ABSTRACT
Some specific and non-specific immune variables of rainbow trout were assessed following vaccination of fish with formalin killed cells [FKC] and FKC containing extra cellular products [ECP] of S. iniae. Rainbow trout weighing 80-100 g were vaccinated by intraperitoneal [i.p], dip and oral routes using FKC and FKC plus ECP with or without Fround adjuvant [FA] at 16-17 C. Antibody titration, lysozyme activity, serum bacterial killing activity and population of immunocompetent cells were measured on 3, 6, 9, 12, 15 and 18 weeks postvaccination. Data were analyzed by ANOVA. Results showed that the highest antibody titers were produced in i.p vaccinated fish with FKC plus ECP and immunized fish with FKC by dip, respectively. However, administration resulted in the lowest response. Also, the level of antibody production was higher during initial period of post-immunization, while it reduced to lower levels at the end of sampling time. Similar results were obtained when lysozyme activity and bacterial killing capacity of sera samples were estimated. Moreover, while, leukocyte and lymphocyte populations in immunized fish were generally higher than control groups, heterophil and monocyte counts were varied during the sampling periods. Reuslts show that both humeral and cellular immunities of trout are enhanced following immunization of fish with FKC with or without ECP administered as i.p and dip. However, i.p administration of FKC with or without ECP could cause higher response than both dip and oral routes
Subject(s)
Animals , Streptococcus/immunology , ImmunizationABSTRACT
Background: People who have been administrated radiopharmaceuticals could be a source of radiation to their relatives, medical nurses, and people who are in contact with them. The aim of this work was to estimate radiation dose received by nuclear medicine nurses
Materials and Methods: In this study, the dose rates at various distances of 5 - 100 cm from 70 patients, who were administered diagnostic amounts of 201Tl-Chloride and 99mTc-MIBI, were measured using an ionization chamber. For determination of external radiation dose to the nurses, three different time intervals were used for measurements
Results: The maximum values of external dose rates of 201Tl and 99mTc-MIBI were 11.2 microSv/h +/-2.3 and 43.1microSv/h +/-11.9 respectively, at 5cm from the patients. Significant exposure from patients after injection of 99mTc-MIBI was limited to the day of administration. Departure dose rate of 201Tl fell gradually; so, it became significant by 3 days after administration. Maximum and average absorbed dose of nuclear medicine staff from 201Tl, was 4.6 and 2.7 microSv/h, and for 99mTc-MIBI was 18.1 and 9.8 microSv/h in each scan
Conclusion: Significant exposure from the patients is limited to the few hours after administration, therefore patients should be recommended to urinate frequently before leaving the nuclear medicine department
ABSTRACT
The radioisotope 67Ga [T 1/2=78 h] in extensively used as single photon marker for detecting the presence of malignancy and the diagnosis of inflammatory diseases. The high tumor specificity of carrier-free 67Ga make it one of the most interesting radionuclides in nuclear medicine for in vivo scanning studies. 67Ga is a cyclotron produced radioisotopes and is one of the radiopharmaceuticals which is produced at our center. An enriched 68Zn cyclotron target design has been developed for the large-scale production of carrier-free 67Ga with -<5 percent 66Ga contamination as one of the impurities. The advantage of high 67Ga yield from proton beam bombardment of enriched Zinc is somewhat to our disadvantage due to the high price of enriched Zinc. Due to this problem another alternative method for Ga-67 production was sought. Our theoritical and experimental studies have been resulted to production of 67Ga by irradiating natural Zinc with deuteron beam. The production of the radiopharmaceutical is achieved by two steps. 1] Deuteron bombardment of natural Zinc target in the cyclotron and subsequent production of Ga-67. 2] Chemical processing which involves the separation of 67Ga from target material. After quality control testing, the produced 67GaCI3 is converted to citrate and as a sterile and pyrogen free product, it is ready for human use