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Title: Experimental investigation of neutronic characteristics of the IR-8 reactor to confirm the results of calculations by MCU-PTR code

A comparison of measured and calculated neutronic characteristics (fast neutron flux and fission rate of {sup 235}U) in the core and reflector of the IR-8 reactor is presented. The irradiation devices equipped with neutron activation detectors were prepared. The determination of fast neutron flux was performed using the {sup 54}Fe (n, p) and {sup 58}Ni (n, p) reactions. The {sup 235}U fission rate was measured using uranium dioxide with 10% enrichment in {sup 235}U. The determination of specific activities of detectors was carried out by measuring the intensity of characteristic gamma peaks using the ORTEC gamma spectrometer. Neutron fields in the core and reflector of the IR-8 reactor were calculated using the MCU-PTR code.
Authors:
; ; ; ; ;  [1]
  1. National Research Center Kurchatov Institute (Russian Federation)
Publication Date:
OSTI Identifier:
22471959
Resource Type:
Journal Article
Resource Relation:
Journal Name: Physics of Atomic Nuclei; Journal Volume: 78; Journal Issue: 11; Other Information: Copyright (c) 2015 Pleiades Publishing, Ltd.; Country of input: International Atomic Energy Agency (IAEA)
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; ACTIVATION DETECTORS; COMPARATIVE EVALUATIONS; ENRICHMENT; FAST NEUTRONS; FISSION; GAMMA SPECTROMETERS; IRON 54 TARGET; IRRADIATION DEVICES; NEUTRON REACTIONS; NICKEL 58 TARGET; PROTONS; REACTOR CORES; RESEARCH REACTORS; URANIUM 235; URANIUM DIOXIDE