Published 1992 | Version v1
Journal article

The decay data in ENDF/B: History and current status

Creators

  • 1. Idaho National Engineering Lab., Idaho Falls (United States)

Description

In recognition of the importance of radioactive-nuclide decay data for a variety of reactor-related applications, the scope of the Evaluated Nuclear Data File/B (ENDF/B) was expanded in 1973 to include such information. The impetus for this expansion was provided by the need for a common base of evaluated decay data for input to the computer codes developed to carry out 'summation-type' calculations of the fission product decay-heat source term in nuclear reactors. In its original formulation, this data base was called the Fission Product File, and an ad hoc group, the Decay Heat Task Force, was set up under the Fission Product Subcommittee of the Cross Sections Evaluation Working Group to prepare it. This group began work on the project early in 1973. The ENDF/B data file is profiled from its formation through various evaluation, developments, and changes to the present Version VI

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society
Journal Volume
66
Journal Page Range
p. 151.
ISSN
0003-018X
CODEN
TANSAO

Conference

Title
past, present, and future.
Acronym
Joint American Nuclear Society (ANS)/European Nuclear Society (ENS) international meeting on fifty years of controlled nuclear chain reaction
Dates
15-20 Nov 1992.
Place
Chicago, IL (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
24050527
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
COMPUTER CODES; CROSS SECTIONS; EVALUATED DATA; HISTORICAL ASPECTS; NUCLEAR DATA COLLECTIONS; NUCLEAR DECAY
Descriptors DEC
DATA; DECAY; INFORMATION; NUMERICAL DATA

Optional Information

Secondary number(s)
CONF-921102--.