By M. Ishii; S. T. Revankar; U. S. Rohatgi; T. Downar; Y. Xu, H. J. Yoon; D. Tinkler; USDOE Office of Nuclear Energy, Science and Technology (NE) (US); Purdue University.; Brookhaven National Laboratory.; United States. Dept. of Energy. Oakland Operations Of
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Extra info for MODULAR AND FULL SIZE SIMPLIFIED BOILING WATER REACTOR DESIGN WITH FULLY PASSIVE SAFETY SYSTEMS
522 MW, 630 MW. 22 to 1800 MW,. Of the 36 reactor concepts listed, about 50% belong to a low-power category < 100 MW,, including seven very-low-power designs and concepts that are < 12 MWt. (iv) Despite the large number of IPWR designs and concepts listed, very few have been actually constructed. The exceptions are very-low-power experimental prototype units in China and Russia (< 5 MW,) and marine propulsion systems of intermediate power levels (< 50 MW,) in France and Germany. 5 and SHR. All of these small IPWR designs use natural circulation of the primary coolant without pumps and incorporate passive safety features such that some degree of limited autonomous reactor operation may be achievable.
Design features that enhance the ability to cool the core include: a low power density to provide a large fuel heat transfer surface area and a large temperature margin to fuel failure, a large primary coolant inventory to provide a slow response to transients, relatively low primary system operating temperature and pressure to provide large safety margins, reduced stored thermal energy and slower response to Loss Of Coolant Accident (LOCA) events, a thermalhydraulic arrangement that facilitates natural coolant circulation while avoiding the potential formation of vapour-lock flow barriers, a passive decay heat removal system, particularly one that does not require active initiation, and limitation of LOCA events by using only small diameter piping penetrations on the RPV and locating them well above the top of the reactor core.
In general, these barriers include the fuel matrix itself (UO2), the fuel cladding, the primary heat transport circuit boundary and a surrounding containment structure. Autonomous reactor operation for a specified time interval requires that all containment barriers are initially intact and that no events are foreseen that could compromise barrier integrity within this duration. Concerning the fuel cladding containment barrier, special mention must be made of the hightemperature ceramic cladding used with TRISO coated-particle fuel that provides excellent containment behaviour in high temperature gas cooled reactors, even though fuel based on this principle is not presently applicable to PWRs.
MODULAR AND FULL SIZE SIMPLIFIED BOILING WATER REACTOR DESIGN WITH FULLY PASSIVE SAFETY SYSTEMS by M. Ishii; S. T. Revankar; U. S. Rohatgi; T. Downar; Y. Xu, H. J. Yoon; D. Tinkler; USDOE Office of Nuclear Energy, Science and Technology (NE) (US); Purdue University.; Brookhaven National Laboratory.; United States. Dept. of Energy. Oakland Operations Of