Evaluated Nuclear Data

Obložinský, P.; Herman, M.; Mughabghab, S.F.

doi:10.1007/978-0-387-98149-9_2

Cited by 5 publications

(6 citation statements)

References 89 publications

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“…While the STAYSL PNNL suite doesn't currently use the IRDFF library, future work will likely make use of such resources. Most of the reaction data in IRDFF below 20 MeV are identical to the data in IRDF-2002; the main difference is that IRDFF extends to 60 MeV for applications with higher energy neutron sources.…”

Section: History/backgroundmentioning

confidence: 75%

“…The first library produced was IRDF-90 [18], which was followed by an updated and expanded version called IRDF-2002 [5]. The nuclear data are derived from evaluated nuclear data libraries [19,20] including ENDF (Evaluated Nuclear Data File), JENDL (Japanese Evaluated Nuclear Data Library), and JEFF (Joint Evaluated Fission and Fusion File). However, the important distinction from general purpose evaluated nuclear data libraries is that IRDF-2002 is a special application file that combines all nuclear reactions that lead to a production of a specific isotope during an irradiation.…”

Section: History/backgroundmentioning

confidence: 99%

“…These files demonstrate the file structures and provide reference files to use for comparison to those produced with the user's installed executables. 20 …”

Section: General Notes On Installationmentioning

confidence: 99%

“…If the specified power is greater than the AVGBM value (it cannot be less than AVGBM), then it is assumed that the irradiation time is the effective full power time (otherwise the time is assumed to be the actual irradiation time). P XPROD T irr ( 19 ) AVGBM P RNF ( 20 ) If gamma-ray spectrum analysis software was used in acquiring/processing the activity measurements, then the irradiation time, T irr , and renormalization factor, RNF, are user inputs. If the user enters a RNF value that is greater than 1.0, then the irradiation time is assumed to be the effective full power time (hence the actual irradiation time, including downtime, would be RNF·T irr ).…”

Section: Calculationsmentioning

confidence: 99%

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User Guide for the STAYSL PNNL Suite of Software Tools

Greenwood

Johnson²

2013

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Executive SummaryThe STAYSL PNNL software suite provides a set of tools for working with neutron activation rates measured in a nuclear fission reactor, an accelerator-based neutron source, or any neutron field to determine the neutron flux spectrum through a generalized least-squares approach. This process is referred to as neutron spectral adjustment since the preferred approach is to use measured data to adjust neutron spectra provided by neutron physics calculations. The input data consist of the reaction rates based on measured activities, an initial estimate of the neutron flux spectrum, neutron activation cross sections and their associated uncertainties (covariances), and relevant correction factors. The output consists of the adjusted neutron flux spectrum and associated covariance matrix, which is useful for neutron dosimetry and radiation damage calculations.The software suite consists of the STAYSL PNNL, SHIELD, BCF, and NJpp Fortran codes and the SigPhi Calculator spreadsheet tool. In addition, the development of this software suite and associated data libraries used the third-party NJOY99 Fortran code. The NJOY99 and NJpp codes are used to assemble cross section and covariance input data libraries (for both SHIELD and STAYSL PNNL) from the International Reactor Dosimetry File of 2002 (IRDF-2002) developed by the Nuclear Data Section of the International Atomic Energy Agency (Vienna, Austria). The BCF, SigPhi Calculator, and SHIELD software tools are used to calculate corrected activation rates and neutron self-shielding correction factors, which are inputs to the STAYSL PNNL code.This report documents each of the software tools, describing the purpose of the software, the installation/uninstallation procedures, the required input data and run options, the type and format of output data, and details of the calculations performed by the software. Because NJOY99 is third-party software, the documentation here of that software is limited to application in the context of the STAYSL PNNL software suite and the user is referred to the NJOY99 documentation for details on general software functionality and implementation.v

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Section: History/backgroundmentioning

confidence: 75%

Section: History/backgroundmentioning

confidence: 99%

“…These files demonstrate the file structures and provide reference files to use for comparison to those produced with the user's installed executables. 20 …”

Section: General Notes On Installationmentioning

confidence: 99%

Section: Calculationsmentioning

confidence: 99%

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User Guide for the STAYSL PNNL Suite of Software Tools

Greenwood

Johnson²

2013

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“…Измерение параметров резонансов составляет предмет множества исследований. Результаты оцениваются [26][27][28] и публикуются в библиотеках ядерных данных [29]. Наиболее полные библиотеки: ENDF (Evaluated Nuclear Data Files) [30], РОСФОНД (РОСсийская библиотека Файлов Оцененных Нейтронных Данных) [31], JEF (Joined European Files) [32], JENDL (Japanies Evaluated Nuclear Data Library) [33].…”

Section: X T S F M N Elunclassified

Метод Лебеговых Моментов Для Решения Уравнения Переноса Нейтронов

Shilkov¹

2020

Матем. моделирование

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Разработан метод лебеговых моментов для моделирования эффектов обращения резонансов, резонансной самоэкранировки, блок-эффекта в спектрах нейтронов протяженных неоднородных объектов - ядерных реакторов, защит от излучений, установок для исследования вещества. Метод использует более точную процедуру осреднения по энергии нейтронов, чем осреднение в группы. Основные составляющие метода: выделение резонансной структуры нейтронных сечений с помощью разбиения шкалы энергий на ряд множеств - носителей резонансов; выполнение лебеговского осреднения сечений и тока нейтронов в пределах носителей; разложение тока нейтронов в ряд по базисным функциям, зависящим от величины нейтронных сечений. Для расчета коэффициентов разложения (лебеговых моментов) могут применяться известные методы решения уравнения переноса нейтронов.

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Theoretical cross-sectional calculation of some structural fusion material on (n, α)-induced reactions

Siddik

2019

Indian J Phys

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Evaluated Nuclear Data

Cited by 5 publications

References 89 publications

User Guide for the STAYSL PNNL Suite of Software Tools

User Guide for the STAYSL PNNL Suite of Software Tools

Метод Лебеговых Моментов Для Решения Уравнения Переноса Нейтронов

Theoretical cross-sectional calculation of some structural fusion material on (n, α)-induced reactions

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