Published 1989 | Version v1
Book

Analysis of neutron emission on PWR spent fuel assemblies for burn-up assessment

  • 1. SCK/CEN, Mol (Belgium)

Description

A series of passive neutron measurements performed on TIHANGE I spent fuel assemblies were analyzed for comparison with calculated burn-up values and neutron emission rates. The burn-up range of these assemblies was between 10 and 45 MWd/kg and the cooling time varied from 1 to 8 years approximately. The measurements, performed with 235U fission chambers, were correlated with neutron emission and burn-up by means of the ORIGEN-2 point model depletion code, taking into account the irradiation history. A fairly good correlation is found between the 244Cm contributions, as deduced from the measurements corrected with ORIGEN-2, and the burn-up values as calculated with fuel management codes. The ratio of the calculated (ORIGEN-2) neutron emission and the measured neutron detection varied with the burn-up

Additional details

Publishing Information

Publisher
ASTM.
Imprint Place
Philadelphia, PA (USA)
ISBN
0-8031-1184-3
Imprint Title
Reactor dosimetry
Imprint Pagination
798 p.
Series
STP 1001.
Journal Page Range
p. 710-719.

Conference

Title
methods, applications, and standardization.
Acronym
6. ASTM-Euratom symposium on reactor dosimetry
Dates
31 May - 5 Jun 1987.
Place
Jackson Hole, WY (USA).

Optional Information

Secondary number(s)
CONF-870501--.