SYMPOSIA PAPER Published: 01 January 1989
STP10087S

Power Reactor Neutron Dosimetry: Experimental Estimate of the Influences Due to Local Changes in Core Configuration and Gamma-Induced Reactions

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For the evaluation of neutron flux densities in reactor pressure vessel surveillance analyses a detailed knowledge of the local power history is required. In this paper a new method is proposed which reconstructs experimentally the effects of the local power history through the analysis of the measured activities in fission dosimeters. The validity of the method was tested by comparing measurements carried out at Caorso BWR plant with neutron flux density computations performed using the DOT 4.2 code.

The same measurements and computations were utilized for carrying out an estimate of the gamma-ray flux density at the irradiation position.

Author Information

Alloggio, G
ENEL, Ente Nazionale per l'Energia Elettrica, Centro di Ricerca Termica e Nucleare (CRTN), Milan, Italy
Borioli, E
ENEL, Ente Nazionale per l'Energia Elettrica, Centro di Ricerca Termica e Nucleare (CRTN), Milan, Italy
Brega, E
ENEL, Ente Nazionale per l'Energia Elettrica, Centro di Ricerca Termica e Nucleare (CRTN), Milan, Italy
Sandrelli, G
ENEL, Ente Nazionale per l'Energia Elettrica, Centro di Ricerca Termica e Nucleare (CRTN), Milan, Italy
Cesana, A
Politecnico di Milano, Istituto di Ingegneria Nucleare, Centro Studi Nucleari E. Fermi (CESNEF), Milan, Italy
Terrani, M
Politecnico di Milano, Istituto di Ingegneria Nucleare, Centro Studi Nucleari E. Fermi (CESNEF), Milan, Italy
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Details
Developed by Committee: E10
Pages: 281–292
DOI: 10.1520/STP10087S
ISBN-EB: 978-0-8031-5069-0
ISBN-13: 978-0-8031-1184-4