Bonow, R. O., Carabello, B. A., Chatterjee, K. és mtsai:
2008 focused update incorporated into the ACC/AHA 2006 guidelines for the management of patients with valvular heart disease: a report of the American College of Cardiology/American Heart
Authors:D. Djokić, T. Maksin, J. Vučina, and D. Janković
A modified99mTc(Sn)-pyrophosphate (PyP) kit for the application in nuclear cardiology (radioventriculography, angiocardiography, scintigraphy
of blood pool) was developed. Each vial contains 12 mg PyP (Na4P2O7), 4 mg SnCl2·2H2O, 2.5 mg gentisic acid and 10 mg NaCl. The reconstitution is performed by dissolving the lyophilized kit in 3 ml 0.9% NaCl.
In comparison with the standard pyrophosphate kit for bone scanning and detection of miocardial infarction, it contains an
increased amount of Sn(II) so that the molar ratio ligand/reductant is lowered from 25 to 2.5. The radiochemical analyses
showed that the radiochemical purity of the labeled kit is high (>90%) during three hours after addition of99mTc-activity. The shelf-life of the inactive freeze-dried preparation is up to four months providing that it is kept in vacuum
and at appropriate temperature (2–8°C). The biodistribution studies revealed increased accumulation in blood and low uptake
by liver and kidneys. It was concluded that the modified kit performs stable and reproducible properties.
Authors:M. Zdravkovic, B. Vujusić-Tesic, M. Krotin, I. Nedeljkovic, S. Mazic, J. Stepanovic, M. Tesic, and M. Ostojic
Cardiovascular pre-participation screening of young competitive athletes for prevention of sudden death: Proposal for a common European protocol. Consensus Statement of the Study Group of Sport Cardiology of the Working Group of Cardiac
Authors:F. F. (Russ) Knapp Jr., S. Mirzadeh, A. L. Beets, and M. Du
Greater availability of therapeutic radioisotopes is required to meet the demands for increasing clinical applications in nuclear medicine, oncology and interventional cardiology. Because of the need for very high specific activity products, methods other than direct neutron capture reactions (n,γ-elastic and n,n’-inelastic routes) are required to insure that the highest specific activity - and hopefully no carrier added (nca) - radioisotopes are available. Two major methods to obtain nca radioisotopes from reactors are through the use of radionuclide generator systems using reactor-produced parents and the formation of desired radioisotopes through beta-decay of reactor-produced species. In this paper we describe our recent development of new approaches to obtain nca 177Lu from the decay of reactor-produced 177Yb and free of the long-lived 177mLu (T1/2 = 160 d) radiocontaminant. We also describe preliminary results of our new “indirect” method for the production of 195mPt via decay of 195mIr, reactor-produced by neutron irradiation of highly enriched 193Ir.