Radiation Detection And Measurement 4th Edition Knoll Pdf
Mary Gallery
Over the decade that has passed since the publication of the 3rd edition, technical developments continue to enhance the instruments and techniques available for the detection and spectroscopy of ionizing radiation. The Fourth Edition of this invaluable resource incorporates the latest developments and cutting-edge technologies to make this the most up-to-date guide to the field available:
GLENN FREDERICK KNOLL is Professor of Nuclear Engineering and Radiological Sciences in the College of Engineering at the University of Michigan. Following his undergraduate education at Case Institute of Technology, he earned a Master's degree from Stanford University and a doctorate in Nuclear Engineering from the University of Michigan. During his graduate work, he held national fellowships from the Atomic Energy Commission and the National Science Foundation.
He joined the Michigan faculty in 1962, and served as Chairman of the Department of Nuclear Engineering from 1979 to 1990 and as Interim Dean of the College of Engineering from 1995-96. He held appointments as Visiting Scientist at the Nuclear Research Center in Karlsruhe, Germany and as Senior Fellow in the Department of Physics at the University of Surrey, U.K. His research interest have centered on radiation measurements, nuclear instrumentation, and radiation imaging. He is author or co-author of over 140 technical publications, 8 patents, and 2 textbooks.
He has been elected a Fellow of the American Institute for Medical and Biological Engineering, the American Nuclear Society, and the Institute of Electrical and Electronics Engineers. He has been selected to receive three national awards given annually to a single recipient for achievements in engineering and education: the 1979 Glenn Murphy Award from the American Society for Engineering Education, the 1991 Arthur Holly Compton Award of the American Nuclear Society, and the 1996 Merit Award of the IEEE/Nuclear and Plasma Sciences Society. He is one of five receiving editors of Nuclear Instruments and Methods in Physics Research, Part A, and a past or present member of the Editorial Boards for Nuclear Science and Engineering, IEEE Transaction on Medical Imaging, and Physica Medica. In 1999, he was elected to membership in the National Academy of Engineering. He has served as consultant to 25 industrial and government organizations in technical areas related to radiation measurements, and is a Registered Professional Engineer in the State of Michigan. Permissions Request permission to reuse content from this site
Radiation Detection and Measurement, Fifth Edition,provides authoritative information on the instruments and techniques used for the detection and spectroscopy of ionizing radiation originating in atomic or nuclear processes. The most comprehensive textbook available on the subject, this classic volume contains detailed yet student-friendly coverage of radiation sources and interactions, counting statistics and error prediction, Geiger-Mueller Counters, ionization chambers, gamma ray detectors, and more.
The fifth edition contains new and revised material throughout, including up-to-date coverage of current scientific literature and leading-edge detection and measurement technologies. The text clearly explains the principles of operation and basic characteristics of a wide range of detector systems, including organic and inorganic scintillators, photomultiplier tubes, high-pressure xenon spectrometers, and lithium-drifted silicon detectors. Also available in enhanced eBook format, this leading textbook is ideal for first courses in nuclear instrumentation or radiation measurements, and a valuable review and reference guide for scientists and engineers actively involved in radiation measurements.
I am examining the detection limits in a case where my background is spatially varying and I am examining how to use that data set in determining detection limits. For example, I measure the radiation level in 100 different locations, where the background changes from location to location (100 different houses constructed of various materials). I now want to determine the detection limit for future studies of additional locations in the same general area. I have reviewed the statistics equation and thought about just using the measured standard deviation as the standard deviation of background (the square root of the average background count) instead of making the normal approximation. But that just seems too easy. What is the correct path? Also, is there a good reference for counting statistics when the background is varying by location and/or time in addition to the normal random probability fluctuations?
You cite the instance of measuring radiation levels in 100 different houses as an example. If you have observed variations in levels that are associated with differences in building materials, such causes of variability constitute nonrandom sources; they represent systematic sources of variation in measured readings. In such cases, you might be able to group the houses according to building materials, building design, or the like to define more than one population of test subjects, each population being subject to normal statistics. In these instances, each population (for example, wood-frame houses, brick houses, natural-stone houses) would be associated with its own normal statistics, such as a mean radiation level and an associated standard deviation. The experimental sample variance, which is the square of the standard deviation, may be calculated in the usual fashion from your respective set of N measurements, the ith measurement being defined as xi and the mean of the measurements being x:
If you believe that differences in construction materials are producing differences in measured radiation levels, you can perform statistical tests to evaluate whether the respective mean values of two subpopulations are in fact statistically different. If there are other influencing factors, such as notable changes in elevation, differences in geology, or time dependencies associated with measurable differences in radiation levels, these could also be considered in grouping of your measurement results. Minimizing the influences of systematic influences in this fashion may reduce the uncertainties associated with your measurements and provide for more powerful testing of real changes that might exist among measurements.
There are many textbooks and online sources available that deal with statistics. Many are not specific to radiation measurements, but the basic concepts discussed are often applicable. A couple of statistics texts that I have found useful are Data Reduction and Error Analysis for the Physical Sciences (Philip R. Bevington and D. Keith Robinson, McGraw-Hill Book Company, 1992) and Mathematical Statistics with Applications (Dennis D. Wackerly, William Mendenhall, and Richard L. Scheaffer, Duxbury Press, 1996). There are also useful discussions of commonly applied statistics in some of the more popular radiation science and protection textbooks, for example, Introduction to Health Physics: Fourth Edition (Herman Cember and Thomas E. Johnson, McGraw Hill, 2009) and Radiation Detection and Measurement, Fourth Edition (Glenn F. Knoll, Wiley, 2011). If you are a member of the Health Physics Society, you can also find several online sources on statistics available through the Members Toolbox. Click on "Members Login" on the HPS.org home page, sign in, and click on "HP Toolbox" and then "Statistics" under "Applied Topics."
Once you have determined the background characteristics, the mean and standard deviation for a given population, you can proceed to evaluate detection limits. Depending on the nature of the data being collected, the background data may be used to calculate the critical level, which defines the lower limit of radiation above background that is deemed statistically significant (see ATE answer to Question 6701 as an example of the calculation of critical level from count data). The lower limit of detection (and minimum detectable level) is a quantity larger than the critical level and obtainable from it. You or your employer may have other criteria that are to be used for defining a critical level and/or minimum detectable level, depending on your needs and intentions and the number of false conclusions you are willing to accept.
DESCRIPTION: In the aftermath of the Fukushima event it was learned that radioactive isotopes were in the water off the coast of the reactor site. Ships struggled to determine if the water they were sailing through had radioactive isotopes. This is important since large ships use water from the body of water they are sailing through on the ship for numerous uses. Having a detector on the water intake pipe taking regular measurements would inform the ship's crew of rising radiation levels in the water and thus make informed decisions on the next course of action to take. This is valuable to all large naval vessels that are concerned.The detector system should be readily repairable, will make measurements on the exterior surface of the pipe with no penetrations into the pipe, should be able to measure through varying thicknesses of pipe 1/4" up to 1", should use a less expensive crystal material for the detector, able to measure gamma rays in the range of 60 KeV to 3 MeV, able to run continuously for 1 year with minimal maintenance, and able to communicate data to a software application that records and reports the data via a cable or wireless communication.
PHASE III: This technology could be used on any water intake pipe or effluent pipe where detection of radiation is a concern, such as on ships in both fresh or salt water, water treatment facilities, nuclear power plant effluent systems, and other industrial facilities that process water with radioactive isotopes.
0aad45d008