Ñ.Ï. Êëèìîâ, Â.Ò. Ëàçóðèê... Õàðàêòåðèñòèêè èçëó åíèÿ ïðè... ( ) [1] «Sierra Nuclear Corporation» [2]

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1 «Â³ñíèê Õàðê³âñüêîãî óí³âåðñèòåòó», ¹ 845, 2009 ñåð³ÿ ô³çè íà «ßäðà, àñòèíêè, ïîëÿ», âèï. 1 /41/ Õàðàêòåðèñòèêè èçëó åíèÿ ïðè ,.. 2,.. 1,.. 2,.. 2,.. 3 1,., 2...,., 3 «-»,., rud@pht.univer.kharkov.ua ModeASHE-M MCNPX. : ModeASHE-M - - ; MCNPX - ( geometry splitting ).,.,,., 1,4. :,, -1000,, - ( ) 2001 ( ) [1]. ( - ), ( ) VSC-24, «Sierra Nuclear Corporation» [2] ( ) ( 50 ) 380, 24..,,,,., -, ( -.1),,., 24.,,.,,. : (2,5 ), (7,5 ) (70 )

2 32 «Â³ñíèê Õàðê³âñüêîãî óí³âåðñèòåòó», ¹ 845, 2009, , 10., -1000, 4,4%, 41,5 / U 3-. VSC-24 ( - ), 350. (..1),,, 1 [1]. 5. -, (,, )., 3, [3]. SpectrOJAT [4] -,, 60,, JEF ( [5]), 1999 JEF 3 [6]. SpectrOJAT -., SpectrOJAT,, FISPACT [7], Nuclear Energy Agency., FISPACT,, 0, ) ).2. - (24 ) 41,5 / U, SpectrOJAT 50. ) ; ). - SpectrOJAT , 15, 25 41,5 / U 3-. -,.,.,, -,,. [8,9]., ( )

3 ñåð³ÿ ô³çè íà «ßäðà, àñòèíêè, ïîëÿ», âèï. 1 /41/ Õàðàêòåðèñòèêè èçëó åíèÿ ïðè variance reduction techniques MCNPX, geometry splitting cell importance. MCNPX,. ModeASHE [10-12]. MCNPX.. 3, MCNPX. ModeASHE-M. : - ; -, ;. - ModeASHE-M. 4. (4) (7),. (6) (8)., ( 5)., (,, ),.,., : ( - 1), ( - 2) ( - 3). -.. MCNPX ModeASHE-M,,,.,,,,..1,. MCNPX,.. 3. MCNPX.. 4. ModeASHE-M.

4 34 «Â³ñíèê Õàðê³âñüêîãî óí³âåðñèòåòó», ¹ 845, 2009,.. 5 (inhomo)-, MCNPX ( ). - -, ( - 50 ) - 5, ( 5, ). 6 (..2 ) ( - θ=6 ) ,..6-5,

5 ñåð³ÿ ô³çè íà «ßäðà, àñòèíêè, ïîëÿ», âèï. 1 /41/ Õàðàêòåðèñòèêè èçëó åíèÿ ïðè ( 1,5 ) 5, ,.,.9 (, ).,, -,.,, -,,, -., (..6), , ,, < γ < , 500,, ,1%. -, 2500,, 5 3%, 1% ( - ) -. - ( ), ,

6 36 «Â³ñíèê Õàðê³âñüêîãî óí³âåðñèòåòó», ¹ 845, 2009,... [12], -,. (inhomo)- MCNPX..11, 24 41,5 / U 6 ( ) , 25% ( 41,5 / U ).,,,..,,,..11., ModeASHE-M MCNPX., -, , ModeASHE-M MCNPX - 41,5 / U, 5 50, SpectrOJAT.,.8,, ModeASHE-M, MCNPX,,, 2% ( )..13 ( ). - ( ) 0,1. 5-6, 24 20,43. - MCNPX.,, ,4..,,, [13,14].. 14

7 ñåð³ÿ ô³çè íà «ßäðà, àñòèíêè, ïîëÿ», âèï. 1 /41/ Õàðàêòåðèñòèêè èçëó åíèÿ ïðè MCNPX, , ,, -,. -,. : ModeASHE-M -,. MCNPX ( geometry splitting ). - :,.,,., MCNPX ModeASHE-M,., 1,4., -,,. 1...,..,..,..,..,..,..,.. " ", 2006,, 2. Ventilated Storage Cask VSC-24. US NRC Certificate of Compliance NUREG :, ,..,.., , //.....,, (36) JEF-2.2 Radioactive Decay Data, OECD Nuclear Energy Agency, JEF Report 13, 1994.

8 38 «Â³ñíèê Õàðê³âñüêîãî óí³âåðñèòåòó», ¹ 845, A.L. Nichols Assessment and evaluation of decay data for EAF 1999/2000, UKNSF(99) P FISPACT is the inventory code in the EASY-2003 (European Activation System), PACKAGE-ID: NEA ,..,..,...., :, Thomas E. Booth, Monte Carlo Variance Comparison for Expected Value Versus Sampled Splitting // Nuclear Science and Engineering Vol. 89. P V. Lazurik, Yu. Rogov, V. Rudychev Simulation of Gamma Radiation Fields from Active Nucleus Distributed in Large Spatial Regions. Abstract Book IEEE Nuclear Science Symposium and Medical Imaging Conference, November 9-15, 1997, Albuquerque, New Mexico V. Lazurik, V. Moskvin, Yu. Rogov, V. Rudychev Gamma Radiation in a Dry Spend-Fuel Storage // Proceedings of the International Conference on the Physics of Nuclear Science and Technology Vol V. Rudychev, A. Adadurov, A. Kalinichenko, V. Lazurik, V. Moskvin, S. Pismeneskiy, Yu. Rogov Calculation of Radiation Fields at the Nuclear Power Plant During a Severe Accident // Proceedings of the International Conference on the Physics of Nuclear Science and Technology Vol.2. - P ,..,..,... -.:, ,..,..,.. //.....,, (38). -C THE CHARACTERISTICS OF RADIATION FIELD FROM DRY STORAGE OF SPENT NUCLEAR FUEL ON ZAPOROZHYE NPP S.P. Klimov 1, V.T. Lazurik 2, A.E. Luchnaja 1, S.A. Pismenetskiy 2, V.G. Rudychev 2, Y.V. Rudychev 3 1 Zaporozhye NPP, Energodar 2 V.N. Karazin Kharkov National University, Kharkov 3 National Scientific Center, Kharkov Institute of Physics and Technology, Kharkov For the calculation of the radiation field around the ventilated cask for dry spent nuclear fuel storage of Zaporozhye NPP the methods were modified that based on the use of Monte Carlo packages MODEASHE-M and MCNPX. For time expenses decreasing the special methods of diminishing of dispersion were used: method of translations of trajectories of quanta and exponential transformation in MODEASHE-M code; the «geometrical spallation» ( geometry splitting ) in MCNPX code. For ventilated cask VSC spectra have been obtained and angular distributions of radiation out of cask and also the change of parameters of radiation depending on time keeping and dependence of dose rate on the distance to the surface of VSC. It was shown that characteristics of VSC radiation are dependent on the fuel assemblies located on the perimeter of basket of cask. Comparison of the calculated distributions of dose power along the surface of VSC with their measured values shows the excess approximately at 1.4 times. KEY WORDS: irradiated nuclear fuel, spent fuel storage, gamma-ray spectrum, concrete ventilated cask, spent fuel assemblies