Published 1978 | Version v1
Report

Status report on dosimetry benchmark neutron field development, characterization and application

Description

A brief but comprehensive review is presented of the status and future directions of benchmark neutron field development, characterization and application in perspective with two major objectives of reactor dosimetry: fuel fission rate and burn-up passive monitoring; and correlation of materials irradiation damage effects and projection to commercial power plants. The report focuses on the Light Water Reactor and Fast Breeder Reactor program needs. Current interfaces between dosimetry, reactor physics, cross section metrology solid state research and metallurgy are highlighted through a tentative classification of the benchmark field and its justification. A summary is given of indications drawn regarding the accuracy of fundamental fission cross sections, of dosimetry sensor nuclear data, of helium production assessment, of dosimetry fission yields, and of some other nuclear cross sections, on the basis of integral measurements in selected benchmark neutron fields. The ENDF/B IV data files are used as reference for the discussions

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS., PC A03/MF A01.

Additional details

Publishing Information

Imprint Pagination
39 p.
Report number
HEDL-SA--1572

Conference

Title
2. symposium on reactor dosimetry.
Dates
3 - 7 Oct 1978.
Place
Palo Alto, CA, USA.

Optional Information

Secondary number(s)
CONF-781002--2.