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The 21st century will be characterised by a numerous acts of sabotage against man-made facilities and NPPs. Events of 9/11 in the  USA showed how it can happed.
      
The vulnerability of an NPP can be explained by the application of fuel elements with zirconium claddings. Tubes from such an alloy can perfectly well retain the fission products under the normal operation conditions. But in accidents the temperature of the alloy rises to 1000°C. At that temperature the strength deteriorates by several times. Due to that the fission products escape from the fuel and the reactor. In case of a heavy aircraft crash the containment and the reactor (of VVER type) can be destroyed.  Radiation consequences of such an accident will be comparable to those  ones of Chernobyl.
      
The work of Russian scientists [1] proves that the application of micro-fuel elements in VVER type reactors is very promising.
      Micro-fuel elements are balls made of UO
2 and covered by several layers of graphite and silicon carbide. Originally this fuel was designed for high-temperature reactors (HTGR) with helium coolant. For HTGR micro-fuel elements proved to be excellent. They efficiently retained fission products at 1300-1500°C.
      It is well known that ceramics retains the strength at very high temperatures. In high-temperature reactors the micro-fuel was used at the nominal temperature of 1500°C and retrained the fission products. In accidental conditions this was true even at 2000°C. This is a well known property of ceramic materials. High temperature gas cooled reactors were not widely used for competitive reasons.
      Application of micro-fuel elements in VVER reactors may significantly increase the radiation safety of NPPs.
      In the work [1] the micro-fuel elements were placed in a fuel assembly (as a layer of fuel or a pebble bed) directly washed by the coolant.
      It is important to note that the fuel assembly with micro-fuel elements can be made as an exact replica of the current FA with fuel rods (keeping the same thermal, hydraulic and neutronic characteristics and dimensions). It means that all existing NPPs can be loaded with new fuel assemblies with micro-fuel elements and the radiation safety will be guaranteed at any accidents, up to the deterministic level.
      In the reactor with micro-fuel the residual heat is removed by a natural convection at any failure of an active cooling system. If any positive reactivity is inserted it is compensated by the evaporation of the coolant which is a moderator also. This unique property is inherent only to VVER and PWR reactors that use the same liquid for cooling and moderation. Even in case of the vessel tank rapture after the aircraft crash or sabotage, the micro-fuels elements scattered on the site will retain the fission products.
      This way the application of micro-fuel in the existing NPPs will allow large scale development of the nuclear power in the first half of the 21
st century.
      Studies on the application of micro-fuel in VVER were started in
Russia in 1992. Since 1994 this work is supported by Framatome. Up to now a number of out-of-pile tests has been made, namely:

-    Examination of corrosion resistance in water (3500, 19 MPa, 10 months)

-    Examination of corrosion resistance in superheated steam (55000, 10 MPa, 14 months)

-    Examination of corrosion resistance in superheated steam (900°C, 14 days);

-    Examination of corrosion resistance in combustion gases (simulation of water-steam mixture) at 1000-1670°C during 6 hours;

-    Examination of the chemical interaction between micro-fuel and stainless steel at temperatures above 1200°C;

-    Mathematical modeling of accidents, including vessel tank rapture

These studies showed the possibility to create a reactor of VVER type with unique safety characteristics. Presently micro-fuel elements are tested in-pile in a water loop of research reactor IVV-2M (Zarechny near Yekaterinburg).
      
Studies on the application of micro-fuel elements in boiling reactors of BWR type were supported by Hitachi and the use of the same fuel in fast breeders is supported by French Commissariat of Atomic Energy. Development of a concept for a vessel type once-through reactor with super-heated steam and micro-fuel elements is supported by PNNL (USA).
     
The goal of this work is to develop a design of a micro-fuel element for existing NPP with VVER (PWR) reactors.
      The work will be carried out by a number of Russian companies, including RRC KI, VNIIAM, NPO Lutch, and OKB Gidropress.
      97 experts and scientists will participate in the project under the aegis of VNIIAM. Among them 55 earlier were involved in the design and fabrication of weapons.
      To realize that project is needed to cooperate Russia
and USA together.

Best Regards,
Nickolay Zhukov

 

VNIIAM 2005

 

 

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