Technical Meeting on Commercial Products and Services of
Research Reactors

28 June–2 July, 2010, IAEA, Vienna

Details
 
Large Reactor Utilization
INR TRIGA Research Reactors: A Neutron Source for Radioisotopes and Materials Investigation

D. Barbos, M. Ciocanescu, C. Paunoiu, A.F. Bucsa
Institute for Nuclear Research, Mioveni, Romania

Abstract

At the INR there are 2 high intensity neutron sources. These sources are in fact the two nuclear TRIGA reactors: TRIGA SSR 14 MW and TRIGA ACPR. TRIGA stationary reactor is provided with several in-core irradiation channels. Other several out-of-core irradiation channels are located in the vertical channels in the beryllium reflector blocks. The maximum value of the thermal neutron flux (E<0.55 eV) in the central core channel XC-1 (water-filled) is 2.46×1014 cm-2s-1 and of fast neutron flux (E>1 MeV) is 6.89×1013 cm-2s-1. For neutron activation analysis both reactors are used and k0-NAA method has been implemented. At INR Pitesti a prompt gamma ray neutron activation analysis devices has been designed, manufactured ant put into operation. For nuclear materials properties investigation neutron radiography methods was developed in INR. For these purposes two neutron radiography devices were manufacture, one of them underwater and other one dry. The neutron beams are used for investigation of materials properties and components produced or under development for applications in the energy sector (fission and fusion). At TRIGA 14 MW reactor a neutron difractormeter and a SANS devices are available for material residual stress and texture measurements. TRIGA 14 MW reactor is used for medical and industrial radioisotopes production (131I, 125I, 192Ir, etc) and a method for 99Mo-99Tc production from fission is under developing. At INR Pitesti several special programmes for new types of nuclear fuel behavior characterization are under development.

 
Paper   Presentation

Vienna, Austria, 28 Jun–2 July 2010

IAEA-TM-38728

© IAEA, 2013

Produced by the IAEA in Austria
July 2013