Aybaba HANÇERLİOĞULLARI

Monte Carlo Simülasyon Metodu ve MCNP Kod Sistemi

Monte Carlo metodu, olaslık teorisi üzerine kurulu bir sistemdir. Monte Carlo metodunda istatistiksel ve matematiksel tekniklerle bir deneyi veya çözülmesi gereken bir fiziksel olayı tesadüfi sayıları defalarca kullanarak simülasyon edilip çözmek esastır.(1)Günümüzde bu metot, fizik ve matematik problemlerinin çözümünde MCNP(Monte Carlo N – Parçacık Taşınım ) kodunu kullanarak nükleer transport hesaplamalarda iyi sonuçlar vermektedir (2,3).

Monte Carlo Simulation Method and MCNP Code System

The Method of Monte Carlo is a system which is based upon the theory of possibility. What is fundamental in this method is to clarify a physics incident or experiment which has to be explained with statistical and mathematical techniques by using random numbers constantly in order to simulate.(1) Nowadays, this method is so perfect in solving physical or mathematical problems and in nuclear transport calculations by using MCNP (Monte Carlo N-partıcal transport) code (2,3.)

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1. Briesmeister, J., “RSIC Computer Code Collection MCNP4A, Monte Carlo N-Particle Transport Code System”, Los Alamos National Laboratory, New Mexiko, 1993.
2. Johston, R., “A General Monte Carlo Neutronics Code”, LAMS-2856, Los alamos, 1963.
3. Hançerlioğulları, A., “APEX Hibrid Reaktör Modellemesi İçin Monte Carlo Yöntemi Kullanılarak Nötron Transport Hesaplamalarının Yapılması”, Doktora Tezi, Gazi Üniversitesi, Ankara, 2003.
4. Spanier,J.,” Monte Carlo Methods and their application to neutron transport problems”, USAEC report WAPPD-195,Bettis atomic power laboratory,july 1959
5. Şarer.,B, Hançerlioğulları, A.,Übeyli.,”Nükleer hesaplamalarda monte carlo yönteminin kullanımı”,8.ulusal nükleer bilimler ve teknolojiler kongresi, Kayseri, Ekim 2003
6. Birger,J.,”Random number generators Victor petterson’s bokindustri aktiibolar”Stockholm,1966
7. Leimddorter,A.”On the Transformation of the Transport Equation for Solving Deep Penetration Problems by the monte carlo metod,”Trans.Chalmers Univ.Technol.,Gothenbers.No:286,1964
8. Ürün.,G.,Menkinli C.T.,”Applicatıons of monte carlo simulatıon in petroleum exploratıon and productıon as a method of rısk analysıs”TPJD bülteni,cilt 15,sayı 1haziran,2003
9. Morton,K.W.,”On the tratment of monte carlo methods in textbooks.”Math.Tab.Aids Comput.10,223-224
10. Hammerssley,J.M.,”Monte Carlo Methods for solving multivariable problems.”Ann.Newyork Acad.Sci.86,844-874
11. Garber,D.,”ENDF/B-V,”Report BLN-17541(ENDF-201),Natinol Nuclear Data Center,Brookhaven National laboratory ,Upton,N.Y.,October 1975
12. Howerton,R.J.,Cullen,D.E.,Haight ,R.C,MacGregor,M.H.,”The LLL Evaluated Nuclear Data Library(ENDL):Evaluation techniques,Reaction Index,and Descriptions of ındividual reactions,”Lawrence Livermore National Laboraty report UCRL-50400,Vol.15, Part A,September 1975
13. Ulam,S.,Metropolis ,N.,”The Monte Carlo Method,”j.amer.Stat.assoc.,44,335,1949
14. Foster,D.G.,Artur,”Avarege Neutronic Properties of “Prompt” Fission Poducts,” Los Alamos National Laboraty Report LA-9168-MS,February 1982
15. Lux,.I.,Koblinger,L.”Monte Carlo Particle Transport Methods,Neutron and Photon Calculations ,CRC Pres,boc raton.,1991