Patent Number: 
Section: claims

1. A method of extracting strontium-89 from a uranyl sulfate water solution fueled nuclear reactor, the method comprising: operating said solution nuclear reactor whereby inert gaseous fission fragments are produced and migrate to the free volume above the solution surface, said gaseous fission fragments comprised of isotopes of beryllium, krypton and rubidium;  pumping said inert gaseous fission fragments through a first delaying device to achieve an approximate ten minute delay whereby krypton-90 is substantially depleted;  passing gas through a first filter to remove rubidium and strontium isotopes that were not precipitated in said first delaying device;  pumping remaining gas through a second delaying device to achieve an approximate thirty minute delay;  passing gas through a second filter to remove any remaining rubidium and strontium isotopes that were not precipitated out in said second delay device;  pumping remaining gas back to the reactor; and  extracting precipitated strontium-89 from said second delay device and from said second filter. 2. The method of  claim 1  wherein the extraction of strontium-89 from said second delay device and said second filter is by an acid wash. claim 1