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Title: ANSL-V: ENDF/B-V based multigroup cross-section libraries for Advanced Neutron Source (ANS) reactor studies

Multigroup P3 neutron, P0-P3 secondary gamma ray production (SGRP), and P6 gamma ray interaction (GRI) cross section libraries have been generated to support design work on the Advanced Neutron Source (ANS) reactor. The libraries, designated ANSL-V (Advanced Neutron Source Cross-Section Libraries), are data bases in a format suitable for subsequent generation of problem dependent cross sections. The ANSL-V libraries are available on magnetic tape from the Radiation Shielding Information Center at Oak Ridge National Laboratory.
Authors:
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Publication Date:
OSTI Identifier:
6113574
Report Number(s):
CONF-871101-33
ON: DE87011675
DOE Contract Number:
AC05-84OR21400
Resource Type:
Conference
Resource Relation:
Conference: California State Air Resources Board, Los Angeles, CA, USA, 15 Nov 1987; Other Information: Portions of this document are illegible in microfiche products
Research Org:
Oak Ridge National Lab., TN (USA)
Country of Publication:
United States
Language:
English
Subject:
73 NUCLEAR PHYSICS AND RADIATION PHYSICS; NEUTRON SOURCE FACILITIES; DESIGN; EVALUATED DATA; NUCLEAR DATA COLLECTIONS; CROSS SECTIONS; DATA; INFORMATION; NUMERICAL DATA 654000* -- Radiation & Shielding Physics