Published November 1989
| Version v1
Journal article
ENDF/B-VI [Evaluated Nuclear Data File] radioactive decay and yield libraries
- 1. Los Alamos National Laboratory, NM (USA)
- 2. Westinghouse Hanford Company, Richland, WA (USA)
- 3. Idaho National Engineering Laboratory, Idaho Falls, ID (USA)
Description
The ENDF/B-VI [Evaluated Nuclear Data File] library will contain sublibraries of all radioactive decay data and fission product yields. These libraries will continue to contain error files. Reaction cross sections (neutron and charged particle) for materials and individual nuclides will be contained in other libraries. There are very few new reaction cross-section evaluations in the range of fission products and actinides. However, evaluators did pay special attention to certain activation reactions
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 60
- Series
- Trans. Am. Nucl. Soc.
- Journal Page Range
- 614-616
- ISSN
- 0003-018X
- CODEN
- TANSA
Conference
- Title
- Winter meeting of the American Nuclear Society (ANS) and nuclear power and technology exhibit.
- Dates
- 26-30 Nov 1989.
- Place
- San Francisco, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22085414
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S73: NUCLEAR PHYSICS AND RADIATION PHYSICS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- ACTINIDES; CROSS SECTIONS; DATA BASE MANAGEMENT; DECAY; DOCUMENTATION; EVALUATED DATA; FISSION PRODUCTS; FISSION YIELD; GROUP THEORY; NEUTRON REACTIONS; NUCLEAR DATA COLLECTIONS; NUCLEAR REACTION YIELD; RADIOISOTOPES; REACTOR PHYSICS
- Descriptors DEC
- BARYON REACTIONS; DATA; ELEMENTS; HADRON REACTIONS; INFORMATION; ISOTOPES; MANAGEMENT; MATERIALS; MATHEMATICS; METALS; NUCLEAR REACTIONS; NUCLEON REACTIONS; NUMERICAL DATA; RADIOACTIVE MATERIALS
Optional Information
- Secondary number(s)
- CONF-891103--.