MOX and MOX with 237Np/241Am Inert Fission Gas Generation Comparison in ATR Page: 3 of 3
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Table 1. Comparison of RG-MOX and RG-MOX with
Np/Am inert gas generated versus EFPD.
RG-MOX with
EFPD RG-MOX N /Am
He-4 (cm at STP)
125 0.0099 0.7158
250 0.0319 2.7528
375 0.0795 5.5234
500 0.1550 8.2341
625 0.2714 10.9092
750 0.4196 13.2040
Kr (cm3 at STP)
125 0.9649 0.9933
250 2.0229 2.0747
375 2.9114 2.9761
500 3.5911 3.6655
625 4.1559 4.2400
750 4.6349 4.7336
Xe (cm3 at STP)
125 14.1253 14.5928
250 29.6718 30.5445
375 42.9961 44.1182
500 53.1880 54.5127
625 61.9150 63.4734
750 69.3953 71.2654
Total Inert Gas (cm3 at STP)
125 15.1000 16.3019
250 31.7267 35.3720
375 45.9870 52.6177
500 56.9341 66.4123
625 66.3423 78.6227
750 74.4499 89.2030
As expected, the Kr and Xe fission gas production,
which is proportional to burn-up, did not show any
significant differences between the two case studies after
750 EFPD. However, the He-4 generated, which comes
from the Am-241 transmutation and Cm-242 a-decay, and
the Np-237 transmutation and Pu-238 a-decay (Due to its
long a-decay time, the contribution is very small),
showed significant increase in Case-2 RG-MOX with
Np/Am, which will have an impact on the fuel
performance versus burnup.CONCLUSIONS
The verified MCWO method was used to perform the
neutronics analysis of LWR-2 fuel testing in ATR.
Although the LHGR and burn-up for Case-1 and Case-2
did not show significant differences, the inert gas
generated did show a significant difference. The results of
this study can be used as a reference for the MOX fuel
pellet postirradiation examination (PIE) analysis by the
INL. PIE results can also be used to validate MCWO
method.
REFERENCES
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.
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Chang, G. S.; Robel, M.; Carmack, W. J. & Utterbeck, D. J. MOX and MOX with 237Np/241Am Inert Fission Gas Generation Comparison in ATR, article, June 1, 2006; [Idaho Falls, Idaho]. (https://digital.library.unt.edu/ark:/67531/metadc891288/m1/3/: accessed April 25, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.