AMPX: A modern cross section processing system for generating nuclear data libraries

D. Wiarda, M. L. Williams, C. Celik, M. E. Dunn

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

8 Scopus citations

Abstract

Nuclear data libraries are essential for nuclear analysis code systems like SCALE. AMPX has been continuously developed since the early 1970s and is used to generate these data libraries for SCALE. Recently, Oak Ridge National Laboratory (ORNL) initiated a major modernization effort to position AMPX for continued development and deployment on modern computing platforms. An important step toward modernization has been to merge AMPX under the SCALE continuous integration (CI) development framework. As a result, AMPX is now developed under the SCALE software quality assurance plan, providing increased confidence in the quality of data libraries developed and deployed by AMPX. This merge allowed us to develop novel methods to generate self-shielding factors that combine SCALE's resonance self-shielding capabilities with the AMPX library-generation capabilities. AMPX processes Evaluated Nuclear Data Format (ENDF/B) files. The ENDF community is working to develop a more modern format that will replace the existing ENDF/B format. Due to strict space and memory requirements when AMPX was first developed, the original AMPX processing and reading of ENDF data were tightly integrated. On newer computer systems, this is no longer necessary. Now there is a separation between reading and processing which allows for simultaneous support of current and new ENDF formats. As a result, AMPX is positioned to adopt any new ENDF format when available. For end users, the modernization effort has resulted in improved processing capabilities for generating nuclear data libraries. The objective of the paper is to document the latest AMPX cross-section processing capabilities and provide the current status of the AMPX modernization effort.

Original languageEnglish
Title of host publicationICNC 2015 - International Conference on Nuclear Criticality Safety
PublisherAmerican Nuclear Society
Pages1241-1254
Number of pages14
ISBN (Electronic)9780894487231
StatePublished - 2015
Event2015 International Conference on Nuclear Criticality Safety, ICNC 2015 - Charlotte, United States
Duration: Sep 13 2015Sep 17 2015

Publication series

NameICNC 2015 - International Conference on Nuclear Criticality Safety

Conference

Conference2015 International Conference on Nuclear Criticality Safety, ICNC 2015
Country/TerritoryUnited States
CityCharlotte
Period09/13/1509/17/15

Keywords

  • Covariance matrices
  • Cross section processing
  • Shielding factors

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