Analysis of the PROFIL and PROFIL-2 Sample Irradiation Experiments in Phénix for JEFF-3.1 Nuclear Data Validation

Tommasi, J.; Noguère, G.

doi:10.13182/nse160-232

Cited by 27 publications

(32 citation statements)

References 2 publications

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“…During the analysis, 9) a discrepancy was found between the fluence predicted from the 148 Nd buildup in the 235 U samples and the fluence monitored using the 235 U/ 238 U concentration ratio (mostly sensitive to 235 U fission) and the 236 U/ 235 U ratio (mostly sensitive to 235 U capture). Further- more, the fluence predicted from the buildup of a given Nd isotope would drift significantly according to its mass number (from A ¼ 143 to 150).…”

Section: Results For Separate Sample Irradiationsmentioning

confidence: 90%

JEFF-3.1.1 Nuclear Data Validation for Sodium Fast Reactors

Lebrat

Tommasi

Archier

et al. 2011

Journal of Nuclear Science and Technology

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The JEFF-3.1.1 Nuclear Data Library is the latest version of the Joint Evaluated Fission and Fusion Library. We present the status of the validation of this library using the Monte Carlo Code TRIPOLI 4.5 and the deterministic code package ERANOS 2.2 for fast reactor calculations. For this purpose, we reanalyze a selected set of integral experiments performed in the MASURCA mock-up (CEA/ CADARACHE), in the ZPPR mock-up at ANL (USA), and in the SUPERPHENIX Power Reactor. Furthermore, we also present the analysis of pure sample irradiation experiments PROFIL and PROFIL-2 performed in the PHENIX reactor, as this kind of experiment provides a direct feedback on nuclear capture data. We observe good performances of these calculation tools for criticality calculations and fuel inventory prediction. From this validation work, some required improvements on nuclear data are highlighted, as well as the need for new specific integral experiments. The main trends observed are the following:-Reactivity of clean and fresh cores: the results obtained with JEFF-3.1.1 are consistent with those obtained using JEFF-3.1 within 80 pcm, but there is an overestimation of the calculated reactivity of all the experiments between 40 and 800 pcm depending on the spectrum hardness (Pu content) and fuel composition, the discrepancy being larger in hard spectra. :35); impact of the trends observed on the individual fission products put in PROFIL and PROFIL-2 is % 4% on the part of Á burnup due to fission products.

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Section: Results For Separate Sample Irradiationsmentioning

confidence: 90%

JEFF-3.1.1 Nuclear Data Validation for Sodium Fast Reactors

Lebrat

Tommasi

Archier

et al. 2011

Journal of Nuclear Science and Technology

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“…The principle of the experimental setup is briefly described below. More information can be found in previous papers [8,9].…”

Section: Description Of the Profil-1 And Profil-2 Programsmentioning

confidence: 99%

“…Previous interpretations of the PROFIL-1, PROFIL-2A and PROFIL-2B integral experiments carried out in the PHENIX reactor (CEA Marcoule, France) with the ERANOS code [6,7] in association with the evaluated nuclear data library JEFF-3.0 and JEFF-3.1 showed some significant discrepancies for the cumulative fission yields of several Neodymium isotopes for the fast fission of 235 U [8,9]. The average calculated-to-experimental ratios C/E associated to the Neodymium produced by fission in several samples are gathered in Figure 1.…”

Section: Introductionmentioning

confidence: 99%

Measurements of the effective cumulative fission yields of¹⁴³Nd,¹⁴⁵Nd,¹⁴⁶Nd,¹⁴⁸Nd and¹⁵⁰Nd for²³⁵U in the PHENIX fast reactor

Privas

Noguère

Tommasi

et al. 2016

EPJ Nuclear Sci. Technol.

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Abstract. The effective Neodymium cumulative fission yields for 235 U have been measured in the fast reactor PHENIX relatively to the 235 U fission cross-section. The data were derived from isotope-ratio measurements obtained in the frame of the PROFIL-1, PROFIL-2A and PROFIL-2B programs. The interpretations of the experimental programs were performed with the ERANOS code in association with the Joint Evaluated Fission and Fusion library JEFF-3.1. Nd were 5.61%, 3.70%, 2.83%, 1.64% and 0.66%, respectively. The relative uncertainties attached to each of the cumulative fission yields lie between 2.1% and 2.4%. The main source of uncertainty is due to the fluence scaling procedure (<2%). The uncertainties on the Neodymium capture cross-sections provide a contribution lower than 1%. The energy dependence of the fission yields was studied with the GEF code from the thermal energy to 20 MeV. Neutron spectrum average corrections, deduced from GEF calculations, were applied to our effective fission yields with the aim of estimating fission yields at 400 keV and 500 keV, as given in the International Evaluated Nuclear Data Files (JEFF, ENDF/B and JENDL). The neutron spectrum average correction calculated for the PROFIL results remains lower than 1.5%.

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“…The 242 Pu was chosen for assimilation as an example of a minor actinide for which there are clean irradiation experiments, PROFIL-1, PROFIL-2 [33,34], and COSMO. The irradiation experiments are relatively clean when compared to k eff experiments, which imply transport calculations and often involve various materials.…”

Section: Pumentioning

confidence: 99%

Use of Covariances in a Consistent Data Assimilation for Improvement of Basic Nuclear Parameters in Nuclear Reactor Applications: From Meters to Femtometers

Herman¹,

Hoblit²,

Palumbo³

et al. 2013

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Analysis of the PROFIL and PROFIL-2 Sample Irradiation Experiments in Phénix for JEFF-3.1 Nuclear Data Validation

Cited by 27 publications

References 2 publications

JEFF-3.1.1 Nuclear Data Validation for Sodium Fast Reactors

JEFF-3.1.1 Nuclear Data Validation for Sodium Fast Reactors

Measurements of the effective cumulative fission yields of¹⁴³Nd,¹⁴⁵Nd,¹⁴⁶Nd,¹⁴⁸Nd and¹⁵⁰Nd for²³⁵U in the PHENIX fast reactor

Use of Covariances in a Consistent Data Assimilation for Improvement of Basic Nuclear Parameters in Nuclear Reactor Applications: From Meters to Femtometers

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Analysis of the PROFIL and PROFIL-2 Sample Irradiation Experiments in Phénix for JEFF-3.1 Nuclear Data Validation

Cited by 27 publications

References 2 publications

JEFF-3.1.1 Nuclear Data Validation for Sodium Fast Reactors

JEFF-3.1.1 Nuclear Data Validation for Sodium Fast Reactors

Measurements of the effective cumulative fission yields of143Nd,145Nd,146Nd,148Nd and150Nd for235U in the PHENIX fast reactor

Use of Covariances in a Consistent Data Assimilation for Improvement of Basic Nuclear Parameters in Nuclear Reactor Applications: From Meters to Femtometers

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Measurements of the effective cumulative fission yields of¹⁴³Nd,¹⁴⁵Nd,¹⁴⁶Nd,¹⁴⁸Nd and¹⁵⁰Nd for²³⁵U in the PHENIX fast reactor