Published November 1992 | Version v1
Report Open

Specifications for the development of BUGLE-93: An ENDF/B-VI multigroup cross section library for LWR shielding and pressure vessel dosimetry

Creators

Description

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

Availability note (English)

MF available from INIS under the Report Number; OSTI as DE93004028; NTIS; INIS; US Govt. Printing Office Dep.

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Additional details

Publishing Information

Imprint Pagination
31 p.
Report number
ORNL/TM--12230

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
24027176
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
Descriptors DEI
BWR TYPE REACTORS; CROSS SECTIONS; DATA BASE MANAGEMENT; DOSIMETRY; PWR TYPE REACTORS; RADIATION TRANSPORT; REACTOR PHYSICS; REACTOR SAFETY; REACTOR VESSELS; SHIELDING; SPECIFICATIONS
Descriptors DEC
CONTAINERS; ENRICHED URANIUM REACTORS; MANAGEMENT; POWER REACTORS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Contract/Grant/Project number
Contract AC05-84OR21400
Funding organization
Nuclear Regulatory Commission, Washington, DC (United States).