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Program - Brookhaven National Laboratory

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Prompt fission neutron spectra (PFNS) have proven to have a significant effect in some critical benchmarks,<br />

in some cases as important as cross-section uncertainties. Therefore, a precise determination of<br />

uncertainties in PFNS is largely desired. Existing PFNS evaluations in nuclear data libraries relied so far<br />

almost exclusively on the Los Alamos model [1]. However, deviations of evaluated data from available<br />

experiments have been noticed at both low and high neutron emission energies. Existing experimental<br />

database for PFNS in EXFOR has been revisited and covariance information of selected experimental sets<br />

have been proposed [2]. New experimental measurements have been recently published. The use of the<br />

Bayesian Kalman filter has successfully proven to be a powerful tool to improve and refine evaluations by<br />

fitting cross-section data. It therefore represents a natural path for fitting fission spectra using all available<br />

experimental data. The goal is to derive realistic values for PFNS model parameters and corresponding<br />

uncertainties and correlations. The present work describes the effort of integrating Kalman and EMPIRE<br />

codes in such a way to allow for parameter fitting of PFNS models. The first results are shown for the<br />

major actinides for two different models (Kornilov [3] and Los Alamos [1]). This represents the first step<br />

towards consistent fitting of both cross-section and fission spectra data considering both microscopic and<br />

integral experimental data.<br />

[1] D. G. Madland and J. R. Nix, Nucl. Sci. Eng., 81, 213 (1982) [2] IAEA Summary Report, Consultant’s<br />

Meeting, INDC(NDS)-0540, 2008 [3] N. V. Kornilov, A. B. Kagalenko, and F.-J. Hambsch, Physics of<br />

Atomic Nuclei, 62, 173 (1999)<br />

PR 112<br />

Study of the Channel Spin Dependence of nu for Pu-239<br />

G. Noguere, O. Serot, E. Fort, C. De Saint Jean, CEA, DEN, DER, SPRC, Cadarache, F-13108<br />

Saint-Paul-lez-Durance, France. L. Leal, Oak Ridge <strong>National</strong> <strong>Laboratory</strong>, P.O.Box 2008, Oak Ridge, TN,<br />

USA, 37831.<br />

The description of fluctuations of the various fission quantities in the resonance range, such as the number<br />

of prompt neutron emitted per fission, is a longstanding problem difficult to solve experimentally. For<br />

Pu-239, the fluctuations in nu have been widely accepted since the pioneer works in the late 60. However,<br />

only two data sets reported by Frehaut et al. (1973) and Gwin et al. (1984) were used to investigate such<br />

fluctuations below few ten’s of eV. A phenomenological description proposed by Shackleton (1974) was<br />

already applied on Pu-239 by Fort in 1988. The formalism takes into account the channel spin dependence<br />

(s=0 and s=1) for the (n,f) and (n,gf) processes. In practice, the fission cross section has to be decomposed<br />

in four components. Effects of the two-step (n,gf) process can be included as a corrective term. The weight<br />

of each component was determined using the Pu-239 resonance parameters recommended in the existing<br />

Evaluated Neutron Data File. In the present work, an improved Neutron Resonance Shape Analysis was<br />

applied. The methodology consists to extract simultaneously the resonance parameters together with<br />

the weight of each component by including in the fitting procedure all the cross section data and neutron<br />

multiplicities. Thanks to this approach, the smallest fission widths for J=1+ resonances will provide reliable<br />

partial widths for the (n,gf) reaction. Such results are crucial to validate the theoretical calculation of the<br />

partial width for the (n,gf) reaction in the J=0+ resonances. The analysis is performed with the nuclear<br />

data code CONRAD. For the prior information, we use the latest Pu-239 resonance parameters established<br />

in the frame of the WPEC/SG-34. The CONRAD results (posterior model parameters and covariance<br />

matrix) provide accurate information to adress the impact of the (n,gf) reaction on the average radiation<br />

width.<br />

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