Preliminary evaluation of the fixed and fluidized bed nuclear reactor concept using the IAEA-INPRO methodology
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F. Sefidvash
Abstract
The International Atomic Energy Agency (IAEA) through its INPRO Project has developed a methodology to evaluate the innovative nuclear reactors. Here is a preliminary application of this methodology to evaluate the Fixed and Fluidized Bed Nuclear Reactor Concept (FBNR). The FBNR is based on pressurized light water reactor technology. It is a small, modular, and integrated primary circuit reactor. It is an inherently safe and passively cooled reactor concept. FBNR in its first phase of development is a fixed bed nuclear reactor and in its next phase will be a fluidized bed nuclear reactor. FBNR in its advanced versions can use supercritical steam or helium gas as coolant, and utilize MOX or thorium fuel.
Kurzfassung
Die Internationale Atomenergiebehörde (IAEA) hat mit den INPROProjekt eine Methodologie entwickelt um innovative Reaktorkonzepte zu evaluieren. In diesem Beitrag wird eine vorläufige Anwendung dieser Methodologie vorgestellt, um die Konzepte des Festbett und Wirbelbettreaktors (FBNR) zu evaluieren. Der FBNR basiert auf der Druckwasserreaktortechnik. Es ist ein kleiner, modular aufgebauter und primärseitig integrierter Reaktor. Es handelt sich um einen inhärent sicheren, passiv gekühlten Reaktor. Der FBNR ist in seiner ersten Entwicklungsphase ein Festbettreaktor und in der folgenden Phase ein Wirbelbettreaktor. In fortgeschrittenen Phasen kann er sowohl überkritischen Dampf oder Heliumgas als Kühlmittel benutzen als auch Mischoxid oder Thoriumbrennstoff enthalten.
References
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© 2004, Carl Hanser Verlag, München
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- Summaries/Kurzfassungen
- Summaries
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- Steady state thermal-hydraulic analysis for the ETRR-2 Research Reactor
- Monte Carlo simulation of the ETRR-2 research reactor using the MCNP Code
- Preliminary evaluation of the fixed and fluidized bed nuclear reactor concept using the IAEA-INPRO methodology
- Technical Notes/Technische Mitteilungen
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Improved Dancoff factors for cluster fuel bundles by the WIMSD code
- The impact of non-optimized operation of nuclear power plants on the nuclear fuel burn-up
- Experience with MTR fuel at the HOR reactor
- Comparison of two modern approaches for MBDA calculations of RBMK-type reactors
- Calculation of the energy deposition in the targets from C to U irradiated with intermediate energy protons
- U-Pb accelerator-driven sub-critical systems research at the proton beam of the JINR NUCLOTRON
- Steady state thermal-hydraulic analysis for the ETRR-2 Research Reactor
- Monte Carlo simulation of the ETRR-2 research reactor using the MCNP Code
- Preliminary evaluation of the fixed and fluidized bed nuclear reactor concept using the IAEA-INPRO methodology
- Technical Notes/Technische Mitteilungen
- A clean nuclear blasting technique for the excavation of a new isthmus canal in Central America
