Effect of95241Am(n, γ) reaction branching ratio on fuel cycle and reactor design characteristics

Nuclear Science and Engineering

Volumn 161, Issue 3, 2009, Pages 289-302

  Golyand, Leonid ^a   Shwageraus, Eugene ^a   Ronen, Yigal ^a  

^a BEN GURION UNIVERSITY OF THE NEGEV   (Israel)

Author keywords

[No Author keywords available]

Indexed keywords

ACTINIDES; LIBRARIES; LIGHT WATER REACTORS; NEUTRONS; NUCLEAR FUELS;

ACCURATE PREDICTION; ADVANCED FUEL CYCLE; EVALUATED NUCLEAR DATA FILE; INCIDENT NEUTRON ENERGY; ISOTOPIC COMPOSITION; LIGHT WATER REACTOR FUELS; NEUTRON ENERGY SPECTRUM; TRANSURANIC ACTINIDES;

FUELS;

EID: 62449154539     PISSN: 00295639     EISSN: None     Source Type: Journal    
DOI: 10.13182/NSE161-289     Document Type: Article

References (22)

1. 242m Am in a Fast Reactor," Nucl. Technol., 153, 224 (2005).
2. 242m Am Production in Thermal Reactors," Nucl. Technol., 148, 97 (2004).
3. P. BENETTI, A. CESANA, L. CINOTTI, G. RASELLI, and M. TERRANI, "Americium 242m and Its Potential Use in Space Applications," J. Phys. Conf. Ser., 41, 161 (2006).
4. 242mAm as a Nuclear Fuel," Nucl. Technol., 129, 407 (2000).
5. 242mAm Fueled Nuclear Battery," Nucl. Instrum. Methods Phys. Res. A, 531, 639 (2004).
6. Y. RONEN, M. KURTZHAND, L. DROIZMAN, and E. SHWAGERAUS, "Conceptual Design of Americium Nuclear Battery for Space Applications," J. Propulsion Power, 23, 874 (2007).
7. F. M. MANN and R. E. SCHENTER, "Calculated Neutron Capture Cross Sections to the Americium Ground and Isomeric States," Nucl. Sci. Eng., 63, 242 (1977).
8. "JANIS 3.0," Nuclear Energy Agency; available on the Internet at http://www.nea.fr/janis.
9. M. B. CHADWICK, P. OBLOZINSKY, M. HERMAN, N. M. GREENE, R. D. McKNIGHT, D. L. SMITH, P. G. YOUNG, R. E. MACFARLANE, G. M. HALE, S. C. FRANKLE, A. C. KAHLER, T. KAWANO, R. C. LITTLE, D. G. MADLAND, P. MOLLER, R. D. MOSTELLER, P. R. PAGE, P. TALOU, H. TRELLUE, M. C. WHITE, W. B. WILSON, R. ARCILLA, C. L. DUNFORD, S. F. MUGHABGHAB, B. PRITYCHENKO, D. ROCHMAN, A. A. SONZOGNI, C. R. LUBITZ, T. H. TRUMBULL, J. P. WEINMAN, D. A. BROWN, D. E. CULLEN, D. P. HEINRICHS, D. P. McNABB, H. DERRIEN, M. E. DUNN, N. M. LARSON, L. C. LEAL, A. D. CARLSON, R. C. BLOCK, J. B. BRIGGS, E. T. CHENG, H. C. HURIA, M. L. ZERKLE, K. S. KOZIER, A. COURCELLE, V. PRONYAEV, and S. C. VAN DER MARCK, "ENDF/B-VII.O: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology," Nucl. Data Sheets, 107, 2931 (2006).
10. "WIMS-D Library Update: Final Report of a Coordinated Research Project," International Atomic Energy Agency (2007).
11. R. SANCHEZ, J. MONDOT, Z. STANKOVSKI, A. COSSIC, and I. ZMIJAREVIC, "APOLLO II: A User-Oriented, Portable, Modular Code for Multigroup Transport Assembly Calculations," Nucl. Sci. Eng., 100, 352 (1988).
12. J. PARATTE, P. GRIMM, and J. HOLLARD, "User's Manual for the Fuel Assembly Code BOXER," Paul Scherrer Institut (1995).
13. "MCNP: A General Monte Carlo N-Particle Transport Code, Version 4C," LA-13709M, J. F. BRIESMEISTER, Ed., Los Alamos National Laboratory (Apr. 2000).
14. E. SHWAGERAUS, E. FRIDMAN, E. ABRAMSKY, and A. GALPERIN "BG-CORE-A Comprehensive Package for Reactor Core and Fuel Storage Analysis," Proc. 23rd Conf. Nuclear Societies in Israel, Dead Sea, Israel, February 2005.
15. G. O'CONNOR, "Burn-Up Credit Criticality Benchmark, Phase IV-B: Results and Analysis of MOX Fuel Depletion Calculations," Radioactive Materials Transport Division, Department for Transport, Local Government and the Regions, United Kingdom (2003).
16. T. A. TAIWO, T. K. KIM, J. A. STILLMAN, R. N. HILL, M. SALVATORES, and P. J. FINCK, "Assessment of a Heterogeneous PWR Assembly for Plutonium and Minor Actinide Recycle," Nucl. Technol., 155, 34 (2006).
17. M. SALVATORES, "The Physics of Transmutation in Critical or Subcritical Reactors," Appl. Phys., 3, 999 (2002).
18. 242mAm in a PWR," Proc. 24th Conf. Nuclear Societies in Israel, Dead Sea, Israel, February 2007.
19. "Fast Reactor Database," IAEA-TECDOC-1531, International Atomic Energy Agency (2006).
20. K. WIRTZ, Lectures on Fast Reactors, Karlsruhe University (1978).
21. J. ASKEW, F. FAYERS, and P. KEMSHELL, "A General Description of the Code WIMS," Nucl. Energy Soc., 5, 564 (1966).
22. A. CROFF, "ORIGEN2: A Versatile Computer Code for Calculating the Nuclide Compositions and Characteristics of Nuclear Materials," Nucl. Technol., 62, 335 (1983).