This book provides an authoritative reference on all aspects of the nuclear energy enterprise for both fission and fusion reactors. Featuring 22 peer-reviewed chapters by recognized authorities in the field, the book offers concise yet comprehensive coverage of fundamentals, current areas of research, and goals for the future. Topics range from fundamental reactor physics calculations, reactor design, nuclear fuel resources, and the nuclear fuel cycle, to radiation detection and protection and the economics of nuclear power. All chapters have been updated from the first edition, with new chapters added on small modular reactors, medical applications - atomic and nuclear, an
Tsoulfanidis Measurement And Detection Of Radiation Pdf Download
As useful to students and nuclear professionals as its popular predecessors, this fifth edition provides the most up-to-date and accessible introduction to radiation detector materials, systems, and applications. There have been many advances in the field of radiation detection, most notably in practical applications. Incorporating these important developments, Measurement and Detection of Radiation, Fifth Edition provides the most up-to-date and accessible introduction to radiation detector materials, systems, and applications. It also includes more problems and updated references and bibliographies, and step-by-step derivations and numerous examples illustrate key concepts.
The measurements are performed using the CsI (Tl) scintillator detector model NT-812 as shown in Fig. 10. The MCNPX code is used to determine the attenuation coefficient through the simulation. By having the flux in the presence and absence of the radiation shield using (1), the radiation attenuation coefficient is obtained. The radiation attenuation coefficient is also calculated by using MCNPX code. In the MCNPX simulation, the arrangement of the detector (Fig. 9), radiation shield and source is exactly same as the experimental procedures arrangement in the laboratory according to Fig. 10. This is done to validate the simulation results in the optimal shield design using the MCNPX code.
In the experimental phase, the CsI (Tl) scintillator detector is applied regarding the higher efficiency for detection the gamma rays in comparison with the similar detectors like NaI (Tl), according to the experimental work, and. F2 Tally in the MCNPX is used to determine the flux. The radiation sources with different gamma energies tabulated in Table 8 are used for irradiation of the proposed shield, also. The configuration of this measurement is shown in Fig. 10 in which multiple shields are placed in front of the source and read by the detector.
The abovementioned statistical analysis is a lengthy, error prone and time-consuming process, which gets more tedious when the number of measurements increases. To the best of our knowledge, there is no dedicated open-source and easy-to-use software that is tailor-made for statistical analysis of GM counter data, and most researchers and students use tools such as Microsoft Excel, MATLAB, and other multi-purpose software to carry out statistical analysis of their experimental data. In the present work, we have developed an open-source graphical user interface (GUI) program named RadStat for statistical analysis of GM counter data. RadStat has its own specific scripting language to perform user defined statistical analysis. RadStat has been bundled with gnuplot ( ) for ease of plotting and visualization of the results. There are variety of tools and software that can perform general statistical analysis such as SPSS Statistics [15], SAS/STAT [16], Stata [17], Minitab [18] and many other packages. These software packages are for general statistical analysis and not dedicated to statistics of nuclear radiation. In addition, there are other tools that were developed for statistical analysis of nuclear radiation. For example, ROOT [19] is a powerful software framework written in C++ programming language that provides statistical analysis, data processing and visualization, however users need to learn and use C++ programming language to communicate with the program. The ADAQ framework [20] uses C++ and Python libraries and has been designed to streamline the acquisition and analysis of radiation detector data produced in digital data acquisition (DAQ) systems and in Monte Carlo detector simulations; this software mainly focuses on data acquisition and lacks in-depth statistical analysis functions. InterSpec [21] is a native or web application to assist in analyzing spectral nuclear radiation data, using a peak-based methodology; this software would be useful in identifying radionuclides, source age and activity, shielding amounts and dose rate calculations by feeding the obtained spectrum into the software. In comparison, RadStat is easy to use, since no programming knowledge would be required, and the statistical features provided by RadStat would be useful for early learners in this field to verify the statistics involved in nuclear radiation measurements.
The fluctuations arising from the counting statistics represent an unavoidable source of uncertainty in all nuclear radiation measurements; these fluctuations can be quantified and compared with the predictions from statistical distributions such as Poisson and normal distribution [26]. Previously, Tsoulfanidis and Landsberger [27] provided a detailed description on the statistical analysis process in nuclear radiation measurements and provided all the required steps; these were implemented in the RadStat computer program. To the best of our knowledge, there is no software like RadStat computer program which is tailor-made for statistical analysis of counts from nuclear radiation measurements that has the ease of use, functionality and its own syntaxes. 2ff7e9595c
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