Data processing for ENDF/B-VI (Evaluated Nuclear Data File)

Conference · Wed Nov 01 04:00:00 EST 1989 · Transactions of the American Nuclear Society; (United States)

OSTI ID:5374841

MacFarlane, R E ^[1]

---

1. Los Alamos National Laboratory, NM (USA)

The new ENDF/B-VI (Evaluated Nuclear Data File) library has improvements in both data content and data representation. These improvements should make it possible to do better calculations, but they have created problems for many existing reactor physics codes. This paper discusses some of the new features included in the ENDF-6 format and how they affect the preparation of processed data libraries. The emphasis will be on the NJOY nuclear data processing system, which is currently able to process data in the ENDF-6 format.

• OSTI ID: 5374841
• Report Number(s): CONF-891103--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 60
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
651000 -- Nuclear Physics
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
99 GENERAL AND MISCELLANEOUS
990300 -- Information Handling
ACCURACY
ACTINIDE ISO
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
ANISOTROPY
CHARGED PARTICLES
DATA
DATA BASE MANAGEMENT
DATA PROCESSING
DOCUMENTATION
EPITHERMAL REACTORS
EVALUATED DATA
EVEN-EVEN NUCLEI
EVEN-ODD NUCLEI
FAST REACTORS
GROUP THEORY
HEAVY NUCLEI
INFORMATION
INTERNAL CONVERSION RADIOISOTOPES
ISOMERIC TRANSITION ISOTOPES
ISOTOPES
MANAGEMENT
MATHEMATICS
MINUTES LIVING RADIOISOTOPES
NUCLEAR DATA COLLECTIONS
NUCLEAR REACTIONS
NUCLEI
NUMERICAL DATA
PHYSICS
PLUTONIUM 239
PLUTONIUM ISOTOPES
PROCESSING
RADIOISOTOPES
REACTOR PHYSICS
REACTORS
SCATTERING
SHIELDING
SPONTANEOUS FISSION RADIOISOTOPES
THERMAL REACTORS
URANIUM 235
URANIUM 238
URANIUM ISOTOPES
YEARS LIVING RADIOISOTOPES