Validation of multigroup neutron cross sections for the Advanced Neutron Source against the FOEHN critical experimental measurements
Conference
·
OSTI ID:10143165
The FOEHN critical experiments were analyzed to validate the use of multigroup cross sections in the design of the Advanced Neutron Source. Eleven critical configurations were evaluated using the KENO, DORT, and VENTURE neutronics codes. Eigenvalue and power density profiles were computed and show very good agreement with measured values.
- Research Organization:
- Oak Ridge National Lab., TN (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 10143165
- Report Number(s):
- CONF-940407-18; ON: DE94010121; TRN: 94:008581
- Resource Relation:
- Conference: Topical meeting on advances in reactor physics,Knoxville, TN (United States),11-14 Apr 1994; Other Information: PBD: [1994]
- Country of Publication:
- United States
- Language:
- English
Similar Records
Validation of multigroup neutron cross sections and calculational methods for the advanced neutron source against the FOEHN critical experiments measurements
Advanced Neutron Source Cross Section Libraries (ANSL-V): ENDF/B-V based multigroup cross-section libraries for advanced neutron source (ANS) reactor studies
Recent Validation Experience with Multigroup Cross-Section Libraries and SCALE
Technical Report
·
Mon May 01 00:00:00 EDT 1995
·
OSTI ID:10143165
Advanced Neutron Source Cross Section Libraries (ANSL-V): ENDF/B-V based multigroup cross-section libraries for advanced neutron source (ANS) reactor studies
Technical Report
·
Sat Sep 01 00:00:00 EDT 1990
·
OSTI ID:10143165
+6 more
Recent Validation Experience with Multigroup Cross-Section Libraries and SCALE
Conference
·
Sun Sep 17 00:00:00 EDT 1995
·
OSTI ID:10143165
+2 more
Related Subjects
07 ISOTOPES AND RADIATION SOURCES
22 GENERAL STUDIES OF NUCLEAR REACTORS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
MULTIGROUP THEORY
CROSS SECTIONS
NEUTRON SOURCE FACILITIES
VALIDATION
DESIGN
POWER DENSITY
MONTE CARLO METHOD
SHIELDING
070201
220100
663610
DESIGN, FABRICATION, AND OPERATION
THEORY AND CALCULATION
NEUTRON PHYSICS
22 GENERAL STUDIES OF NUCLEAR REACTORS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
MULTIGROUP THEORY
CROSS SECTIONS
NEUTRON SOURCE FACILITIES
VALIDATION
DESIGN
POWER DENSITY
MONTE CARLO METHOD
SHIELDING
070201
220100
663610
DESIGN, FABRICATION, AND OPERATION
THEORY AND CALCULATION
NEUTRON PHYSICS