Neutronic performance calculations with alternative fluids in a hybrid reactor by using the Monte Carlo method

References

1 Şahin, S.; Übeyli, M.: Radiation Damage Studies on The First Wall of a HYLIFE-II Type Fusion Breeder. Energy Conversion and Management46 (2005) 3185 10.1016/j.enconman.2005.03.007Suche in Google Scholar

2 Şahin, H. M.: Monte Carlo Calculation of Radiation Damage in First Wall of An Experimental Hybrid Reactor. Annals of Nuclear Energy34 (2007) 86110.1016/j.anucene.2007.04.011Suche in Google Scholar

3 Şarer, B.; Günay, M.; et al.: Three-Dimensional Neutronic Calculations For The Fusion Breeder Apex Reactor. Fusion Science and Technology52 (2007) 10710.13182/FST07-A1490Suche in Google Scholar

4 Günay, M.; et al.: Three-Dimensional Neutronic Calculations for a Fusion Breeder Apex Reactor Using Some Libraries. Annals of Nuclear Energy38 (2011) 275710.1016/j.anucene.2011.08.007Suche in Google Scholar

5 Günay, M.; et al.: Three-dimensional Monte Carlo Calculation of Gas Production in Structural Material of APEX Reactor for Some Evaluated Data Files. Annals of Nuclear Energy55 (2013) 29210.1016/j.anucene.2013.01.001Suche in Google Scholar

6 Günay, M.; et al.: The Effect on Radiation Damage of Structural Material in a Hybrid System By Using a Monte Carlo Radiation Transport Code. Annals of Nuclear Energy63 (2013) 15710.1016/j.anucene.2013.07.038Suche in Google Scholar

7 Christofilos, N. C.: Design for A High Power-Density Astron Reactor. Journal of Fusion Energy8 (1989) 9710.1007/BF01050784Suche in Google Scholar

8 Moir, R. W.: Liquid First Walls For Magnetic Fusion Energy Configurations. Nuclear Fusion37 (1997) 55710.1088/0029-5515/37/4/I13Suche in Google Scholar

9 Abdou, M. A.; et al.: Chapter 1: Overview. APEX Interim Report, 1999Suche in Google Scholar

10 Abdou, M. A.; et al.: On The Exploration of Innovative Concepts for Fusion Chamber Technology. Fusion Engineering and Design54 (2001) 18110.1016/S0920-3796(00)00433-6Suche in Google Scholar

11 Abdou, M. A.: Preface. Fusion Engineering and Design72 (2004) 110.1016/j.fusengdes.2004.10.001Suche in Google Scholar

12 Abdou, M. A.; et al.: Overview of Fusion Blanket R&D in the US over the last Decade. Nuclear Engineering and Technology37 (5) (2005) 401Suche in Google Scholar

13 Abdou, M. A.: Research On Liquid Walls for Fusion Systems. Appl. Electromag. Mech.9 (2001) 151Suche in Google Scholar

14 Ying, A.; et al.: Chapter 5: Thick Liquid Blanket Concept, APEX Interim Report, 1999Suche in Google Scholar

15 Youssef, M. Z.; Abdou, M. A.: Heat Deposition, Damage and Tritium Breeding Characteristics in Thick Liquid Wall Blanket Concepts. Fusion Engineering and Design49 (2000) 71910.1016/S0920-3796(00)00179-4Suche in Google Scholar

16 Youssef, M. Z.; et al.: The Breeding Potential of “Flinabe” and Comparison to “Flibe” in “CLiFF” High Power Density Concept. Fusion Engineering and Design61 (2002) 49710.1016/S0920-3796(02)00245-4Suche in Google Scholar

17 IAEA: International Atomic Energy Agency IAEA-TECDOC-1349,2003Suche in Google Scholar

18 Piera, M.; et al.: Hybrid Reactors: Nuclear Breeding or Energy Production. Energy Conversion and Management51 (2010) 175810.1016/j.enconman.2010.01.025Suche in Google Scholar

19 Şarer, B.; et al.: Calculations of Neutron-Induced Production Cross-Sections of ^{180,182,183,184,186}W up to 20 MeV. Annals of Nuclear Energy36 (2009) 41710.1016/j.anucene.2008.11.025Suche in Google Scholar

20 Günay, M.: Investigation of radiation damage in structural material of APEX reactor by using Monte Carlo method. Annals of Nuclear Energy53 (2013) 5910.1016/j.anucene.2012.06.038Suche in Google Scholar

21 Günay, M.; Kasap, H.: Neutronic Investigation of the Application of certain Plutonium-Mixed Fluids in a Fusion-Fission Hybrid Reactor. Annals of Nuclear Energy63 (2014) 43210.1016/j.anucene.2013.08.024Suche in Google Scholar

22 Chadwick, M. B.; et al.: ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology. Nuclear Data Sheets, 107 (2006) 293110.1016/j.nds.2006.11.001Suche in Google Scholar

23 Pelowitz, D. B.: MCNPX User's Manual, Version 2.7.0, LA-CP-11-00438, 2011Suche in Google Scholar

24 Şarer, B.; et al.: Comparisons of The Calculations Using Different Codes Implemented in MCNPX Monte Carlo Transport Code for Accelerator Driven System Target. Fusion Science Technology61 (2012) 30210.13182/FST12-A13437Suche in Google Scholar

25 Sawan, M. E.; Abdou, M. A.: Physics and Technology Conditions for Attaining Tritium Self-Sufficiency for the DT Fuel Cycle. Fusion Engineering and Design81 (2006) 113110.1016/j.fusengdes.2005.07.035Suche in Google Scholar

26 Jung, J.; Abdou, M. A.: Assessments of Tritium Breeding Requirements and Breeding Potential for the Starfire/Demo Design. Nuclear Technology/Fusion4 (1983) 361Suche in Google Scholar

27 Youssef, M. Z.; Morley, N.; El-Azabet, A.: X-rays Surface and Volumetric Heat Deposition and Tritium Breeding Issues In Liquid-Protected FW In High Power Density Devices. Paper presented at the 13^th Topical Meeting on the Technology of Fusion Power. Nashville, Tennessee, June 7–11 (1998)Suche in Google Scholar

28 Abdou, M. A.; et al.: Deuterium-Tritium Fuel Self-Sufficiency in Fusion Reactors. Fusion Technology9 (1986) 25010.13182/FST86-A24715Suche in Google Scholar

29 Kuan, W.; Abdou, M. A.: A New Approach for Assessing The Required Tritium Breeding Ratio and Startup Inventory in Future Fusion Reactors. Fusion Technology35 (1999) 30910.13182/FST99-A84Suche in Google Scholar

30 Youssef, M. Z.; Abdou, M. A.: Uncertainties in Prediction of Tritium Breeding in Candidate Blanket Designs Due to Present Uncertainties in Nuclear Data Base. Fusion Technology9 (1986) 28610.13182/FST86-A24716Suche in Google Scholar

31 Şahin, S.; Übeyli, M.: Modified APEX Reactor as A Fusion Breeder. Energy Conversion and Management45 (2004) 149710.1016/j.enconman.2003.09.014Suche in Google Scholar

32 Dhaba'an, A. H.; Beynon, T. D.: Three-Dimensional Analyses of Candidate Blanket Designs for the Compact Tokamak Reactor Concept. Progress in Nuclear Energy29 (1995) 110.1016/0149-1970(94)00013-VSuche in Google Scholar