Published March 1986
| Version v1
Journal article
The neutron cross section standards evaluation for ENDF/B-VI
- 1. National Bureau of Standards, Gaithersburg, MD (USA)
- 2. Argonne National Lab., Idaho Falls, ID (USA)
- 3. Los Alamos National Lab., NM (USA)
- 4. Oak Ridge National Lab., TN (USA)
Description
The neutron cross section standards are now being evaluated as the initial phase in the development of the new ENDF/B-VI file. These standards evaluations are following a somewhat different process compared with that used for earlier versions of ENDF. The primary effort is concentrated on a simultaneous evaluation using a generalized least squares program, R-matrix evaluations, and a procedure for combining the results of these evaluations. The ENDF/B-VI standards evaluation procedure is outlined, and preliminary simultaneous evaluation and R-matrix results are presented. (author)
Additional details
Publishing Information
- Journal Title
- Radiat. Eff.
- Journal Volume
- 96
- Journal Issue
- 1-4
- Series
- Radiat. Eff.
- Journal Page Range
- 87-98
- ISSN
- 0033-7579
- CODEN
- RAEFB
Conference
- Title
- international conference.
- Acronym
- Nuclear data for basic and applied science
- Dates
- 13-17 May 1985.
- Place
- Santa Fe, NM (USA).
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 18063867
- Subject category
- S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CROSS SECTIONS; EVALUATION; LEAST SQUARE FIT; NEUTRON REACTIONS; NEUTRONS; NUCLEAR DATA COLLECTIONS; R MATRIX; STANDARDIZATION
- Descriptors DEC
- BARYON REACTIONS; BARYONS; ELEMENTARY PARTICLES; FERMIONS; HADRON REACTIONS; HADRONS; MATRICES; MAXIMUM-LIKELIHOOD FIT; NUCLEAR REACTIONS; NUCLEON REACTIONS; NUCLEONS; NUMERICAL SOLUTION