مدل‌سازی اندازه‌گیری قدرت راکتور VVER-1000 با تابش نوترون و گاما با استفاده از کد مونت‌کارلو

نویسندگان

1 گروه فیزیک، دانشگاه پیام نور واحد تهران، تهران

2 پژوهشکده راکتور، پژوهشگاه علوم و فنون هسته‌ای، سازمان انرژی اتمی ایران، تهران

چکیده

در این پژوهش می‌کوشیم تا روش جدیدی را برای اندازه‌گیری توان راکتور قدرت به‌کار گیریم. در این روش از پرتو گاما و نوترون حاصل از کل ساختار راکتور استفاده می‌شود، بی آن‌که در ساختارش تغییری داده شود. این روش می‌تواند توان راکتور را بی‌درنگ اندازه‌گیری و به‌طور لحظه‌ای گزارش کند. برای به‌دست آوردن رابطه‌ی بین قدرت راکتور و میزان تابش نشتی نوترون و گاما به وسیله‌ی شبیه‌سازی، با استفاده از کد مونت‌کارلو MCNP5 مقادیر تالی F5 را در فواصل مختلف از دیواره‌ی راکتور به‌دست آورده و نمودار آن را رسم می‌کنیم تا نحوه‌ی تغییرات را مشاهده نماییم. با دور شدن از راکتور میزان تابش و هم انرژی ذرات تابشی افت می‌نماید تا جایی‌که در فاصله‌ی چهار متری از بدنه، تابش نشتی نوترون با عنایت به عایق‌بندی خوب آن به صفر می‌رسد و این عدد برای تابش گاما فقط حدود 5/2 متر است. با تعیین نقطه دامنه کاهش تابش نشتی به تابش زمینه و رابطه خطی قدرت و شار نشتی در این نقطه می‌توان در هر لحظه برای راکتور با اندازه‌گیری شار در نقطه مورد نظر توان را محاسبه نمود.

کلیدواژه‌ها

عنوان مقاله [English]

Modeling the measurement of VVER-1000 reactor power by neutron and gamma radiation with MCNP code

نویسندگان [English]

  • Majid Tawanpour 1
  • Majid Jalali Hajiabadi 2
  • Mohammad Reza Jalali Nodoushan 1
1
2
چکیده [English]

The present study deals with a new method for measuring the power of a reactor. This method uses gamma and neutron radiation resulted from the entire reactor structure, without changing its structure (online). In terms of functionality, this method can measure the reactor power in real-time and report it instantly. In order to obtain the relationship between reactor power and gamma and neutron leakage radiation by simulation, the values of the F5 tally are calculated at different distances from the reactor wall, using the MCNP5 code (Monte Carlo N-Particles). Then, we plot the diagram to observe the variation trend. However, an increase in the distance from the reactor reduces both the amount of radiation and the energy of the radiation particles until the neutron leakage radiation reaches zero within five meters of the body, due to its good insulation. However, this number is only about four meters for gamma irradiation. The reactor power can be calculated by measuring the flux at the given point and any time by determining the point for a range of leakage radiation reduction to background and the linear relationship between power and leakage flux.

کلیدواژه‌ها [English]

  • Modeling
  • Power
  • VVER-1000 reactor
  • Gamma radiation
  • Neutron radiation
  • MCNP code

مراجع

[1] A.Z. Mesquita, H.C. Rezende and R.M.G. Prado Souza. Thermal power calibrations of the IPR-R1 TRIGA reactor by the calorimetric and the heat balance methods, Prog. Nucl. Energy, 53 (2011), 1197–1203. [2] M. Arakani and M. Gharib. Reactor core power measurement using Cherenkov radiation and its application in Tehran Research Reactor, Annu. Nucl. Energy, 36 (2009) 869–900. [3] A.I. Mogil’ner and D.M. Shvetsov. Statistical methods of measuring the absolute power of a reactor, J. Nucl. Energy, 21 (1967) 87–95. [4] N. Sadeghhi. Estimation of reactor power using N-16 production rate and its radiation risk assessment in Tehran research Reactor (TRR), Nucl. Eng. Des, 240 (2010) 3607–3610. [5] L. Yung-shen. Measurement of reactor power level by a Nitrogen-16 monitor Thesis in Nuclear Engineering, The Pennsylvania State University, The Graduate School, Department of Nuclear Engineering, (1964). [6] H.R. Armozd, M. Gharib, H. Afarideh, M. Ghergherehchi, A. Ahmadi Niar and M. Jafarzadeh. Determination of Tehran research reactor power by 16N gamma detection, Annu. Nucl. Energy, 38 (2011) 2667–2672. [7] S.G. Tsypin, V.V. Lysenko, A.I. Musorin, L.N. Bogachek, V.F. Bai, V.V. Kuz'min and A.B. Koshelev. N-16 ray diagnostics of a nuclear reactor in a nuclear power plant, Atom. Energy, 95(3) (2003) 609–612. [8] P.A. Beeley, J.M. Brushwood, M.G. Henesy, M.W. Collins and C.A. Haywood. Determination of in-core power in low energy research reactors by measurement of 16N and 18F in the primary coolant, J. Radioanal. Nucl. Chem, 215(1) (1997) 135–139. [9] R. Coulon, S. Normand, G. Ban, E. Barat, T. Montagu, T. Dautremer, H.P. Brau, V. Dumarcher, M. Michel, L. Barbot, T. Domenech, K. Boudergui, J.M. Bourbotte, P. Jousset, G. Barouch, S. Ravaux, F. Carrel, N. Saurel, A.M. Frelin Labalmea, H. Hamritaa and V. Kondrasovsa. Delayed gamma power measurement for sodium-cooled fast reactors, Nucl. Eng. Des, 241 (2011) 339–348. [10] Y.V. Klimov, V.I. Kopeikin, L.A. Mikaélyan, K.V. Ozerov and V.V. Sinev. Neutrino method remote measurement of reactor power and power output, Atom. Energy, 76(2) (1994) 123–127. [11] D. Lhuillier. Reactor neutrino monitoring, Nucl. Phys. B, 188 (2009) 112–114. [12] Y.Q. Shi and Y.G. Li. Measurement of fast fission factor for Heavy Water Zero Power Reactor (HWZPR) by solid state nuclear track detector, Radiat. Meas. 34 (2001) 605–607. [13] W.S. Snyder and J. Neufeld. Vacancies and Displacements in a Solid Resulting from Heavy Corpuscular Radiation, Phys. Rev, 103 (1956) 862. [14] T. Yamamoto and Y. Miyoshi. Improvement of neutron source introduction method for absolute measurements of low reactor power, J. Nucl. Sci. Technol, 36 (1999) 1069–1075. [15] J. Costa Oliverira. Absolute measurement of reactor power by neutron noise analysis, J. Nucl. Energy, 24 (1971) 525–526. [16] M. Jalali, M.R. Abdi and M. Mostajaboddavati. Reactor power measurement by gamma and neutron radiation in Heavy Water Zero Power Reactor (HWZPR), Annals of Nuclear Energy, 57 (2013) 368–374. [17] M. Jalali, M.R. Abdi and M. Mostajaboddavati. Prompt gamma radiation as a new tool to measure reactor power, Radiation Physics and Chemistry, 91 (2013) 19-27. [18] R. Mahmodi. VVER-1000 (V-320 & V-446) Nuclear Reactor (Reactor Building and Equipment, Normal Operating Systems and Safety Systems), Jahad Daneshgahi Publication, (2011). [19] D. Masti. Determining the Differential and Integral Value of Control Rods Using MCNP Code for a VVER-1000 Reactor (Master's Degree in Nuclear Engineering), Faculty of Nuclear Physics and Sciences Amir Kabir University, (2000). [20] IAEA. Iranian Atomic Energy Agency (AEOI) Documents, (2007). [21] J.F. Briesmeister. MCNP TM–A General Monte Carlo N–Particle Transport Code Version 5. Los Alamos National Laboratory, USA, (2011). [22] Denise B. Pelowitz. Monte Carlo N-particle transport code system for multi-particle and high energy applications, (2011). [23] Nuclear Power Technology Development Section International Atomic Energy Agency. WWER-1000 Reactor Simulator Material for Training Courses and Workshops, Second Edition Vienna Printed by the IAEA in Austria, (2005). [24] IAEA. Final Safety Analysis Report of Bushehr Nuclear Power Plant. Chapter 4, Reactor, (2007). [25] D.J. Bennet and J.R. Thomson. The Elements of Nuclear Power, 3rd.New York, (1989). [26] S. Astakhov, A. Kravchenko, Y. Kraynov, A. Nasedkin and S. Tsyganov. Determination of Reactor Parameters During Start up Tests at The Tianwan NPP, Unit 1 RRC Kurchatov Institute Moscow Russia, 13 (2006) 1-2. [27] S.A. Jonah, J.R. Liaw and J.E. Matos. Monte Carlo simulation of core physics parameters of the Nigeria Research Reactor-1 (NIRR-1), Annals of Nuclear Energy, 34 (2007) 953-957. [28] J. R Lamarsh and A. J Baratta. Introduction to Nuclear Engineering, Prentice Hall, 3rd Ed. (2001). [29] J. R Lamarsh. Introduction to Nuclear Reactor Theory, Addison-Wesley Publhshing Company, (1966).

فایل ها

هم رسانی

ارجاع به این مقاله

آمار