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NUCLEAR SAFETY
Objectives:
- Increasing contribution of the institute to assimilation, development of knowledge database and evaluation technologies for nuclear installations behavior, focusing on Cernavoda NPP, in accident conditions;
- Increasing research contribution to nuclear safety evaluation needed for licensing and operation of Cernavoda NPP.
Research perspectives:
- DBA accident analysis:
- Assimilation and contribution to the development of Canadian technologies;
- Development of alternative, proprietary computer codes;
- Advanced modeling techniques;
- Cernavoda NPP applications: accident analyses for operation and licensing and specific training modules for personnel.
- Severe accident analysis ( beyond DBA):
- Assimilation and contribution to Cernavoda technologies development;
- Contribution in experimental areas;
- Development and alternative computer codes (ASTEC) in cooperation with EU;
- Cernavoda NPP applications: envelope behavior, operating procedures under severe accident conditions.
- Probabilistic and risk assessment:
- Upgrading the evaluation technologies to international level;
- Development of present techniques and methodologies;
- Pilot projects and case studies;
- Cernavoda NPP applications: risk evaluation models, norms and standards, personnel training.
- Specific assessment methodologies:
- Ageing of CNE components and structures;
- Components integrity;
- Operation events;
- Human factor behavior and performances;
- Safety limits and margins.
Main results of research:
- Reactor physics:
- Evaluation of nuclear data for isotopes of interest in the Cernavoda reactor;
- Development of methods and algorithms for processing nuclear data libraries;
- Development of methodology and methods for neutronic transport. Performance evaluation and documentation for the programs developed at SCN to characterize the Cernavoda reactor core;
- Reactor physics calculations for reactor core at Cernavoda NPP using AECL program and also programs developed by SCN Pitesti.
- Thermo-hydraulics:
- Model and computer code evaluation for accident analyze;
- Contribution on developing and perfecting the computing models and programs;
- Modeling and analyzing the LOCA accidents on Cernavoda NPP using computer codes and compare with existing results.
- Severe accidents:
- Contribution in validation for ASTEC computing program in EU PHEBEN2 (FP5) AND SARNET (FP6) projects;
- Evaluation and preliminary specification to adapt ASTEC computer program to Cernavoda NPP in EU SARNET (FP6);
- Assessment of the necessity and feasibility for some experiments at SCN-Pitesti for degradation of Cernavoda NPP reactor core in severe accident condition.
- Nuclear probabilistic safety assessment:
- Development of SCN Pitesti methodologies and computer codes;
- PSA models and studies for the TRIGA reactor;
- Analysis for the evaluation of fuel channel behavior in accident conditions;
- Thermo-hydraulic and Neutrino instrumentations characterizations in steady-state and dynamic regimes;
- Criticality analysis, biological protection, components radioactivity, radiation doses, applications of Monte Carlo method to reactor physics and radiation physics;
- Criticality analysis, biological protection for transport and interim storage of nuclear fuel;
- Radioactivity evaluation of components from reactor core, criticality calculations and neutrino analyses for nuclear fuel using Monte Carlo MCNP code in Bonner spectrometry.
Contact: Andrei RIZOIU; e-mail:
andrei.rizoiu@nuclear.ro
Last update: 22.04.2010 |
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Nuclear 2012
The 5th Annual International Conference on Sustainable Development through Nuclear Research and Education
May 16-18, 2012
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