title: Characterisation of neutron fields at Cernavoda NPP.
abstract: Near a nuclear reactor or a fuel container, mixed neutron/gamma fields are very common, necessitating routine neutron dosimetry. Accurate neutron dosimetry is complicated by the fact that the neutron effective dose is strongly dependent on the neutron energy and the direction distribution of the neutron fluence. Neutron field characterisation is indispensable if one wants to obtain a reliable estimate for the neutron dose. A measurement campaign at CANDU nuclear power plant located in Cernavoda, Romania, was set up to characterise the neutron fields in four different locations and to investigate the behaviour of different neutron personal dosemeters. This investigation intends to assist in choosing a suitable neutron dosimetry system at this nuclear power plant.
authors.affiliation: SCK-CEN Belgian Nuclear Research Centre, Institute for Environment, Health and Safety, Radiation Protection Dosimetry and Calibration, Boeretang 200, 2400 Mol, Belgium. vcauwels@sckcen.be
authors.forename: Vanessa
authors.initials: V
authors.lastname: Cauwels
authors.forename: Filip
authors.initials: F
authors.lastname: Vanhavere
authors.forename: Dorin
authors.initials: D
authors.lastname: Dumitrescu
authors.forename: Alecsandru
authors.initials: A
authors.lastname: Chirosca
authors.forename: Luke
authors.initials: L
authors.lastname: Hager
authors.forename: Marc
authors.initials: M
authors.lastname: Million
authors.forename: James
authors.initials: J
authors.lastname: Bartz
mesh_terms: D019544:Equipment Failure Analysis; D006801:Humans; D009502:Neutrons; D055848:Nuclear Power Plants; D016273:Occupational Exposure; D011829:Radiation Dosage; D011834:Radiation Monitoring / Q000295:instrumentation*; D011835:Radiation Protection / Q000295:instrumentation*; D018570:Risk Assessment; D012383:Romania; D017751:Safety Management