Journal of Nuclear Science, Engineering and Technology (JONSAT)
In cooperation with the Iranian Nuclear Society

Study of the VVER1000 reactor core fuel assemblies reaction to mass flux changes, caused by lose of coolant accident, by means of the sound effect

Document Type : Research Paper

Authors

S Heidari
M Rahgoshay
N Vosoughi
M Athari
https://doi.org/10.24200/nst.2019.993
Abstract
The article aims in the studying of thermal-hydraulic simulation of the VVER-1000 reactor core fuel assemblies’ reaction to the mass flux changes which are caused by the lose of coolant accident and its sudden pressure drop. The analysis of mentioned accident is performed in concise periods (mili second) by the use of the sound effect. Time-related thermal-hydraulic equations were analyzed by the method of a compressible fluid in a single heated channel and were evaluated by the results of the mentioned transient, in a PWR reactor. The mentioned transient was simulated in RELAP5 code and results were compared to the previous ones. Then, 28 reactor fuel assemblies were studied, considering the 1/6 symmetry of VVER-1000 reactor and unique features of every assembly. Mass flux drop was happened the end of the channel, after a few seconds. It was observed that mass flux is at dependent on the role of every assembly in the production of core heat power. The acoustic effect reveals some of the perturbations in mass flux changes, considering every fuel assembly features.

Highlights

 

  1. P.K. Chan, IEEE Transaction on Computer Aided Design, 10, 8,  1078–1079 (1991).

  2. C.K. Ooi, K.N. Seetharamu, Z.A.Z. Alauddin, G.A. Quadir, K.S. Sim, T.J. Goh, Fast transient solutions for heat transfer, 2003, in Proceedings of the Conference on Convergent Technologies for the Asia-Pacific Region (IEEE TENCON ’03), 1, 469–473 (2003).

  3. P. Liu, H. Li, L. Jin, W. Wu, S.X.D. Tan, J. Yang, IEEE Transactions on Computer-Aided Design of Integrated Circuits and Systems, 25, 12, 2882–2892 (2006).

  4. K.N. Proskuryakov, Recent Adv Petrochem Sci, Volume 2 Issue 1 (2017).

  5. N.E. Todreas, M.S. Kazimi, Nuclear systems II: Elements of thermal hydraulic design (Vol. 2). Taylor & Francis (1990).

  6. G. Forti, E. Vincenti, The codes costanza for the dynamics of liquid cooled nuclear reactor,  joint nuclear research center Ispra stablishment-Italy, reactor physics department reactor teory and analysis (1967).

  7. M. Hosseini, H. Khalafi, S. Khakshournia, Progress in Nuclear Energy, 85, 108-120 (2015).

  8. J.C.M. Leung, K.A. Gallivan, R.E. Henry, Critical Heat Flux Predictions During Blow down Transient, Argonne National Laboratory, Argonne, IL60439, U.S.A (1981).

  9. AEOI, Reactor Final Safety Analysis Report VVER-1000 Bushehr, Chapter 4, Atomic Energy Organization of Iran (2005).

  10. W. Wagner, H.J. Kretzschmar, International Steam Tables, Second edition, Faculty of Mechanical Engineering Chair of Thermo-dynamics (2007).

  11. RELAP5/SCDAP//MOD3.2 Code Manuals, A Computer Code for Best-Estimate Transient Simulation of Light Water Reactor Coolant Systems During Severe Accidents, Prepared for the U.S. 1997, Nuclear Regulatory Commission, Idaho National Engineering and Environmental Laboratory, NUREG/CR-6150.

Keywords

Fuel assembly
VVER-1000
Mass flux
Sound effect

  1.  

    1. P.K. Chan, IEEE Transaction on Computer Aided Design, 10, 8,  1078–1079 (1991).

    2. C.K. Ooi, K.N. Seetharamu, Z.A.Z. Alauddin, G.A. Quadir, K.S. Sim, T.J. Goh, Fast transient solutions for heat transfer, 2003, in Proceedings of the Conference on Convergent Technologies for the Asia-Pacific Region (IEEE TENCON ’03), 1, 469–473 (2003).

    3. P. Liu, H. Li, L. Jin, W. Wu, S.X.D. Tan, J. Yang, IEEE Transactions on Computer-Aided Design of Integrated Circuits and Systems, 25, 12, 2882–2892 (2006).

    4. K.N. Proskuryakov, Recent Adv Petrochem Sci, Volume 2 Issue 1 (2017).

    5. N.E. Todreas, M.S. Kazimi, Nuclear systems II: Elements of thermal hydraulic design (Vol. 2). Taylor & Francis (1990).

    6. G. Forti, E. Vincenti, The codes costanza for the dynamics of liquid cooled nuclear reactor,  joint nuclear research center Ispra stablishment-Italy, reactor physics department reactor teory and analysis (1967).

    7. M. Hosseini, H. Khalafi, S. Khakshournia, Progress in Nuclear Energy, 85, 108-120 (2015).

    8. J.C.M. Leung, K.A. Gallivan, R.E. Henry, Critical Heat Flux Predictions During Blow down Transient, Argonne National Laboratory, Argonne, IL60439, U.S.A (1981).

    9. AEOI, Reactor Final Safety Analysis Report VVER-1000 Bushehr, Chapter 4, Atomic Energy Organization of Iran (2005).

    10. W. Wagner, H.J. Kretzschmar, International Steam Tables, Second edition, Faculty of Mechanical Engineering Chair of Thermo-dynamics (2007).

    11. RELAP5/SCDAP//MOD3.2 Code Manuals, A Computer Code for Best-Estimate Transient Simulation of Light Water Reactor Coolant Systems During Severe Accidents, Prepared for the U.S. 1997, Nuclear Regulatory Commission, Idaho National Engineering and Environmental Laboratory, NUREG/CR-6150.

Home