On the processing of JEFF-3.2 neutron data library with AMPX 6.2 for its use with the SCALE tool suite
1 OECD Nuclear Energy Agency (NEA) - Data Bank, 92130, Issy-les-Moulineaux, France
2 Oak Ridge National Laboratory, Reactor and Nuclear Systems Division, 37831-6170, Oak Ridge, TN, USA
a e-mail: email@example.com
Published online: 15 March 2016
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.
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