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TRIGA REACTOR
Objectives:
- To provide technical support for nuclear fuel and structure materials irradiation and test;
- To produce radioisotopes for health, industry and environment application.
Activities:
- In-pile irradiation of nuclear fuel and structure materials:
- Irradiation test of nuclear fuel (fresh or irradiated fuel) in overpower, ramp power or power cycling condition:
- Residual clad deformations;
- Central fuel temperature measurement;
- Fission gases pressure;
- Fission gases composition.
- Development and licensing of the irradiation devices.
- Reactor core management:
- The core physics;
- Fuel management;
- Neutronic and thermo hydraulic assessment for HEU to LEU conversion of TRIGA SSR;
- Isotopic evaluation for the spent TRIGA-HEU fuel for its return to the country of origin;
- Development and maintenance of computer codes and libraries;
- RIA test developed in ACPR.
- Reactor utilization for isotopes irradiation:
- Development and licensing new irradiation devices for radioisotopes production;
- Development and licensing technologies for new radioisotopes production for industrial and medical use;
- Development and licensing of methods and measurement instrumentation channels in order to characterize the radioactive sources.
- Neutrons beam tubes applications:
- Neutron radiography;
- Neutron scattering experiments:
- structure analysis on polycrystalline samples;
- stress measurement;
Services:
- Neutron activation analysis;
- PGNA spectrometry;
- Neutrons flux measurement;
- Fuel burn-up measurement;
- Reactor physics tests and measurements;
- Gamma irradiation tests on materials and equipment for nuclear use;
- Radio-sterilization study (food and medical products).
Experimental installations:
- Standard irradiation devices:
- LOOP A-100KW: max. Temperature: 310 °C; max. Pressure: 120 bars;
- CAPSULE C1, C2: max. Temperature: 300 °C; max. Pressure: 120 bars;
- C5 CAPSULE: max. Temperature: 290 °C; max. Pressure: 6 bars;
- C6 CAPSULE: max. Temperature: 50 °C; max. Pressure: 4 bars;
- C7 CAPSULE: max. Temperature: 310 °C; max. Pressure: 110 bars;
- C9 CAPSULE: max. Temperature: 300 °C; max. Pressure: 120 bars.
- High resolution neutrons diffraction facility, DIR 1;
- Neutron radiography facility;
- PGNA spectrometry facility;
- Thermal column;
- High Activity Irradiation Gamma Facility (SIGMA).
Important achievements:
- Nuclear fuel tests and structural materials:
- Sample holder designing, making and instrumentation for fuel elements core temperature measurement;
- Fuel element core temperature measurement test;
- Simulation of nuclear fuel behavior in power cycling;
- Steel irradiation, used at terminals of fuel tubes;
- Zircaloy-4 clad sample irradiation;
- Zr - 2,5 % Nb alloy irradiation - samples was obtained from pressure tube heads from Cernavoda Unit 1;
- Out of order fuel nuclear limit energy determination;
- Gamma spectrometry fuel burn-up measurement;
- Gamma irradiation comportment test of components and equipments for Cernavoda Unit 1.
- Radioisotopes:
- 192Ir sources production for industrial gammagraphy;
- Irradiation target production for radioisotopes.
- Others specific applications of nuclear domain:
- Neutrons activation analysis development using K0 method;
- Neutron activation multi-elementary analysis;
- Boron (B) and gadolinium (Gd) isotopic abundance determination by gamma prompt spectroscopy;
- Developing of an new concept of crystal high resolution neutrons diffraction facility;
- Flux measurements at TRIGA reactor conversion;
- Flux measurement in TRIGA - ACPR reactor;
- Neutronic characterization of irradiating devices for tests in TRIGA - SSR and ACPR reactors;
- Gamma radiation testing condition establishment for electrically insulated materials used in nuclear field;
- Agricultural and food products irradiation treatment;
- Research regarding sterilization of mud in sewage;
- Necessary doses establishment for inactivation of radio resistant microorganisms;
- Irradiation tests for establishment of necessary doses for wine conservation and sterilization of materials used in oenology.
Contact: Dr. Marin PREDA; e-mail:
marin.preda@nuclear.ro |
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Nuclear 2010
The Third Annual International Conference on Sustainable Development through Nuclear Research and Education
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