Abstract
In design a Deuterium–Tritium (D–T) fusion driven hybrid reactor, neutronics and nuclear data libraries have an essential role for reliable neutronics calculations. Therefore, nuclear data libraries are very important to calculate of the neutronic parameters and selection of tritium breeder materials to be used in the blanket. In this study tritium breeding performances of candidate tritium breeding materials, namely, Li2O, LiH, Li2TiO3, Li2ZrO3 and Li4SiO4 in a (D–T) driven fusion–fission (hybrid) reactor is investigated based on three dimensional (3-D) and one dimensional (1-D) neutronic calculations. 3-D and 1-D neutron transport calculations are performed with Monte Carlo transport code (MCNP 4C), SCALE 5 and ANISN nuclear data codes to determine the tritium breeding ratio (TBR) of the blanket. The effects of different nuclear data libraries on TBR are examined and TBR calculation results are comparatively investigated.
Similar content being viewed by others
References
E. Greenspan, in Fusion–Fission Hybrid Reactors, Advances in Science and Technology, vol. 16, ed. by J. Lewins, M. Becker (Plenum Press, 1984), p. 289
D.H. Berwald, et al., Fission Suppressed Hybrid Reactor Fusion Breeder (Lawrence Livermore National Laboratory, UCID-19327, 1982)
R.W. Moir, The fusion breeder, submitted to the National Science Foundation Policy Workshop (Washington DC, March 4–5, Lawrence Livermore Laboratory, CA, UCRL-87290, 1982)
J.D. Lee, et al., Feasibility study of a Fission-Suppressed Tandem-Mirror Hybrid Reactor: Fusion Breeder. (Lawrence Livermore National Laboratory, CA, UCID-19327, 1982)
S. Şahin, T.A. Al-Kusayer, M.A. Raoof, Fusion Technol. 10, 84 (1986)
S. Şahin, H. Yapıcı, Ann. Nucl. Energy 26, 13–27 (1999)
H.M. Şahin, Ann. Nucl. Energy 34, 861–870 (2007)
S. Şahin, R. Moir, J.D. Lee, S. Ünalan, Fusion Technol. 25(4), 388–397 (1994)
S. Ünalan, et al., Energy Convers. Manage. 44, 2567 (2003)
M.E. Sawan, M.Z. Youssef, Fusion Eng. Des. 81, 1169–1181 (2006)
Y. Futamura, H. Kawamura, K. Tsuchiya, Tritium Breeding Materials Data Base for Fusion reactor Blankets (4), Hydrogen Isotope Research Center (HRC) Annual Report, vol. 19, Toyama University, (1999)
M. Song, et al., Fusion Eng. Des. 10, 47–55 (1989)
M. Übeyli, J. Fusion Energy 25(1–2), 99–106 (2006)
K. Yıldız, A. Acır, J. Fac. Eng. Arch. Gazi Univ. 20–4, 463 (2005), (in Turkish)
K. Yıldız, Ann. Nucl. Energy 32–1, 101 (2005)
S. Şahin et al., Ann. Nucl. Ener. 29, 1641 (2002)
J.F. Briesmeister, A General Monte Carlo N-Particle Transport Code, Version 4C, LA-13709 M Los Alamos National Laboratory, MCNP, (2000)
R. Kinsey, Data Formats and Procedures for the Evaluated Nuclear Data File, ENDF. Brookhaven National Laboratory Report, BNL-NCS-50496 (ENDF 102) 2nd edn. (ENDF/B-V) (October 1979)
ENDF/B-VI. The US Evaluated Neutron Nuclear Data Library for Neutron Reactions. IAEA Vienna, IAEA-NDS-100. Rev. 6 (1995)
ANS-6.1.1 Working Group, M.E. Battat (Chairman). American National Standard Neutron and Gamma-Ray Flux-to-Dose Rate Factors. ANSI/ANS-6.1.1-1977 (N666), American Nuclear Society, LaGrange Park, Illinois (1977)
P.F. Rose, Compiler and Editor. ENDF-201, ENDF/B-VI Summary Documentation. BNL-NCS-17541, Brookhaven National Laboratory (1991)
L.M. Petrie, SCALE5-Scale System Driver, NUREG/CR-0200, Revision 7, Volume III, Section M1. ORNL/NUREG/CSD-2/V3/R7, Oak Ridge National Laboratory (2004)
W.W. Engle, ANISN, A One-Dimensional Discrete Ordinates Transport Code With Anisotropic Scattering. K1693, Oak Ridge National Laboratory (1970)
T.A. Al-Kusayer, et al., CLAW-IV, Coupled 30 Neutrons, 12 Gamma Ray Group Cross Sections with Retrieval Programs for Radiation Transport Calculations. RSIC Newsletter, Radiation Shielding Information Center, Oak Ridge National Laboratory (1988)
R.J. Barrett, R.E. Macfarlane, CLAW, Coupled 30 Neutrons, 12 Gamma-Ray Group Cross Sections For Neutron Transport Calculations. LA-7808-MS, Los Alamos Scientific Laboratory (1979)
R.E. MacFarlane, TRANSX-2, A Code For Interfacing MATXS Cross-Section Libraries to Nuclear Transport Codes. Los Alamos Scientific Laboratory (1993)
N.M. Greene, L.M. Petrie, XSDRNPM, A One-Dimensional Discrete-Ordinates Code For Transport Analysis, NUREG/CR-0200, Revision 7, vol. 2, Section F3. ORNL/NUREG/CSD-2/V2/R7, Oak Ridge National Laboratory (2004)
W.C. Jordan, S.M. Bowman, Scale Cross-Section Libraries, NUREG/CR-0200, Revision 7, vol. 3, Section M4. ORNL/NUREG/CSD-2/V3/R7, Oak Ridge National Laboratory (2004)
N.M. Greene, BONAMI, Resonance Self-Shielding by the Bondarenko Method, NUREG/CR-0200, Revision 7, 2, Section F1. ORNL/NUREG/CSD-2/V2/R7, Oak Ridge National Laboratory (2004)
N.M. Greene, L.M. Petrie, R.M. Westfall, NITAWL-III, Scale System Module For Performing Resonance Shielding and Working Library Production, NUREG/CR-0200, Revision 7, 2, Section F2. ORNL/NUREG/CSD-2/V2/R7, Oak Ridge National Laboratory (2004)
N.F. Landers, L.M. Petrie, D.F. Hollenbach, CSAS, Control Module for Enhanced Criticality Safety Analysis Sequences, NUREG/CR-0200, Revision 7, 1, Section C4. ORNL/NUREG/CSD-2/V1/R7, Oak Ridge National Laboratory (2004)
S. Şahin, H. Yapıcı, S. Ünalan, ERDEMLI, A Computer Program to Process ANISN Output Data (Gazi University, Ankara, Turkey, 1991)
Author information
Authors and Affiliations
Corresponding author
Rights and permissions
About this article
Cite this article
Acır, A. Effect of Nuclear Data Libraries on Tritium Breeding in a (D–T) Fusion Driven Reactor. J Fusion Energ 27, 301–307 (2008). https://doi.org/10.1007/s10894-008-9141-6
Published:
Issue Date:
DOI: https://doi.org/10.1007/s10894-008-9141-6