RISS 검색 - 국내학술지논문

1
^(23)Na Evaluation with CONRAD for Fast Reactor Applications

P. Archier,C. De Saint Jean,G. Noguere,J. Tommasi 한국물리학회 2011 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.59 No.23
For sodium-cooled fast reactor (SFR), sodium void reactivity effect (SVRE) is a key parameter beingparticularly sensitive to sodium nuclear data. Present evaluations of ^(23)Na available in the major libraries(JEFF-3.1.1, ENDF/B-VII.0, JENDL-3.3 and TENDL-2009) exhibit large discrepancies especially in the high energy range.These differences translate into uncertainties in the prediction of integral parameters and, in fine, into expensivesafety margins.A new evaluation of sodium nuclear data is currently under way using the CONRAD code at CEA Cadarache. Severalextensive developments have been made to implement ECIS and TALYS codes interface into CONRAD for optical and statisticalmodel calculations. The modeling of the ^(23)Na cross-sections and angular distributions are based on a robust andinnovative methodology, which takes into account both differential and integral experiments in the evaluation process.First, we show the impact of sodium nuclear data from different libraries on SVRE in MASURCA and ZPPR experiments. Themethodology using CONRAD to produce an ajusted ^(23)Na evaluation, based on differential and integral experiments, isdescribed. Finally, the preliminary results obtained with this methodology is presented.
2
Fission Product Cross Section Evaluations using Integral Experiments

G. Noguere,P. Archier,B. Habert,C. De Saint Jean,D. Bernard,J. Tommasi 한국물리학회 2011 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.59 No.23
The focus of this evaluation work is the analysis of the resolved and unresolved resonance ranges of the main fission products of interest for the nuclear applications. The strength and the originality of the study are the simultaneous analysis of differential and integral data with the nuclear data code CONRAD. The latter code has been designed to account for results provided by the deterministic code systems APOLLO2 and ERANOS2. Integral trends used in this work were measured at the MINERVE facility (CEA, DEN Cadarache) with the oscillation technique and at the PHENIX facility (CEA,DEN Marcoule). Performances of the CONRAD code are illustrated with model parameters (resonance parameters, l-dependent average parameters, optical model parameters) obtained for ^(155)Gd and ^(151)Sm.
3
Uncertainty Evaluation of Nuclear Reaction Model Parameters using Integral and Microscopic Measurements with the CONRAD Code

C. De Saint Jean,B. Habert,P. Archier,G. Noguere,D. Bernard,J. Tommasi,P. Blaise 한국물리학회 2011 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.59 No.23
In the [eV;MeV] energy range, modeling of the neutron induced reactions are based on nuclear reaction models having parameters. Estimation of covariances on cross sections or on nuclear reaction model parameters is a recurrent puzzle in nuclear data evaluation. Major breakthrough were asked by nuclear reactor physicists to assess proper uncertainties to be used in applications. In this paper, mathematical methods will be presented to explain how to treat all types of uncertainties (including experimental ones, statistical and systematic ones) and propagate them to nuclear reaction model parameters or cross sections. Furthermore, one major drawback found by reactor physicists is the fact that integral or analytical experiments (reactor mock-up or simple integral experiment, e.g., ICSBEP,...) were not taken into account sufficiently soon in the evaluation process to remove discrepancies. In this paper, we will thus describe a clear mathematical framework to take into account properly this kind of information.
4
Statistical Analysis of a Set of Actinide Resolved Resonance Parameters with CONRAD Code

O. Litaize,C. De Saint Jean,G. Noguere,P. Archier 한국물리학회 2011 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.59 No.23
A resolved resonance parameters set can be obtained with Conrad and analyzed in the same code in order to determine the average parameters used as input for the unresolved resonance energy range. The statistical analysis performed to estimate the mean level spacing or the reduced neutron width is respectively based on the Wigner and Porter-Thomas laws. In addition, Dyson F-statistic and Metha-Dyson Δ_3 statistic tests are performed to detect missing or spurious levels. The case of U-238 is presented here as an example. In addition of JEFF-3.1 and ENDF/B-VII.0 libraries, a simple data test is shown to highlight the impact of resonance orbital momentum assignment in this analysis.

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