On the processing of JEFF-3.2 neutron data library with AMPX 6.2 for its use with the SCALE tool suite

C. J. Díez, F. Michel-Sendis, O. Cabellos, D. Wiarda, M. E. Dunn

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

Abstract

New processing capabilities are under development at the NEA Data Bank (DB) that aim to provide enlarged and enhanced nuclear data services to member countries in the framework of processing, verification and benchmarking of evaluated nuclear data. Within the context of the Joint Evaluated Fission and Fusion Nuclear Data Library Project (JEFF), we undertake to generate, with the latest version of AMPX processing code, a JEFF-3.2 incident-neutron nuclear data application library for the SCALE tool suite. In this paper we describe the requirements, in terms of nuclear data content, for new data to be considered and used in the SCALE tool suite. An overview of how to process and prepare JEFF-3.2 incident-neutron data with AMPX for its application in SCALE neutron transport codes is given. The resulting library is verified and tested at differential and integral level by comparing the performance of JEFF-3.2 in AMPX format with other processing and transport codes.

Original languageEnglish
Title of host publicationWONDER 2015 - 4th International Workshop on Nuclear Data Evaluation for Reactor Applications
EditorsOlivier Serot
PublisherEDP Sciences
ISBN (Electronic)9782759819706
DOIs
StatePublished - Mar 15 2016
Event4th International Workshop on Nuclear Data Evaluation for Reactor Applications, WONDER 2015 - Aix-en-Provence, France
Duration: Oct 5 2015Oct 8 2015

Publication series

NameEPJ Web of Conferences
Volume111
ISSN (Print)2101-6275
ISSN (Electronic)2100-014X

Conference

Conference4th International Workshop on Nuclear Data Evaluation for Reactor Applications, WONDER 2015
Country/TerritoryFrance
CityAix-en-Provence
Period10/5/1510/8/15

Bibliographical note

Publisher Copyright:
© Owned by the authors, published by EDP Sciences, 2016.

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