Published 1980 | Version v1
Report Restricted

Status of CINDER and ENDF/B-V based libraries for transmutation calculations

Creators

Description

The CINDER codes and their data libraries are described, and their range of calculational capabilities are described using documented applications. The importance of ENDF/B data and the features of the ENDF/B-IV and ENDF/B-V fission-product and actinide data files are emphasized. The actinide decay data of ENDF/B-V, augmented by additional data from available sources, are used to produce average decay energy values and neutron source values from sponteneous fission, (α,n) and delayed neutron emission for 144 actinide nuclides that are formed in reactor fuel. The status and characteristics of the CINDER-2 code is described, along with a brief description of more well known code versions; a review of the status of new ENDF/B-V based libraries for all versions is presented

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS., PC A03/MF A01.

Files

Restricted

The record is publicly accessible, but files are restricted to users with access.

Additional details

Publishing Information

Imprint Pagination
26 p.
Report number
LA-UR--80-2107

Conference

Title
International conference on nuclear waste transmutation.
Dates
22 - 24 Jul 1980.
Place
Austin, TX, USA.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
11571322
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BURNUP; COMPUTER CALCULATIONS; FISSION PRODUCTS; FUEL ELEMENTS; NUCLEAR DATA COLLECTIONS; PERFORMANCE; THERMAL REACTORS
Descriptors DEC
ISOTOPES; RADIOACTIVE MATERIALS; REACTOR COMPONENTS; REACTORS

Optional Information

Secondary number(s)
CONF-800743--6.