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At least 19 recordsLinked to original sources
PubMed1989

[Dosimetry of fast neutrons in 1W nuclear reactor with plastic nuclear-track detectors].

A nuclear reactor at Kinki University is operated at the maximum of 1W. It produces fission neutrons as much as gamma-rays. To facilitate its use for neutron radiobiology, fast neutrons inside the reactor were measured with nuclear-track detectors TS 16 N and a pair of ion chambers. The angular dependence of TS 16 N response, an anisotropy of fast neutron fluxes in the reactor and misuse of the kerma factor assumed for radiation protection business are the major causes of discrepancy is measured doses by the two methods. Correction factors for the three causes are proposed. After correction, neutron doses estimated with TS 16 N and chambers agree within 5%. The dose-rate at the reactor's center is about 20 tissue-cGy/h. This is the first in situ dosimetry of fast neutrons in a reactor with track detectors attached to biologic samples. Our routine usage has demonstrated that, if used with caution, TS 16 N elements are handy, reliable monitors for fast neutron dosimetry as they are insensitive to contaminated gamma-rays and small enough to be attached to biologic samples.

Fast Neutrons↗
PubMed1998

Numerical evaluation of the production of radionuclides in a nuclear reactor (Part I).

Numerical evaluation of nuclear transmutations is essential for optimization of radionuclide production. Accordingly, we have developed a generalized computer program called LAURA for predicting the production rates of radionuclides in a nuclear reactor. The program is generalized in the sense that it can be used for calculation of the production rate of any member of a network undergoing spontaneous decay and/or induced neutron transformation in a nuclear reactor. In this paper (Part I), we describe the mathematical basis for the development of LAURA. Expressions based on the Rubinson (1949) approach have been used for the evaluation of the depletion functions. This method is also valid when some of the depletion constants have identical values; thus, the approximate solution of Raykin and Shlyakhter (1989) can be used to account for the effects of feedback due to alpha decay.

Algorithms↗
PubMed1988

Radiation does from medical in-vivo prompt gamma-ray activation using a mobile nuclear reactor.

A method of medical diagnosis of toxic elements, using a neutron beam from a mobile nuclear reactor to perform partial-body in-vivo prompt gamma-ray activation technique, has been developed. Both neutron and gamma-ray dose equivalents in an irradiated phantom and around medical researchers were measured and evaluated. Neutron flux at various kinetic energies was measured using an activation foil technique, and the neutron dose equivalents at tissues of risk inside the irradiated phantom were calculated by neutron transport code. Gamma-ray dose equivalents inside the irradiated phantom and around the nuclear reactor were measured by thermoluminescent dosimeters. The risk associated with the neutron and gamma radiation dose equivalents received by both the irradiated phantom and medical researchers were evaluated in detail. The radiation safety of the in-vivo medical diagnosis using the mobile nuclear reactor, under the context of radiation protection guidelines, is discussed.

Activation Analysis↗
PubMed1985

A feasibility study of the in vivo prompt gamma activation analysis using a mobile nuclear reactor.

A facility for in vivo prompt gamma activation analysis using moderated neutron beams from a 0.1 W mobile nuclear reactor is described. The low-power nuclear reactor provides total neutron flux of 3.3 X 10(4)n cm-2 s-1 on the surface of a vertical beam tube to which a liquid phantom is positioned. The capability of such a partial-body irradiation facility is demonstrated by measuring trace amounts of toxic cadmium in kidney. The detection limit of Cd in kidney for a skin dose of 1.66 mSv (166 mrem) is 1.34 mg under 500 s irradiation. This facility therefore combines the advantages of mobility with high sensitivity of detection of a toxic element under low neutron and gamma doses.

Cadmium Poisoning↗
PubMedDate not supplied

A study of vital rates near a nuclear reactor.

Radiation exposure from the Big Rock Point nuclear reactor in Charlevoix County, Michigan was investigated by studying vital rates for that county and nearby counties in comparison with other matching counties, for periods before and after the reactor began operation. None of the variables studied showed any unusual change in pattern for Charlevoix county after the rector's operation was initiated, but the trend in low-weight births was higher in Charlevoix county than in adjacent counties, whose trends were in turn higher than for the matching counties. However, no other important significant differences were found among those tested statistically, therefore, an examination of these vital rates did not substantiate an association between the proximity of the reactor and the occurrence of pathology. Nevertheless, further study should be conducted to explain the pattern of low-weight births.

Humans↗
PubMed1987

[Evaluation of the dose equivalent absorbed by the population of Como and surrounding area following the nuclear reactor accident at Chernobyl].

The effects produced as a consequence of the Chernobyl nuclear reactor accident in the population of Como are assessed on the basis of the measurements taken in the environment and on the food. Exposure measurements produced by external radiation and the activities of the different radionuclides introduced into the body, by ingestion and inhalation, made it possible to obtain an estimate of the dose equivalent and its somatic and genetic effects on the population. The results show that such effects may produce 0.5-2 cases of malignant tumour in the next 25 years and 0.2-1 case of genetic damage in the next 60 years and are therefore statistically insignificant.

Accidents↗
PubMed1997

Semen Quality of Workers Exposed to Ionizing Radiation in Decontamination Work after the Chernobyl Nuclear Reactor Accident.

The objective of the study was to assess effects of radiation on sperm quality, including ultramorphology of spermatozoa of men who worked as salvage workers at the Chernobyl nuclear reactor accident site or in the adjacent region. Semen characteristics were assessed by light microscopy, biochemical analysis, and quantitative ultramorphologic analysis seven years after the accident. Samples were collected in the Ukraine, examined there by routine semen analysis, fixed, and transferred to Israel for further examinations. The study population consisted of 18 radiation-exposed individuals. Eighteen unexposed Ukrainian men were examined as controls. Sperm motility was found to be reduced in the radiation-exposed workers. Ultramorphologic defects were evident in the sperm nucleus. Fertility potential was adversely affected among the exposed workers. Thus, salvage workers who had worked at the Chernobyl nuclear reactor accident site or in the vicinity thereof were found to manifest ultramorphologic abnormalities in the sperm nucleus and to have impaired fertility potential seven years after the radiation exposure. The injury was independent of whether the work site had been located at the reactor site or in the vicinity thereof.

Journal Article↗
PubMedDate not supplied

[Microecology of nuclear reactor pool water].

In the course of research it was found that the circulation of pool water through the nuclear reactor core produces a bactericidal effect of microflora due to the influence of radiation of various types. The amount of microbes returns to initial level after 2-4 months after circulation was stopped. Microflora of pool water comprises large amounts of coccus, Gram-positive rods, fungi and a lower content of Gram-negative rods if compared to water which had been used to fill reactor pool. No difference in radioresistance was noticed for unitype microbes isolated from initial water and from reactor pool water. Quality of microflora reflects a unique phenomenon called "selection" which results in vanishing of all the radiosensitive types of microbes and survival of the radioresistant types. Radioresistance grows with increasing of catalase and nuclease activity.

Bacteria↗
PubMed1997

Individual quantification of 89Sr and 90Sr in nuclear reactor effluent.

An analytical method utilizing ion chromatography, a non-radioactive strontium carrier, and liquid scintillation spectroscopy to individually quantify 89Sr and 90Sr in nuclear reactor effluent is presented. It is observed that this method is less time consuming than traditional procedures for quantifying radio-strontium, deals comprehensively with separation and subsequent isotopic quantification of strontium, and avoids difficulties reported in previous research. The equipment, solutions and operating conditions for the chromatographic separation of strontium in aqueous solution are identified, and the strontium fraction is shown to elute between 7 and 7.5 min after injection. The beta spectra of 90Sr, 89Sr and 90Y are obtained using liquid scintillation spectroscopy, and the effects of quenching are shown to be negligible. The positions of the liquid scintillation windows within the combined beta spectra facilitating isotopic analysis of 89Sr and 90Sr are identified, followed by the system of equations to quantify 89Sr and 90Sr within a sample. The performance of the method is evaluated using five solutions representing effluent containing radio-strontium at known concentrations. It is observed that when the 89Sr and 90Sr concentrations each are approximately 37 Bq mL(-1) or more, the method over-estimates the 89Sr activity by 15-20% and under-estimates the 90Sr activity by 10-30%, while yielding the total radio-strontium activity to within 1-4% of expected. The lower limit of detection of the system for either 89Sr or 90Sr is shown to be approximately 0.8 Bq mL(-1) of effluent.

Chromatography, Ion Exchange↗
PubMed1991

Radionuclide contamination of foods imported into Iraq following the Chernobyl nuclear reactor accident.

Since early 1986, a monitoring program for radionuclides in imported foods has been carried out by the Iraqi Atomic Energy Commission. After the Chernobyl nuclear reactor accident in the Soviet Union, the program was expanded; our laboratory was officially designated by the Iraqi Government to measure radionuclide activity concentrations in foodstuff imported from countries known to be severely contaminated by Chernobyl radioactive fallout. Gamma-spectrometric analysis was used. Food items such as powdered milk, lamb meat, poultry, cereals and grains imported into Iraq before the Chernobyl accident did not contain any detectable fission products. However, all lamb meat, 81% of the lentil, 44% of the powdered milk and chick-pea, and 17% of the roast beef samples were contaminated with 137Cs or 134Cs and 137Cs. The highest 137Cs contamination levels found were 82, 147, 420, 6 and 4 Bq kg-1, respectively. Contamination by 134Cs was approximately 50% of the values given above.

Accidents↗
PubMed1998

Numerical evaluation of the production of radionuclides in a nuclear reactor (Part II).

A computer program called LAURA has been developed to predict the production rates of any member of a nuclei network undergoing spontaneous decay and/or induced neutron transformation in a nuclear reactor. The theoretical bases for the development of LAURA were discussed in Part I. In particular, in Part I, we described how an expression based on the Rubinson (1949) approach is used to evaluate the depletion function. In this paper (Part II), we describe the full simulation of radionuclide production including the decomposition of a reaction network into independent linear chains, provisions for periodic reactor shutdown and restart, and implementation of an approximate solution given by Raykin and Shlyakhter (1989) to account for the effect of feedback due to alpha decay. Also included are some examples which demonstrate possible uses for LAURA.

Computer Simulation↗
PubMed1984

Nuclear reactor accidents--the use of KI as a blocking agent against radioiodine uptake in the thyroid--a review.

This paper is intended for those people who are responsible for the public health and safety in the event of a nuclear reactor accident. The possibilities and consequences of a radioiodine release are examined briefly. The possible side effects of stable iodine, the prognosis for radiation-induced thyroid disease, and the alternative protective measures are put into perspective and assessed for their individual risks and benefits. It is recommended that all appropriate counter-radiation measures be considered in the case of a reactor accident, and that the harmful side effects of the various actions be weighed carefully. Definitive guidelines as to when the use of KI is justified must be decided upon before implementing mass distribution.

Accidents↗
PubMed1987

Radionuclide monitoring in Northern Ireland of the Chernobyl nuclear reactor accident.

Northern Ireland received higher radiation doses due to the radionuclide contamination from the Chernobyl nuclear reactor accident than did the south of England. Levels of radioactive iodine ((131)I) and caesium ((137)Cs) in cows' milk in Northern Ireland increased to 166 and 120 Bq/l respectively in May 1986, but had decreased by factors of one million, and of twenty-five, respectively, by 1 September 1986. The resultant radiation doses represent less than one per cent of those received by a Northern Ireland individual over a period of 40 years from natural background radiation sources. The added risk to any individual from the Chernobyl accident will therefore be very small and may best be judged in the context of the enormously greater risk of death due to potentially preventable diseases, such as smoking-related lung cancer, and coronary heart disease.

Adult↗
PubMed1992

Poly(L-lactic acid) microspheres containing neutron-activatable holmium-165: a study of the physical characteristics of microspheres before and after irradiation in a nuclear reactor.

The solvent evaporation technique was employed to prepare poly(L-lactic acid) (PLA) microspheres with 165Ho acetylacetonate (Ho-AcAc). Particle size, percentage Ho-165, percent residual solvent, and retentive ability of the spheres were found to be strongly affected by preparatory conditions. Differential scanning calorimetry (DSC) thermograms suggested that the Ho-AcAc existed in the PLA matrix as a molecular dispersion. High neutron flux irradiations of the PLA spheres in a nuclear reactor produced Ho-166, a therapeutic radionuclide that emits high-energy negatrons (Emax = 1.84 MeV; half-life = 26.9 hr). The gamma radiation dose (53-75 Mrad) from the core of the reactor provided an overkill of all bioburdens in the PLA spheres. Gel permeation chromatography (GPC) analysis showed that these irradiations caused a reduction in PLA molecular weight. Infrared spectra, 13C NMR spectra, 1H NMR spectra, and DSC thermograms further confirmed the presence of lower molecular weight PLA but proved the overall maintenance of PLA structure.

Bacillus↗
PubMed1997

A study of the effects of exposure on cleanup workers at the Chernobyl nuclear reactor accident using multiple end points.

Blood samples were collected from 192 exposed workers who participated in the cleanup after the April 26, 1986, nuclear reactor accident at Chernobyl, Ukraine. These samples, together with samples from 73 individuals living in Russia but not involved in Chernobyl cleanup activities, were collected during September 1991 to May 1996 and shipped to the U.S. for evaluation by three bioassays: cytogenetic analysis based on chromosome painting, HPRT mutation analysis and glycophorin A (GPA) variant analysis. Univariate statistical analyses of the results of each bioassay (including adjustments for age, smoking status and estimated precision of the bioassay) found greater frequencies of chromosome translocations and HPRT mutant T lymphocytes among the exposed individuals compared to the controls (P < or = 0.01). GPA analyses showed no significant difference for exposed compared to controls for either hemizygous, N/O, or homozygous, N/N, variant cell frequency. Multivariate analysis of variance of the subset of 44 exposed and 14 unexposed individuals with measurements from all three bioassays found elevated frequencies of chromosomal translocations and HPRT mutants, and reduced frequencies for both GPA end points among the exposed persons compared to the controls. However, none of these differences, considered singly or in combination, was statistically significant (although statistical power is low due to small sample sizes). Mean estimated dose, based on cytogenetic response, for those exposed was 9 cGy (range 0 to 51 cGy) and was less than that estimated by physical dosimetry (25 cGy). Correlation between the end points of the bioassays and estimated physical dosimetry was low (r < 0.2); the only significant correlation found was for physical dose estimate and dates worked at Chernobyl (r = 0.4, P < 0.01), with those working soon after the accident receiving greater estimated doses.

Adolescent↗