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[en] Thorium reserves in the earth's crust are much more than those of uranium, which today measure about 1.5 million tonnes of reasonably assured resources, plus 3 million tonnes of estimated additional resources. These large amount of thorium reserves, also available in Turkey encourages to focus on the utilization of thorium. The most remarkable applications of the use of thorium have been in high temperature reactors. The high temperature pebble bed reactor, which has been chosen as the basis for this study, is a close approximation of the thorium utilizing German reactor THTR. Pebble bed reactors have some unique features which are suitable to burn thorium. (i) The fuel is loaded in the form of coated particles, which are embedded in the graphite matrix of the fuel pebbles, allowing exceptionally high heavy metal burnups; and (ii) the continuous (on-line) fuel loading allows a high utilization factor. The criticality search of the pebble bed reactor is computed by the use of the SCALE4.4 code, CSASIX and KENOVa modules. And the in-core fuel management is computed via SCALE4.4 code, ORIGEN-S module
Source
Turkish Atomic Energy Authority, Ankara (Turkey); International Atomic Energy Agency, Vienna (Austria); OECD/Nuclear Energy Agency, Paris (France); State Planning Organization, Ankara (Turkey); Ege University, Izmir (Turkey); Institute of Nuclear Physics of Uzbekistan Academy of Science, Taskent (Uzbekistan); National Acedemy of Science of Kyrgyzstan, Biskek (Kyrgyzstan); Institute of Nuclear Physics of National Nuclear Center of Kazakhstan, Almaty (Kazakhstan); Academy of Science of Azerbaijan, Baku (Azerbaijan); 642 p; ISBN 975-19-2768-4; 
; 2001; p. 348-353; 1. Eurasia Conference on Nuclear Science and Its Application; 1. Avrasya Nuekleer Bilimler ve Uygulamalari Konferansi; Izmir (Turkey); 23-27 Oct 2000; Available from Turkish Atomic Energy Authority, Ankara (Turkey)
; 2001; p. 348-353; 1. Eurasia Conference on Nuclear Science and Its Application; 1. Avrasya Nuekleer Bilimler ve Uygulamalari Konferansi; Izmir (Turkey); 23-27 Oct 2000; Available from Turkish Atomic Energy Authority, Ankara (Turkey)
[en] Fuel cycle optimization is one of the key subjects of reactor operation. In this study, fuel cycles of Spectral Shift PWR and Pebble Bed HTGR are optimized by using nonlinear reactivity model. The Spectral Shift concept is based on the adjustments of fuel to moderator ratio as a function of burnup. For n-batch fuel cycle, where n is equal to 3 and 4, the fuel to moderator ratio is determined as a function of burnup to maximize discharge burnup, Bd. Results show that it is possible to increase discharge burnup up to 25 percent compared to typical commercial PWR designs. Another problem arises in the design of PB-HTGR's fuel pebbles and mixing ratio. The optimization of the composition of fuel pebbles and mixing ratio for direct and n-pass fuel cycles are analyzed to maximize discharge burnup. We compared our results with the current design parameters of HTR-10 and PBMR.(author)
Source
Jencic, I.; Tkavc, M. (Nuclear Society of Slovenia (Slovenia)) (eds.); Nuclear Society of Slovenia, Ljubljana (Slovenia). Funding organisation: Inst. Jozef Stefan, Ljubljana (Slovenia); European Nuclear Society, Brussels (Belgium); Ministry of Education, Science and Sport of Slovenia, Ljubljana (Slovenia); Slovenian Nuclear Safety Administration, Ljubljana (Slovenia); Agency for Radwaste Management, Ljubljana (Slovenia); Faculty of Mechanical Engineering, Univ. of Ljubljana (Slovenia); Graduate Program Nucelar Engineering, Univ. of Ljubljana (Slovenia); Inst. of Metals and Technology, Ljubljana (Slovenia); Inst. of Metal Constructions, Ljubljana (Slovenia); NPP Krsko (Slovenia); Framatome, Paris (France); Westinghouse Electric Systems Europe S.A., Brussels (Belgium); Canberra-Packard Central Europe, Schwadorf (Austria); Elmont, Krsko (Slovenia); ENCONET International, Zagreb (Croatia); Inetec, Zagreb (Croatia); NUMIP, Krsko (Slovenia); Q Techna, Krsko (Slovenia); SIAP, Maribor (Slovenia); [602 p.]; ISBN 961-6207-20-2; ; 2002; [8 p.]; International Conference Nuclear Energy in Central Europe 2002; Kranjska Gora (Slovenia); 9-12 Sep 2002; Also available from Slovenian Nuclear Safety Administration, Zelezna cesta 16, Ljubljana (SI) or Nuclear Society of Slovenia, Jamova 39, Ljubljana (SI); 7 refs., 7 tabs., 1 fig.
; 2002; [8 p.]; International Conference Nuclear Energy in Central Europe 2002; Kranjska Gora (Slovenia); 9-12 Sep 2002; Also available from Slovenian Nuclear Safety Administration, Zelezna cesta 16, Ljubljana (SI) or Nuclear Society of Slovenia, Jamova 39, Ljubljana (SI); 7 refs., 7 tabs., 1 fig.
[en] In this paper, KENOV.a module of SCALE code system was used to perform Monte Carlo simulation of the TRIGA MARK II research reactor benchmark experiments [1,2] in steady state operation conditions. Robert Jeraj and his coworkers have presented a similar simulation of the TRIGA MARK II research reactor benchmark experiments via MCNP4A in 1997. [3] The core excess reactivity measurement experiments were simulated using detailed geometrical representation with ENDF/B-V 44 and 238 group cross-section libraries. The experiments on control rod worth measurements were simulated for rod insertion and rod exchange method. It was shown that the experimental results on control rod worths are in good agreement with KENOV.a simulations in the case of rod insertion method. However, the simulation results for the rod exchange method are not in agreement with the experimental data since the model used in KENOV.a does not represent the experimental setup.(author)
Source
Jencic, I.; Glumac, B. (Nuclear Society of Slovenia (Slovenia)) (eds.); Nuclear Society of Slovenia, Ljubljana (Slovenia). Funding organisation: Inst. Jozef Stefan, Ljubljana (Slovenia); European Nuclear Society, Brussels (Belgium); Ministry of Education, Science and Sport of Slovenia, Ljubljana (Slovenia); Slovenian Nuclear Safety Administration, Ljubljana (Slovenia); Agency for Radwaste Management, Ljubljana (Slovenia); Faculty of Mechanical Engineering, Univ. of Ljubljana (Slovenia); Graduate Program Nucelar Engineering, Univ. of Ljubljana (Slovenia); Inst. of Metals and Technology, Ljubljana (Slovenia); The Inst. of Metal Constructions, Ljubljana (Slovenia); The Milan Vidmar Electroinstitute, Ljubljana (Slovenia); Welding Inst., Ljubljana (Slovenia); NPP Krsko (Slovenia); Framatome, Paris (France); Westinghouse Electric Systems Europe S.A., Brussels (BE); Elmont d.o.o., Krsko (Slovenia); Inetec, Zagreb (Croatia); NUMIP d.o.o, Krsko (Slovenia); Q Techna d.o.o., Krsko (Slovenia); SIAP d.o.o., Krsko (Slovenia); 97.2 Megabytes; ISBN 961-6207-17-2; ; 2001; [8 p.]; International Conference Nuclear Energy in Central Europe 2001; Portoroz (Slovenia); 10-13 Sep 2001; Also available from Slovenian Nuclear Safety Administration, Zelezna cesta 16, Ljubljana (SI) or Nuclear Society of Slovenia, Jamova 39, Ljubljana (Slovenia); 5 refs., 6 tabs., 5 figs.
; 2001; [8 p.]; International Conference Nuclear Energy in Central Europe 2001; Portoroz (Slovenia); 10-13 Sep 2001; Also available from Slovenian Nuclear Safety Administration, Zelezna cesta 16, Ljubljana (SI) or Nuclear Society of Slovenia, Jamova 39, Ljubljana (Slovenia); 5 refs., 6 tabs., 5 figs.
[en] Ultraspherical polynomial Pn(λ) approximations are used in reflected slab criticality calculations for strongly anisotropic scattering. A unique formulation is developed for reflected slab criticality conditions whose special cases are spherical harmonics approximations, Chebyshev polynomial approximations of first and second kind. It is shown in the calculations that all ultraspherical polynomial approximations are equivalent regarding the convergence of the solution of one-speed neutron transport equation for various degrees of anisotropy and cross section parameters. Although some ultraspherical polynomials approximations converge in the mean as the order of approximation is increased and some converge uniformly, they all converge to the same critical thickness which implies their equiconvergence. It is also demonstrated that the first order approximation P1(λ) would give the exact critical thickness for a certain value of the parameter λ. (orig.)
Journal
[en] In this work, the full core modelling is performed to improve neutronic analyses capability for nuclear research reactors using SCALE4.4 code system. KENOV.a module of SCALE4.4 code system is utilized for full core neutronic analysis. The ORIGEN-S module is coupled with the KENOV.a module to perform burnup dependent neutronic analyses. Results of neutronic calculations for 1st cycle of Cekmece TR-2 research reactor are presented. In particular, coupling of KENOV.a and ORIGEN-S modules of SCALE4.4 is discussed. The preliminary results of 2-D burnup dependent neutronic calculations are also given. These results are extended to burnup dependent core calculations of TRIGA Mark-II research reactors. The code system developed here is similar to the code system that couples MCNP and ORIGEN2.(author)
Source
Jencic, I.; Glumac, B. (Nuclear Society of Slovenia (Slovenia)) (eds.); Nuclear Society of Slovenia, Ljubljana (Slovenia). Funding organisation: Inst. Jozef Stefan, Ljubljana (Slovenia); European Nuclear Society, Brussels (Belgium); Ministry of Education, Science and Sport of Slovenia, Ljubljana (Slovenia); Slovenian Nuclear Safety Administration, Ljubljana (Slovenia); Agency for Radwaste Management, Ljubljana (Slovenia); Faculty of Mechanical Engineering, Univ. of Ljubljana (Slovenia); Graduate Program Nucelar Engineering, Univ. of Ljubljana (Slovenia); Inst. of Metals and Technology, Ljubljana (Slovenia); The Inst. of Metal Constructions, Ljubljana (Slovenia); The Milan Vidmar Electroinstitute, Ljubljana (Slovenia); Welding Inst., Ljubljana (Slovenia); NPP Krsko (Slovenia); Framatome, Paris (France); Westinghouse Electric Systems Europe S.A., Brussels (BE); Elmont d.o.o., Krsko (Slovenia); Inetec, Zagreb (Croatia); NUMIP d.o.o, Krsko (Slovenia); Q Techna d.o.o., Krsko (Slovenia); SIAP d.o.o., Krsko (Slovenia); 97.2 Megabytes; ISBN 961-6207-17-2; ; 2001; [9 p.]; International Conference Nuclear Energy in Central Europe 2001; Portoroz (Slovenia); 10-13 Sep 2001; Also available from Slovenian Nuclear Safety Administration, Zelezna cesta 16, Ljubljana (SI) or Nuclear Society of Slovenia, Jamova 39, Ljubljana (Slovenia); 4 refs., 2 tabs., 9 figs.
; 2001; [9 p.]; International Conference Nuclear Energy in Central Europe 2001; Portoroz (Slovenia); 10-13 Sep 2001; Also available from Slovenian Nuclear Safety Administration, Zelezna cesta 16, Ljubljana (SI) or Nuclear Society of Slovenia, Jamova 39, Ljubljana (Slovenia); 4 refs., 2 tabs., 9 figs.
[en] Genetic Algorithm (GA) based systems are used for the loading pattern optimization. The use of Genetic Algorithm operators such as regional crossover, crossover and mutation, and selection of initial population size for PWRs are discussed. Antithetic variates are used to generate the initial population. The performance of GA with antithetic variates is compared to traditional GA. The results of multi-cycle optimization are discussed for objective function taking into account cycle burn-up and discharge burn-up
Source
Turkish Atomic Energy Authority, Ankara (Turkey); International Atomic Energy Agency, Vienna (Austria); OECD/Nuclear Energy Agency, Paris (France); State Planning Organization, Ankara (Turkey); Ege University, Izmir (Turkey); Institute of Nuclear Physics of Uzbekistan Academy of Science, Taskent (Uzbekistan); National Acedemy of Science of Kyrgyzstan, Biskek (Kyrgyzstan); Institute of Nuclear Physics of National Nuclear Center of Kazakhstan, Almaty (Kazakhstan); Academy of Science of Azerbaijan, Baku (Azerbaijan); 642 p; ISBN 975-19-2768-4; ; 2001; p. 132-141; 1. Eurasia Conference on Nuclear Science and Its Application; 1. Avrasya Nuekleer Bilimler ve Uygulamalari Konferansi; Izmir (Turkey); 23-27 Oct 2000; Available from Turkish Atomic Energy Authority, Ankara (Turkey)
; 2001; p. 132-141; 1. Eurasia Conference on Nuclear Science and Its Application; 1. Avrasya Nuekleer Bilimler ve Uygulamalari Konferansi; Izmir (Turkey); 23-27 Oct 2000; Available from Turkish Atomic Energy Authority, Ankara (Turkey)
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