MARIA reactor safety im improvements and research capacity im - - PowerPoint PPT Presentation
MARIA reactor safety im improvements and research capacity im improvements M. Lipka, M . Tarchalski, M. Gryziski, G. Krzysztoszek, J.Jaroszewicz, K. Pytel, R. Prokopowicz, 3-7 December 2017,18th IGORR, Sydney, Australia National Centre
J.Jaroszewicz, K. Pytel, R. Prokopowicz,
3-7 December 2017,18th IGORR, Sydney, Australia
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Apart from the MARIA research reactor, in years 1958-1995 the EWA research reactor was also operated at the Institute of Nuclear Research (later – the Institute of Atomic Energy). Initially, the reactor’s thermal power was 2 MWth, however it was increased to 10 MWth. The process of reactor decommissioning was started in 1997 and in 2002 the so called “end of phase two” was achieved. That means that all nuclear fuel and all irradiated structures and components, which have activity levels hazardous from the radiological protection viewpoint, were removed from the reactor. Further works were suspended and as for now it is not planned to continue the decommissioning process up to the state of “green grass” (denoted as phase three) due to the potential use of the reactor biological shield as a dry storage for spent fuel from the MARIA reactor.
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The e high igh flux flux res esearch rea eactor MARIA is is a a water an and bery eryll lliu ium mod
eactor
th nom
inal power le level.
l ty type e rea eactor with ith pres essurized fu fuel el ch chan annel els con
inin ing conc
tube e as assem emblie ies of
fuel el ele elements.
el ch channels are e situ ituated in in matrix ix con
inin ing bery eryll lliu ium bloc locks surrounded by gr graphite refle lector.
nominal po power r 30 30 MWth th
235 enr enrichment < < 20 20 %
l ne neutron fl flux de densit ity 3∙1014
14 n/
n/cm2s
ast t ne neutron fl flux de densit ity 3∙1014
14 n/
n/cm2s
H2O, be bery rylliu ium
gr graphite in Al
ing system ch channels in n poo pool
MARIA reactor safety improvements and research capacity uprate
The MARIA reactor has been in operation since December 1974 at the Institute for Nuclear Research in Świerk. In years 1985-1993 the reactor operation was stopped for its essential
been operated by the National Centre for Nuclear Research. From April 1999 to June 2002 the reactor core was converted from highly enriched uranium (80%) to highly enriched uranium fuel (36%). In the years 2012- 2014 the reactor core was further converted to low-enriched fuel LEU (concentration of U235 is below 20%). At present the fuel is 19.75% enriched Uranium 235 enclosed in Aluminium cladding.
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Gate for vehicles Gate for vehicles Reactor building Reactor service personnel building Researchers and offices building Cooling towers Diesel generators Decontamination hall Cooling circuit pumps
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Management of Research Reactor Ageing – IAEA, TE TECDOC-792 Ageing Management for Research Reactors – IAEA, Specific Safety Guide No. SSG SSG-10 10 Maintenance, Periodic Testing and Inspection of Research Reactors – Safety Guide No. NS NS-G-4.2
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