Neutronic analysis of the PBMR-400 full core using thorium fuel mixed with plutonium or minor actinides

被引:22
|
作者
Acir, Adem [1 ]
Coskun, Hasan [2 ]
机构
[1] Gazi Univ, Fac Technol, Dept Energy Syst Engn, Ankara, Turkey
[2] Gazi Univ, Inst Sci & Technol, Ankara, Turkey
关键词
Monte Carlo; MONTEBURNS; ORIGEN2; Thorium; Reactor grade plutonium; Minor actinides; TRANSMUTATION; REACTOR; INCINERATION; CRITICALITY;
D O I
10.1016/j.anucene.2012.05.015
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
Time evolution of criticality and burnup grades of the PBMR were investigated for reactor grade plutonium and minor actinides in the spent fuel of light water reactors (LWRs) mixed with thoria. The calculations were performed by employing the computer codes MCNP and MONTEBURNS 2.0 and using the ENDF/B-V nuclear data library. Firstly, the plutonium-thorium and minor actinides-thorium ratio was determined by using the initial k(eff) value of the original uranium fuel design. After the selection of the plutonium/minor actinides-thorium mixture ratio, the time-dependent neutronic behavior of the reactor grade plutonium and minor actinides and original fuels in a PBMR-400 reactor was calculated by using the MCNP code. Finally, k(eff), burnup and operation time values of the fuels were compared. The core effective multiplication factor (k(eff)) for the original fuel which has 9.6 wt.% enriched uranium was computed as 1.2395. Corresponding to this k(eff) value the reactor grade plutonium/thorium and minor actinide/thorium oxide mixtures were found to be 30%/70% and 50%/50%, respectively. The core lives for the original, the reactor grade plutonium/thorium and the minor actinide/thorium fuels were calculated as similar to 3.2, similar to 6.5 and similar to 5.5 years, whereas, the corresponding burnups came out to be 99,000, similar to 190,000 and similar to 166,000 MWD/T, respectively, for an end of life k(eff) set equal to 1.02. (C) 2012 Elsevier Ltd. All rights reserved.
引用
下载
收藏
页码:45 / 50
页数:6
相关论文
共 32 条
  • [21] Neutronic assessment of a PWR-type SMR core with TRISO particles using mixed-oxide fuel strategies
    Rosales, Jesus
    Francois, Juan-Luis
    Garcia, Carlos
    PROGRESS IN NUCLEAR ENERGY, 2022, 154
  • [22] Explore the possible advantages of using thorium-based fuel in a pressurized water reactor (PWR) Part 1: Neutronic analysis
    Galahom, A. Abdelghafar
    Mohsen, Mohamed Y. M.
    Amrani, Naima
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2022, 54 (01) : 1 - 10
  • [23] Plutonium and Minor Actinides incineration options using innovative Na-cooled fast reactors: Impacting on phasing-out and on-going fuel cycles
    Vezzoni, Barbara
    Gabrielli, Fabrizio
    Rineiski, Andrei
    Schwenk-Ferrero, Aleksandra
    Romanello, Vincenzo
    Maschek, Werner
    Fazio, Concetta
    Salvatores, Massimo
    PROGRESS IN NUCLEAR ENERGY, 2015, 82 : 58 - 63
  • [24] Neutronic Analysis of Accident-Tolerant Cladding Materials in 3D Full Core BEAVRS PWR Benchmark Using OpenMC Code
    Alamri, Khalid A.
    Alqahtani, Meshari M.
    Alomari, Abdullah S.
    Almarshad, Abdullah I.
    INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2024, 2024
  • [25] Evaluation of nanofluid coolant effects on VVER-1000/V-446 reactor using 3-D full core coupled neutronic and thermohydraulics analysis
    Saadati, Hassan
    Hadad, Kamal
    Rabiee, Ataollah
    Kamalinia, Amir Hossein
    ANNALS OF NUCLEAR ENERGY, 2021, 152
  • [26] Analysis of Th and U in thorium-based mixed-oxide fuel using wavelength dispersive X-ray fluorescence spectrometer
    A. Pandey
    S. Dhara
    F. A. Khan
    A. Kelkar
    Pradeep Kumar
    R. B. Bhatt
    P. G. Behere
    Journal of Radioanalytical and Nuclear Chemistry, 2019, 319 : 775 - 781
  • [27] Analysis of Th and U in thorium-based mixed-oxide fuel using wavelength dispersive X-ray fluorescence spectrometer
    Pandey, A.
    Dhara, S.
    Khan, F. A.
    Kelkar, A.
    Kumar, Pradeep
    Bhatt, R. B.
    Behere, P. G.
    JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY, 2019, 319 (03) : 775 - 781
  • [28] Evaluation of nanofluid coolant effects on VVER-1000/V-446 reactor using 3-D full core coupled neutronic and thermohydraulics analysis
    Saadati, Hassan
    Hadad, Kamal
    Rabiee, Ataollah
    Hossein Kamalinia, Amir
    Annals of Nuclear Energy, 2021, 152
  • [29] Analysis of accidents at the Pakistan Research Reactor-1 using proposed mixed-fuel (HEU and LEU) core
    Bokhari, IH
    NUCLEAR TECHNOLOGY, 2004, 148 (03) : 369 - 376
  • [30] Criticality analysis of pyrochemical reprocessing apparatuses for mixed uranium-plutonium nitride spent nuclear fuel using the MCU-FR and MCNP program codes
    Kizub, P. A.
    Blokhin, A. I.
    Blokhin, P. A.
    Mitenkova, E. F.
    Mosunova, N. A.
    Kovrov, V. A.
    Shishkin, A. V.
    Zaikov, Yu. P.
    Rakhmanova, O. R.
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2023, 55 (03) : 1097 - 1104