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Title: Evaluating Nuclear Data and their Uncertainties

Authors:
 [1]
  1. Los Alamos National Laboratory
Publication Date:
Research Org.:
Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1415357
Report Number(s):
LA-UR-17-31373
DOE Contract Number:
AC52-06NA25396
Resource Type:
Conference
Resource Relation:
Conference: 4th International Workshop on Nuclear Data Covariances ; 2017-10-02 - 2017-10-06 ; Aix-en-Provence, France
Country of Publication:
United States
Language:
English

Citation Formats

Talou, Patrick. Evaluating Nuclear Data and their Uncertainties. United States: N. p., 2017. Web.
Talou, Patrick. Evaluating Nuclear Data and their Uncertainties. United States.
Talou, Patrick. 2017. "Evaluating Nuclear Data and their Uncertainties". United States. doi:. https://www.osti.gov/servlets/purl/1415357.
@article{osti_1415357,
title = {Evaluating Nuclear Data and their Uncertainties},
author = {Talou, Patrick},
abstractNote = {},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = 2017,
month =
}

Conference:
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  • The use is demonstrated of the newly developed ECN-SUSD sensitivity/uncertainty code system. With ECN-SUSD it is possible to calculate uncertainties in response parameters in fixed source calculations due to cross section uncertainties (using MF33) as well as to uncertainties in angular distributions (using MF34). It is shown that the latter contribution, which is generally neglected because of the lack of MF34- data in modem evaluations (except for EFF), is large in fusion reactor shielding calculations.
  • The objectives of this paper are threefold: (1) demonstrate the economic impact of present nuclear data uncertainties on exceeding and/or falling short of target design performance characteristics of fusion reactor`s component (e.g. bulk shield, breeding blanket, ... etc.), (2) quantify the uncertainties arising from the approximations embedded in the calculational methods used (e.g. discrete ordinates, Monte Carlo), and (3) describe an approach to estimate the required correction/safety factors that designers can use in order to ascertain that uncertainties in the calculated nuclear responses that are attributed, not only to uncertainties in nuclear data, but also to other sources, are covered,more » based al experiments.« less
  • During the investigation of various surplus fissile material disposition proposals, uncertainties in the data of SiO{sub 2}/Pu mixtures were discovered. These uncertainties were detected for Si/Pu ratios ranging from approximately 20:1 to 200:1. Additionally, it has been reported that metal/U{sup 235} mixtures also have data uncertainties. These problems with large data uncertainties are typically intermediate spectrum problems, i.e. problems which are dominated by scattering and fissions occurring in the energy range of 10 eV to 1 MeV. ANSI/ANS-8.1-1983 states that the ``bias shall be established by correlating the results of criticality experiments with the results obtained for these same systemsmore » by the method being validated``. There is however, a definite lack of critical experiments with an intermediate neutron spectrum. We have identified two potential areas from which these uncertainties may arise. The first potential source of uncertainty in the nuclear data is due to fact that the cross-sections of the fissile material have not been tested in an intermediate energy spectrum. The second potential source of uncertainty is that the non-fissile material in the mixture may not have been appropriately tested in a critical experiment. To provide this benchmark data a critical experiment is necessary.« less