C339. The probability of a serious nuclear reactor accident

1989 ◽  
Vol 32 (1-2) ◽  
pp. 124-126 ◽  
Author(s):  
R.F. Cameron ◽  
C.F. Clement
Keyword(s):  
Nuclear Reactor ◽  
Reactor Accident

Eds Of Radioactive Particles By Self-Induced Fluorescence

1990 ◽  
Vol 48 (2) ◽  
pp. 238-239
Author(s):  
Gregory L. Finch ◽  
Richard G. Cuddihy
Keyword(s):  
Electron Beam Irradiation ◽  
Nuclear Reactor ◽  
X Rays ◽  
Reactor Accident ◽  
Internal Radiation ◽  
X Ray ◽  
External Sources ◽  
X Irradiation ◽  
Available Information ◽  
Individual Particles

The elemental composition of individual particles is commonly measured by using energydispersive spectroscopic microanalysis (EDS) of samples excited with electron beam irradiation. Similarly, several investigators have characterized particles by using external monochromatic X-irradiation rather than electrons. However, there is little available information describing measurements of particulate characteristic X rays produced not from external sources of radiation, but rather from internal radiation contained within the particle itself. Here, we describe the low-energy (< 20 KeV) characteristic X-ray spectra produced by internal radiation self-excitation of two general types of particulate samples; individual radioactive particles produced during the Chernobyl nuclear reactor accident and radioactive fused aluminosilicate particles (FAP). In addition, we compare these spectra with those generated by conventional EDS.Approximately thirty radioactive particle samples from the Chernobyl accident were on a sample of wood that was near the reactor when the accident occurred. Individual particles still on the wood were microdissected from the bulk matrix after bulk autoradiography.

Knowledge on radiation emergency preparedness among nuclear medicine technologists

2021 ◽  
Author(s):  
N.A. Shubayr ◽  
Y.I. Alashban
Keyword(s):  
Nuclear Medicine ◽  
Emergency Preparedness ◽  
Nuclear Reactor ◽  
Radiation Detection ◽  
Population Monitoring ◽  
Geiger Counter ◽  
Willingness To Participate ◽  
Reactor Accident ◽  
Radiation Emergency ◽  
Emergency Preparedness And Response

This study aimed to assess the knowledge of nuclear medicine technologists (NMTs) in radiation emergency preparedness and response operations and their willingness to participate in such operations. A survey was developed for this purpose and distributed to NMTs in Saudi Arabia. Sixty participants responded with a response rate of 63.31%. Based on the overall radiation protection knowledge related to emergency response, NMTs can perform radiation detection, population monitoring, patient decontamination, and assist with radiological dose assessments during radiation emergencies. There were no significant differences in the knowledge on the use of scintillation gamma camera (P = 0.314), well counter (P = 0.744), Geiger counter (P = 0.935), thyroid probes (P = 0.980), portable monitor (P = 0.830), or portable multichannel analyzer (P = 0.413) and years of experience. Approximately 44% of the respondents reported receiving emergency preparedness training in the last 5 years. Respondents who reported receiving training were significantly more familiar with the emergency preparedness resources (P = 0.031) and more willing to assist with radiation detection or monitoring in the event of nuclear reactor accident (P = 0.016), nuclear weapon detonation (P = 0.002), and dirty bomb detonation (P = 0.003). These findings indicate the importance of training and continuing education in radiological emergency preparedness and response, which increase the willingness to respond to radiological accidents and fill the gaps in NMTs’ knowledge and familiarity with response resources.

Swedish Nuclear Power and Economic Rationalities

2002 ◽  
Vol 13 (2) ◽  
pp. 191-206 ◽  
Author(s):  
Tomas Kåberger
Keyword(s):  
Nuclear Power ◽  
Nuclear Reactor ◽  
Electricity Production ◽  
Carbon Taxes ◽  
Long Term Effects ◽  
Reactor Accident ◽  
Energy Supply System ◽  
High Investment ◽  
Market Evaluation ◽  
The Cost

The economic characteristics of nuclear power, with high investment cost and fuel costs lower than conventional fuels, make it possible to achieve low electricity prices when reactors supply marginal electricity. The support for nuclear power by the Swedish electricity consuming industry may be understood as efforts to create and defend a situation of over-capacity in the electricity production sector rather than as support for nuclear power as such. Politically the external costs of routine emissions of radioactive materials are difficult to internalise because they, like carbon dioxide, have global long-term effects. However, like the air pollutants already regulated, costs of reactor accidents, as well as the motives for taking on management costs of nuclear waste, are regional and within a generation in time. The market evaluation of accident risks has been deliberately destroyed by legislation set to favour nuclear power reactors. Societal economic rationality may be successfully applied in the energy sector. This paper describes how climate change risks were internalised in Sweden using carbon taxes under favourable political conditions. The resulting development of biofuels was surprisingly successful, indicating a potential for further modernisation of the energy supply system. Possible ways to restore the nuclear risk market in order to internalise nuclear reactor accident risks and waste costs by legislation are described. This may be done without the difficult quantification of environmental costs. Appropriate legislation may internalise the cost while creating conditions for market evaluation of these uncertain costs.

Questionnaire- and Measurement-Based Individual Thyroid Doses in Ukraine Resulting from the Chornobyl Nuclear Reactor Accident

2006 ◽  
Vol 166 (1) ◽  
pp. 271-286 ◽  
Author(s):  
I. Likhtarev ◽  
A. Bouville ◽  
L. Kovgan ◽  
N. Luckyanov ◽  
P. Voillequé ◽  
...  
Keyword(s):  
Nuclear Reactor ◽  
Reactor Accident

The reduction of I2 by H2O2 in aqueous solution

2001 ◽  
Vol 79 (3) ◽  
pp. 304-311 ◽  
Author(s):  
J M Ball ◽  
J B Hnatiw
Keyword(s):  
Aqueous Solution ◽  
Hydrogen Peroxide ◽  
Nuclear Reactor ◽  
Ph Dependence ◽  
Radiolysis Product ◽  
Molecular Iodine ◽  
Water Radiolysis ◽  
Reactor Accident ◽  
Rate Law ◽  
Accident Conditions

The reduction of I2 by hydrogen peroxide, a primary water radiolysis product, has been identified as a key reaction that would influence iodine volatility in nuclear reactor accident conditions (1–3). Although there have been a number of studies of the reduction of I2, there exists a great degree of controversy regarding the intermediates involved, the effect of buffers, and the general rate law (1–9). Because the rates and the mechanism of this reaction are important in predicting the pH dependence of iodine behaviour in reactor containment building after a postulated reactor accident, we have undertaken a kinetic study of I2 reduction by H2O2 in aqueous solution over a pH range of 6–9. The experiments were performed using stopped-flow instrumentation and monitoring the decay of I–3 spectrophotometrically. The effects of buffer catalysis have been examined by comparison of kinetic data obtained in sodium barbital (5,5-diethylbarbituric acid), disodium citrate, and disodium hydrogen phosphate buffers. The effect of buffers, combined with the complex acid dependence of the rate law, explains many of the discrepancies reported in earlier literature.Key words: hydrogen peroxide, molecular iodine, kinetics, iodine volatility.

Enhancing Probabilistic Risk Assessment Methodology for Solving Reactor Safety Issues

2003 ◽  
Author(s):  
F. L. Cho
Keyword(s):  
Nuclear Reactor ◽  
Severe Accident ◽  
Assessment Methodology ◽  
Reactor Safety ◽  
Reactor Accident ◽  
Safety Issues ◽  
Damage States ◽  
Baseline Information ◽  
Risk Assessment Methodology ◽  
Accident Sequences

This paper reveals a paradigm of analyzing the consequential effects of severe nuclear reactor accident, radionuclides fraction and source terms release, that will influence the MACCS2 codification [1], by coupling with the results of SAPHIA-PSA Levels l & 2 quantification process [2], MELCORE [3], STCP [4], PST [5], and XSOR [6]. Those codes are mutually exclusive and useful. However, it lacks of the closed interface and linkage for addressing Plant Damage States (PDS), Severe Accident Sequences, and Risk Consequence. Thus, it is imperative to formulate the consistent baseline information for MACCS2, PSA Levels 1, 2 and 3, and then linking to a new algorithm of NCM.

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