MOX and MOX with 237Np/ 241am inert gas generation comparison in ATR

Transactions of the American Nuclear Society

Volumn 94, Issue , 2006, Pages 589-590

  Chang, G S ^a   Robel, M ^a   Carmack, W J ^a   Utterbeck, D J ^a  

^a IDAHO NATIONAL LABORATORY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

EID: 33746074528     PISSN: 0003018X     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (5)

1. G. S. Chang and J. M. Ryskamp, "Depletion Analysis of Mixed Oxide Fuel Pins in Light Water Reactors and the Advanced Test Reactor," Nucl. Technol., Vol. 129, No. 3, p. 326-337 (2000).
2. J. F. Briesmeister (Editor), "MCNP - A General Monte Carlo N-Particle Transport Code, Version 4C," LA-13709, Los Alamos National Laboratory (2000).
3. A. G. Croff, "ORIGEN2: A Versatile Computer Code for Calculating the Nuclide Compositions and Characteristics of Nuclear Materials," Nuclear Technology, Vol. 62, pp. 335-352, 1983.
4. F. W. Ingram, R. G. Ambrosek, G. S. Chang, and D. J. Utterbeck, "JAPEIC Irradiation Report for the SFT-1, SFT-3 and FELI-2/3 Specimens," August 2001.
5. G. S. Chang, "ATR WG-MOX Fuel Pellet Burnup Measurement by MONTE CARLO - MASS Spectrometric Method," Proceedings of the International Conference on the New Frontiers of Nuclear Technology: Reactor Physics, Safety and High-Performance Computing, ANS 2002 RPD Topical Meeting, Seoul, Korea, October 7-10, 2002.