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., TN (United States)
- Sponsoring Organization:
- NRC; 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
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990300 -- Information Handling
BWR TYPE REACTORS
CONTAINERS
CROSS SECTIONS
DATA BASE MANAGEMENT
DOSIMETRY
ENRICHED URANIUM REACTORS
MANAGEMENT
PHYSICS
POWER REACTORS
PWR TYPE REACTORS
RADIATION TRANSPORT
REACTOR PHYSICS
REACTOR SAFETY
REACTOR VESSELS
REACTORS
SAFETY
SHIELDING
SPECIFICATIONS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990300 -- Information Handling
BWR TYPE REACTORS
CONTAINERS
CROSS SECTIONS
DATA BASE MANAGEMENT
DOSIMETRY
ENRICHED URANIUM REACTORS
MANAGEMENT
PHYSICS
POWER REACTORS
PWR TYPE REACTORS
RADIATION TRANSPORT
REACTOR PHYSICS
REACTOR SAFETY
REACTOR VESSELS
REACTORS
SAFETY
SHIELDING
SPECIFICATIONS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS