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