, neutron-based scientific...

    Wei Xu, Jian Li, ... Lei Shi in Nuclear Science and Techniques
    Article 16 March 2023