ABSTRACT
The aim of the study was to assess the long-term results of using hemostatic sponge as material of choice for sinus lift with simultaneous implant placement. The results suggest this method to be clinically successful while reducing treatment coast and length.
Subject(s)
Alveolar Process/surgery , Dental Implantation , Hemostatic Techniques , Paranasal Sinuses/surgery , Surgical Sponges , Adolescent , Adult , Aged , Female , Humans , Male , Middle Aged , Young AdultABSTRACT
The given way of reconstruction of posttraumatic injuries showed predicted, long-term results and can be recommended for application in specialized establishments on bases of hospitals. Use of the data of computer tomography during the preoperative and postoperative period allows to estimate the volume of missing bone tissue. It also allows to define the volume of autogenous bone required for completion. Allows to define parameters of thickness, height, degree of curvature of autogenous bone, and also to select the optimum size of titanium plate or mesh. Application of perforated titanium plates ams meshes, made of high-purity the titan, allows to correct complex defects of maxillofacial area with minimization of complications in the postoperative period.
Subject(s)
Facial Bones/injuries , Facial Bones/surgery , Plastic Surgery Procedures/methods , Skull Fractures/surgery , Surgical Mesh , Titanium , Adult , Female , Follow-Up Studies , Humans , Male , Mandibular Reconstruction/methods , Retrospective Studies , Skull Fractures/pathologyABSTRACT
The results presented in this paper display our continuing steps toward development of a neutron source with parameters required by boron neutron capture therapy (BNCT) at the Kyiv Research Reactor (KRR). The purpose of this work was: 1. calculation of the neutron flux which can be achieved at the greatest possible approach of a patient to the reactor core; 2. analysis of the influence of a nickel collimator and a nickel-60 filter on the characteristics of the neutron beam; 3. creation and validation of the MCNP calculational pattern for an actual core fuel load in the KRR. Results of calculations were carried out by means of the MCNP4C code included: 1. An epithermal neutron flux of 3x10(9)-5x10(9)neutron/cm(2)s with an epithermal-to-fast flux ratio of 80-230 could be obtained at the KRR, using a natural nickel layer on the interior borated polyethylene collimator wall and a (60)Ni filter. 2. Use of the (60)Ni filter may be useful to increase the ratio epithermal-to-fast flux without a substantial decrease in the magnitude of the epithermal neutron flux. 3. The MCNP model proposed in this paper could also be useful for reactor safety calculations.
