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Nuclear Fuel
Objectives:
- Increasing burnup in UO2 fuel developing SEU 43-element advanced fuel bundle in order to reduce capital and fuelling cost, increase the operating and safety margins, improve resource uranium utilization and spent fuel management;
- Maintaining and improving the reliability and safety of natural uranium fuel bundles in Cernavoda NPP;
- Study fuel bahaviour during normal, fast transients and accidental conditions;
- Improving NPP operational flexibility;
- Providing high quality experimental data for verification, development and validation of computer codes;
- Improving the physical models used in computer codes.
Research perspectives:
- Fuel performance evaluation:
- Development and validation of fuel behaviour modelling codes;
- Irradiation testing and PIE for experimental fuel elements;
- Out of pile testing;
- Defected fuel behaviour investigation;
- Fuel failure mecanisms investigation;
- Extreme specifications fuel effects for fuel performance;
- Fundamental studies.
- Fuel safety research:
- Rapid overpower transient tests;
- LOCA tests;
- Integral thermal shock tests;
- Tensile tests;
- Fission gas release analytical experiments;
- Modelling of fuel behaviour under accident conditions;
- Validation of computer codes.
- Advanced fuel cycles (SEU, RU):
- Fuel bundle and fuel elements design;
- Reactor physics computation;
- Fuelling schemes simulation;
- Manufacturing and out of pile testing of advanced fuel bundles;
- Performance of fuel elements at extended burnup;
- Probabilistic methods in fuel performance modelling;
- In pile tests.
- Suport for NPP Cernavoda operating:
- Fuel safety analyses for Final Safety Annual Raport (FSAR);
- Fuel flaw cause identification;
- Expert-system development;
- Defining fuel operational limits;
- Fuel performance analyses in normal and accident operating conditions.
Main results of research:
- Computer codes development and validated;
- Fuel designs (design optimization and design evaluation);
- Fuel safety analyses:
- Safety and licensing requirements for nuclear fuel, made in Romania, used in Cernavoda NPP;
- Safety analyses for NPP Cernavoda Final Safety Report;
- Nuclear fuel behaviour during normal and accidental operating conditions.
- In pile tests performed in SCN - Pitesti Material Testing Reactor. PIE in SCN - Pitesti Hot Cells Laboratory:
- High Power Tests;
- Power ramp tests;
- Power cycling tests
- Internal gas pressure measurement tests;
- Sweep gas tests;
- Centerline fuel temperature measurement tests;
- RIA tests.
- Out of pile tests performed in Out-of-Pile Testing Department:
- Pressure drop tests;
- Strength tests;
- Impact tests;
- Flow endurence tests.
- Radioactive waste management:
- Thermal and thermo-mecahnical design analysis of spent fuel repository (cooperation with DBE-Germany).
Contact: Dr. Grigore HORHOIANU;
e-mail: grigore.horhoianu@nuclear.ro
Last update: 22.04.2010 |
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Nuclear 2010
The Third Annual International Conference on Sustainable Development through Nuclear Research and Education
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