ISSN: 1546-962X
CODEN: JAIOAD
Published Online: 1 March 2012
Page Count: 10

Neutron and Gamma Field Investigations in the VVER-1000 Mock-Up Concrete Shielding on the Reactor LR-0

Zaritsky, S.
National Research Center, Kurchatov Institute, Moscow

Egorov, A.
National Research Center, Kurchatov Institute, Moscow

Ošmera, B.
Research Centre Řež Ltd, Řež,

Mařik, M.
Research Centre Řež Ltd, Řež,

Rypar, V.
Research Centre Řež Ltd, Řež,

Cvachovec, F.
Univ. of Defense, Brno,

Kolros, A.
Czech Technical Univ., Prague,

(Received 17 May 2011; accepted 21 November 2011)

Abstract

Two sets of neutron and gamma field investigations were carried out in the dismountable model of radiation shielding of the VVER-1000 mock-up on the LR-0 reactor. First, measurements and calculations of the ³He(n,p)T reaction rate and fast neutrons and gamma flux spectra in the operational neutron monitor channel inside a concrete shielding for different shapes and locations of the channel (cylindrical channel in a concrete, channels with collimator in a concrete, cylindrical channel in a graphite). In all cases measurements and calculations of the ³He(n,p)T reaction rate were done with and without an additional moderator-polyethylene insert inside the channel. Second, measurements and calculations of the ³He(n,p)T reaction rate spatial distribution inside a concrete. The ³He(n,p)T reaction rate measurements and calculations were carried out exploring the relative thermal neutron density in the channels and its space distribution in the concrete. Fast neutrons and gamma measurements were carried out with a stilbene (45 × 45 mm) scintillation spectrometer in the energy regions 0.5–10 MeV (neutrons) and 0.2–10 MeV (gammas).

Keywords:
VVER-1000, shielding, mock-up, LR-0 reactor, 3He(n,p)T reaction rate, fast neutrons, gammas, measurements, calculations

Paper ID: JAI103995
DOI: 10.1520/JAI103995
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