Fuel burnup analysis of the TRIGA Mark II reactor at the University of Pavia

被引:17
|
作者
Chiesa, Davide [1 ,2 ]
Clemenza, Massimiliano [1 ,2 ]
Pozzi, Stefano [1 ,2 ]
Previtali, Ezio [1 ,2 ]
Sisti, Monica [1 ,2 ]
Alloni, Daniele [3 ,4 ]
Magrotti, Giovanni [3 ,4 ]
Manera, Sergio [3 ,4 ]
Prata, Michele [3 ,4 ]
Salvini, Andrea [3 ,4 ]
Cammi, Antonio [2 ,5 ]
Zanetti, Matteo [5 ]
Sartori, Alberto [6 ]
机构
[1] Milano Bicocca Univ, Phys Dept G Occhialini, Piazza Sci 3, I-20126 Milan, Italy
[2] Ist Nazl Fis Nucl, Sect Milano Bicocca, Piazza Sci 3, I-20126 Milan, Italy
[3] Univ Pavia, LENA, Via Aselli 41, I-27100 Pavia, Italy
[4] Ist Nazl Fis Nucl, Sect Pavia, Via A Bassi 6, I-27100 Pavia, Italy
[5] Politecn Milan, Dept Energy, CeSNEF Enrico Fermi Ctr Nucl Studies, Via La Masa34, I-20156 Milan, Italy
[6] Scuola Int Super Studi Avanzati, SISSA MathLab, Via Bonomea 265, I-34136 Trieste, Italy
关键词
Fuel burnup; TRIGA Mark II reactor; MCNP5; simulations; Core reconfiguration; Benchmark analysis; CARLO CODE MCNP; SIMULATION; POWER;
D O I
10.1016/j.anucene.2016.06.008
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
A time evolution model was developed to study fuel burnup for the TRIGA Mark II reactor at the University of Pavia. The results were used to predict the effects of a complete core reconfiguration and the accuracy of this prediction was tested experimentally. We used the Monte Carlo code MCNP5 to reproduce system neutronics in different operating conditions and to analyze neutron fluxes in the reactor core. The software that took care of time evolution, completely designed in-house, used the neutron fluxes obtained by MCNP5 to evaluate fuel consumption. This software was developed specifically to keep into account some features that differentiate low power experimental reactors from those used for power production, such as the daily ON/OFF cycle and the long fuel lifetime. These effects can not be neglected to properly account for neutron poison accumulation. We evaluated the effect of 48 years of reactor operation and predicted a possible new configuration for the reactor core: the objective was to remove some of the fuel elements from the core and to obtain a substantial increase in the Core Excess reactivity value. The evaluation of fuel burnup and the reconfiguration results are presented in this paper. (C) 2016 Elsevier Ltd. All rights reserved.
引用
收藏
页码:270 / 276
页数:7
相关论文
共 50 条
  • [31] Safety assessment and management of spent nuclear fuel for TRIGA mark II research reactor
    Heritier, Beya
    Mahmoud, Rowayda F.
    El Saghir, Ahmed
    Shaat, Mohamed K.
    Badawi, Alya
    [J]. KERNTECHNIK, 2022, 87 (05) : 615 - 624
  • [32] Accident scenarios of the TRIGA Mark II reactor in Vienna
    Villa, Mario
    Haydn, Markus
    Steinhauser, Georg
    Boeck, Helmuth
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2010, 240 (12) : 4091 - 4095
  • [33] Design and Safety of the PGNAA Facility at the TRIGA Research Reactor of the University of Pavia - Lena
    Salvini, Andrea
    Alloni, Daniele
    Clemenza, Massimiliano
    [J]. 28TH INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE (NENE 2019), 2019,
  • [34] Thermal Power Calibration of the TRIGA Mark II Reactor
    Stancar, Ziga
    Snoj, Luka
    [J]. 23RD INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE, (NENE 2014), 2014,
  • [35] Fuel element burnup determination in mixed TRIGA core using reactor calculations
    Ravnik, M
    Zagar, T
    Persic, A
    [J]. NUCLEAR TECHNOLOGY, 1999, 128 (01) : 35 - 45
  • [36] Temperature Feedback of TRIGA MARK-II Fuel
    Usang, M. D.
    Minhat, M. S.
    Rabir, M. H.
    Rawi, M. M. Z.
    [J]. INTERNATIONAL NUCLEAR SCIENCE, TECHNOLOGY AND ENGINEERING CONFERENCE 2015 (INUSTEC2015), 2016, 1704
  • [37] Fuel element burnup determination in mixed TRIGA core using reactor calculations
    Institute Jožef Stefan, Jamova 39, 1000 Ljubljana, Slovenia
    [J]. Nucl Technol, 1 (35-45):
  • [38] Analysis of a Void Reactivity Coefficient of the JS']JSI TRIGA Mark II Reactor
    Jazbec, Anze
    Snoj, Luka
    Kavsek, Darko
    [J]. 22ND INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE, (NENE 2013), 2013,
  • [39] Investigation, design and analysis of a fast neutron facility on beam port 4 at the University of Texas MARK II TRIGA Reactor
    S. M. Whitney
    E. Alvarez
    D. Haas
    K. Jackman
    S. Wilson
    S. Biegalski
    [J]. Journal of Radioanalytical and Nuclear Chemistry, 2008, 276 : 857 - 861
  • [40] Investigation, design and analysis of a fast neutron facility on beam port 4 at the University of Texas MARK II TRIGA Reactor
    Whitney, S. M.
    Alvarez, E.
    Haas, D.
    Jackman, K.
    Wilson, S.
    Biegalski, S.
    [J]. JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY, 2008, 276 (03) : 857 - 861