Published 1983 | Version v1
Journal article Metadata-only

A device for neutron flux monitoring during refueling of WWER-440 reactors

Creators

  • 1. Bylgarska Akademiya na Naukite, Sofia. Inst. za Yadrena Izsledvaniya i Yadrena Energetika

Description

A device for measuring the neutron flux density during fueling of WWER type reactors is described. The device consists of two units: a measuring probe and a registration modulus. The measuring probe is a pulse fission chamber of KNT-54 type with a preamplifier placed in a 2.5 m long stainless steel pipe with an outer diameter of 52 mm. The registration modulus registers neutron impulses from the measuring probe in three channels: digital, acoustic and plotter. Thermal neutron flux in the reactor core is measured in the range 10-103 cm-2.s-1 at γ-emission dose greater than 2.58.10-3A/kg. Tests during the refueling of Kozloduj 1 and 2 reactors indicate that the device is highly reliable, noise-resistant and easy for operation

Additional details

Publishing Information

Journal Title
Yad. Energ.
Journal Volume
20
Series
Yad. Energ.
Journal Page Range
42-48
ISSN
0204-6989

INIS

Country of Publication
Bulgaria
Country of Input or Organization
Bulgaria
INIS RN
16071999
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
FISSION CHAMBERS; NEUTRON FLUX; NEUTRON MONITORS; REACTOR FUELING; THERMAL NEUTRONS; WWER TYPE REACTORS
Descriptors DEC
BARYONS; ELEMENTARY PARTICLES; ENRICHED URANIUM REACTORS; FERMIONS; HADRONS; IONIZATION CHAMBERS; MEASURING INSTRUMENTS; MONITORS; NEUTRON DETECTORS; NEUTRONS; NUCLEONS; POWER REACTORS; PWR TYPE REACTORS; RADIATION DETECTORS; RADIATION FLUX; RADIATION MONITORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS