Specifications for the development of BUGLE-93: An ENDF/B-VI multigroup cross section library for LWR shielding and pressure vessel dosimetry
This report discusses specifications which have been developed for a new multigroup cross section library based on ENDF/B-VI data for light water reactor shielding and reactor pressure vessel dosimetry applications. The resulting broad-group library and an intermediate fine-group library are defined by the specifications provided in this report. Processing ENDF/B-VI into multigroup format for use in radiation transport codes will provide radiation shielding analysts with the most currently available nuclear data. it is expected that the general nature of the specifications will be useful in other applications such as reactor physics.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USNRC; Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6934139
- Report Number(s):
- ORNL/TM-12230; ON: DE93004028
- Country of Publication:
- United States
- Language:
- English
Similar Records
BUGLE-93 (ENDF/B-VI) cross-section library data testing using shielding benchmarks
BUGLE-96: A Revised Multigroup Cross Section Library for LWR Applications Based on ENDF/B-VI Release 3
Production and Testing of the VITAMIN-B6 Fine Group and the BUGLE-93 Broad-Group Neutron/Photon Cross-Section Libraries Derived from ENDF/B-VI Nuclear Data
Conference
·
Wed Jun 01 00:00:00 EDT 1994
·
OSTI ID:6934139
BUGLE-96: A Revised Multigroup Cross Section Library for LWR Applications Based on ENDF/B-VI Release 3
Conference
·
Sun Apr 21 00:00:00 EDT 1996
·
OSTI ID:6934139
+1 more
Production and Testing of the VITAMIN-B6 Fine Group and the BUGLE-93 Broad-Group Neutron/Photon Cross-Section Libraries Derived from ENDF/B-VI Nuclear Data
Technical Report
·
Thu Apr 19 00:00:00 EDT 2001
·
OSTI ID:6934139
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
BWR TYPE REACTORS
SHIELDING
CROSS SECTIONS
DATA BASE MANAGEMENT
PWR TYPE REACTORS
DOSIMETRY
RADIATION TRANSPORT
REACTOR PHYSICS
REACTOR SAFETY
REACTOR VESSELS
SPECIFICATIONS
CONTAINERS
ENRICHED URANIUM REACTORS
MANAGEMENT
PHYSICS
POWER REACTORS
REACTORS
SAFETY
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
990300 - Information Handling
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
BWR TYPE REACTORS
SHIELDING
CROSS SECTIONS
DATA BASE MANAGEMENT
PWR TYPE REACTORS
DOSIMETRY
RADIATION TRANSPORT
REACTOR PHYSICS
REACTOR SAFETY
REACTOR VESSELS
SPECIFICATIONS
CONTAINERS
ENRICHED URANIUM REACTORS
MANAGEMENT
PHYSICS
POWER REACTORS
REACTORS
SAFETY
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
990300 - Information Handling