SYMPOSIA PAPER Published: 01 January 1989
STP10132S

Analysis of Neutron Emission on PWR Spent Fuel Assemblies for Burn-Up Assessment

Source

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 was 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. It was noticed that the ratio of the calculated (ORIGEN-2) neutron emission and the measured neutron detection varied with the burn-up.

Author Information

Debrue, J
SCK/CEN, Mol, Belgium
Raedt, CD
SCK/CEN, Mol, Belgium
Minsart, G
SCK/CEN, Mol, Belgium
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Developed by Committee: E10
Pages: 710–719
DOI: 10.1520/STP10132S
ISBN-EB: 978-0-8031-5069-0
ISBN-13: 978-0-8031-1184-4