Multilevel Formula for the Fission Process

Reich, C.W.; Moore, M. S.

doi:10.1103/physrev.111.929

Cited by 211 publications

(73 citation statements)

References 8 publications

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“…This format is unable to accommodate the effects described above, because it uses only a highly restricted form of the actual Reich-Moore formulation [3]. With LRF = 3, only one incident channel and at most two fission channels are permitted.…”

Section: Creation Of Endf Filementioning

confidence: 99%

Current status of the R-Matrix code SAMMY, with emphasis on the relationship to ENDF formats

Larson

Leal

Sayer

et al. 2007

Nd2007

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Abstract. During the last decade, advances in evaluations of neutron-induced cross sections in the resolved resonance region have surpassed the ability of the Evaluated Nuclear Data Files (ENDF) to make use of those evaluations. At the higher energies used in new evaluations, effects that in the past were deemed to be negligible are now important. There is also a great demand for including uncertainty information in ENDF files. In this paper, we describe recently approved ENDF formats to accommodate new evaluations and their implementation in SAMMY.Other new features of the SAMMY code, available in the 2006 Revision 7 release, are also described.

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Section: Creation Of Endf Filementioning

confidence: 99%

Current status of the R-Matrix code SAMMY, with emphasis on the relationship to ENDF formats

Larson

Leal

Sayer

et al. 2007

Nd2007

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“…A key point of the ReichMoore formalism is neglecting contributions from photon channels into off-diagonal elements of the level matrix [51]. In this case the collision matrix U J nc (c =n) can be presented in following way [51,52]…”

Section: Basic Formulaementioning

confidence: 99%

Evaluation of the⁹³Nb(n,γ) Reaction Cross-Section

Zolotarev

Badikov

2016

EPJ Web of Conferences

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Abstract. New evaluation of the 93 Nb(n, ) 94 Nb reaction cross-section important for retrospective reactor dosimetry was carried out. At neutron energies below 7.5 keV the evaluation is based on the experimental data. The results of measurements extracted from the EXFOR library were corrected (when necessary) to new recommended values of monitor reaction cross-sections and decay data. The resonance analysis of the 93 Nb(n, ) and the 93 Nb(n,tot) reaction cross-sections was carried out within the Reich-Moore formalism. 48 new resonances were identified as compared to the Mughabghab systematics. In the energy range from 7.5 keV to 20 MeV the evaluation is based on the experimental data and theoretical model calculations. The recommended cross-sections and their covariances in this energy range were evaluated by an approximation of the experimental and calculated values with the PADE2 code. The new evaluation provides, essentially, better agreement with the experimental data and the recommended value of the resonance integral compared to other evaluations.

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“…The use of an alternative engine can then be introduced in the tool. A genuine mathematical package will thus be developed for a better description of any general lagrangian (Bayesian, least square...) chosen for minimization and a proper treatment of experimental covariances like equation (1). The figure 6 shows an example of analysis of the average capture cross section of 177 Hf between 2 keV and 100 keV.…”

Section: Parameters Estimationmentioning

confidence: 99%

“…In the resolved resonance range, both R Matrix approximation, Reich-Moore [1] and multi-level Breit-Wigner are coded using exactly the same kind of parameters.…”

Section: Theoretical Featuresmentioning

confidence: 99%

Status of CONRAD, a nuclear reaction analysis tool

Jean

Habert

Litaize

et al. 2007

Nd2007

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Abstract. The development of a software tool (CONRAD) was initiated at CEA/Cadarache to give answers to various problems arising in the data analysis of nuclear reactions. This tool is then characterized by the handling of uncertainties from experimental values to covariance matrices for multi-group cross sections. An object oriented design was chosen allowing an easy interface with graphical tool for input/output data and being a natural framework for innovative nuclear models (Fission). The major achieved developments are a data model for describing channels, nuclear reactions, nuclear models and processes with interface to classical data formats, theoretical calculations for the resolved resonance range (Reich-Moore) and unresolved resonance range (Hauser-Feshbach, Gilbert-Cameron,...) with nuclear model parameters adjustment on experimental data sets and a Monte Carlo method based on conditional probabilities developed to calculate properly covariance matrices. The on-going developments deal with the experimental data description (covariance matrices) and the graphical user interface.

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Multilevel Formula for the Fission Process

Cited by 211 publications

References 8 publications

Current status of the R-Matrix code SAMMY, with emphasis on the relationship to ENDF formats

Current status of the R-Matrix code SAMMY, with emphasis on the relationship to ENDF formats

Evaluation of the⁹³Nb(n,γ) Reaction Cross-Section

Status of CONRAD, a nuclear reaction analysis tool

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Multilevel Formula for the Fission Process

Cited by 211 publications

References 8 publications

Current status of the R-Matrix code SAMMY, with emphasis on the relationship to ENDF formats

Current status of the R-Matrix code SAMMY, with emphasis on the relationship to ENDF formats

Evaluation of the93Nb(n,γ) Reaction Cross-Section

Status of CONRAD, a nuclear reaction analysis tool

Contact Info

Product

Resources

About

Evaluation of the⁹³Nb(n,γ) Reaction Cross-Section