Advanced Neutron Source Cross Section Libraries (ANSL-V): ENDF/B-V based multigroup cross-section libraries for advanced neutron source (ANS) reactor studies
Pseudo-problem-independent, multigroup cross-section libraries were generated to support Advanced Neutron Source (ANS) Reactor design studies. The ANS is a proposed reactor which would be fueled with highly enriched uranium and cooled with heavy water. The libraries, designated ANSL-V (Advanced Neutron Source Cross Section Libraries based on ENDF/B-V), are data bases in AMPX master format for subsequent generation of problem-dependent cross-sections for use with codes such as KENO, ANISN, XSDRNPM, VENTURE, DOT, DORT, TORT, and MORSE. Included in ANSL-V are 99-group and 39-group neutron, 39-neutron-group 44-gamma-ray-group secondary gamma-ray production (SGRP), 44-group gamma-ray interaction (GRI), and coupled, 39-neutron group 44-gamma-ray group (CNG) cross-section libraries. The neutron and SGRP libraries were generated primarily from ENDF/B-V data; the GRI library was generated from DLC-99/HUGO data, which is recognized as the ENDF/B-V photon interaction data. Modules from the AMPX and NJOY systems were used to process the multigroup data. Validity of selected data from the fine- and broad-group neutron libraries was satisfactorily tested in performance parameter calculations.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- DOE/ER
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6502303
- Report Number(s):
- ORNL-6618; ON: DE91000545; TRN: 91-000693
- Country of Publication:
- United States
- Language:
- English
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ANSL-V: ENDF/B-V based multigroup cross-section libraries for Advanced Neutron Source (ANS) reactor studies
ANSL-V: ENDF/B-V based multigroup cross-section libraries for Advanced Neutron Source (ANS) reactor studies. Supplement 1
Related Subjects
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
NEUTRON REACTIONS
NUCLEAR DATA COLLECTIONS
NEUTRON SOURCES
DESIGN
PHOTONUCLEAR REACTIONS
BENCHMARKS
CALCULATION METHODS
COMPUTER ARCHITECTURE
CROSS SECTIONS
DATA BASE MANAGEMENT
LIBRARIES
BARYON REACTIONS
HADRON REACTIONS
MANAGEMENT
NUCLEAR REACTIONS
NUCLEON REACTIONS
PARTICLE SOURCES
RADIATION SOURCES
070201* - Radiation Sources- Design
Fabrication & Operation
651000 - Nuclear Physics