Analysis of Sample and Fuel Pin Irradiation Experiments in Phénix for Basic Nuclear Data Validation

D’Angelo, A.; Cleri, Fabrizio; Marimbeau, P.; Salvatores, M.; Grouiller, Jean-Paul

doi:10.13182/nse90-a19189

Cited by 19 publications

(10 citation statements)

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“…The large volume of irradiated samples makes Monte Carlo calculations much easier to obtain statistically reliable tallies. However, it is extremely difficult to obtain statistically reliable results for PROFIL-1&2 since the size of each sample is very small (~0.06 cm 3 ), and some of reactions (e.g., (n,2n), (n,3n)) are caused by very fast neutrons (5 MeV ~) which are usually not well populated. Moreover, it is not straightforward to perform variance reduction in criticality calculations.…”

Section: Evaluation Of One-group Cross Sections By Monte Carlo Methodsmentioning

confidence: 99%

“…Experimental data from the PROFIL and TRAPU irradiation experiments [3], performed at the CEA PHENIX fast reactor, provide clean and precise information on both cross section data and transmutation rates of actinides. These data are essential for the validation of the methods and data to be used in advanced fuel cycles where transmutation systems will be used to reduce the existing inventory of nuclear waste.…”

Section: Irradiation Experiments In Phenix Reactormentioning

confidence: 99%

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Report on INL Activities for Uncertainty Reduction Analysis of FY11

Plamiotti¹,

Hiruta²

2011

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SUMMARYThis report presents the status of activities performed at INL under the ARC Work Package on "Uncertainty Reduction Analyses" that has as a main goal the reduction of uncertainties associated with nuclear data on neutronic integral parameters of interest for the design of advanced fast reactors under consideration by the ARC program.First, an analysis of experiments was carried out. For both JOYO (the first Japanese fast reactor) and ZPPR-9 (a large size zero power plutonium fueled experiment performed at ANL-W in Idaho) the performance of ENDF/B-VII.0 is quite satisfying except for the sodium void configurations of ZPPR-9, but for which one has to take into account the approximation of the modeling. In fact, when one uses a more detailed model (calculations performed at ANL in a companion WP) more reasonable results are obtained.

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Section: Evaluation Of One-group Cross Sections By Monte Carlo Methodsmentioning

confidence: 99%

Section: Irradiation Experiments In Phenix Reactormentioning

confidence: 99%

Report on INL Activities for Uncertainty Reduction Analysis of FY11

Plamiotti¹,

Hiruta²

2011

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“…Experimental data from the PROFIL and TRAPU irradiation experiments [10], performed at the CEA PHENIX fast reactor, provide clean and precise information on both cross section data and transmutation rates of actinides and fission products. These data are essential for the validation of the methods and data to be used in advanced fuel cycles where transmutation systems will be used to reduce the existing inventory of nuclear waste.…”

Section: Irradiation Experiments: Profil and Trapumentioning

confidence: 99%

Consistent Data Assimilation of Isotopes: 242Pu and 105Pd

Palmiotti¹,

Hiruta²,

Salvatores³

2012

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SUMMARYIn this annual report we illustrate the methodology of the consistent data assimilation that allows to use the information coming from integral experiments for improving the basic nuclear parameters used in cross section evaluation.A series of integral experiments are analyzed using the EMPIRE evaluated files for 242Pu and 105 Pd. In particular irradiation experiments (PROFIL-1 and -2, TRAPU-1, -2 and -3) provide information about capture cross sections, and a critical configuration, COSMO, where fission spectral indexes were measured, provides information about fission cross section.The observed discrepancies between calculated and experimental results are used in conjunction with the computed sensitivity coefficients and covariance matrix for nuclear parameters in a consistent data assimilation.The results obtained by the consistent data assimilation indicate that not so large modifications on some key identified nuclear parameters allow to obtain reasonable C/E. However, for some parameters such variations are outside the range of 1 ı of their initial standard deviation. This can indicate a possible conflict between differential measurements (used to calculate the initial standard deviations) and the integral measurements used in the statistical data adjustment. Moreover, an inconsistency between the C/E of two sets of irradiation experiments (PROFIL and TRAPU) is observed for 242 Pu. This is the end of this project funded by the Nuclear Physics Program of the DOE Office of Science. We can indicate that a proof of principle has been demonstrated for a few isotopes for this innovative methodology. However, we are still far from having explored all the possibilities and made this methodology to be considered proved and robust. In particular many issues are worth further investigation:• Non-linear effects • Flexibility of nuclear parameters in describing cross sections • Multi-isotope consistent assimilation • Consistency between differential and integral experiments

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“…H, 12,13 C, 14 N, 16 O, 24,25,26 Mg, 27 Al, 28,29,30 Si, 39,41 K, 40,42,43,44,46,48 Ca, 46,47,48,49,50 196,198,199,200,201,202,204 Hg…”

mentioning

confidence: 99%

“…In preparation (66 nuclides) 2 H, 6,7 Li, 9 Be, 10,11 B, 15 N, 18 O, 19 F, 23 Na, 35,37 Cl, 35,38,40 Ar, 69,71 Ga, 70,72,73,74,76 Ge, 75 As, 74,76,77,78,80,82 Se, 89 Y, 92,94,95,96,97,98,100 Mo, 113,115 In, 181 Ta, 197 Au, 204,206,207,208 Pb, 209 Bi, 232 3 He, 6,7 Li, 9 Be, 10,11 B, 12 C, 14 N, 16 O, 19 F, 23 Na, 24 26 Mg, 27 Al, 28 30 Si, 31 P, 40,48 Ca, 46…”

mentioning

confidence: 99%

Research Activities of Japan Nuclear Data Committee in Fiscal Years of 2003 and 2004

Igashira

Watanabe

Fukahori

et al. 2007

Nihon Genshiryoku Gakkai wabun rombunshi

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This technical note summarizes research activities on nuclear data carried out by Japanese Nuclear Data Committee ( JNDC) during theˆscal years of 2003 and 2004. During this period, the nuclear dataˆles for special purposes ( JENDL HE 2004 and JENDL PD 2004) were released. Other activities are described: analysis of post nuclear fuel irradiation experiments, nuclear chart and nuclear data evaluation for astrophysics.

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Analysis of Sample and Fuel Pin Irradiation Experiments in Phénix for Basic Nuclear Data Validation

Cited by 19 publications

References 0 publications

Report on INL Activities for Uncertainty Reduction Analysis of FY11

Report on INL Activities for Uncertainty Reduction Analysis of FY11

Consistent Data Assimilation of Isotopes: 242Pu and 105Pd

Research Activities of Japan Nuclear Data Committee in Fiscal Years of 2003 and 2004

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