Ram Venkataraman

Nuclear measurement technologies & solutions implemented during nuclear accident at Fukushima

Fukushima accident imposed a stretch to nuclear measurement operational approach requiring in such emergency situation: fast concept development, fast system integration, deployment and start-up in a very short time frame. This paper is describing the Nuclear Measurement that AREVA-BUNM (CANBERRA) has realized and foresight at Fukushima accident site describing the technical solution conceived developed and deployed at Fukushima NPP for the process control of the treatment system of contaminated water. A detailed description of all levels design choices, from detection technologies to system architecture is offer in the paper as well as the read-out and global data management system. This paper describes also the technical choices executed and put in place to overcome the challenges related to the high radiological contamination on site.

Minimum detectable activity, systematic uncertainties, and the ISO 11929 standard

The Currie formulation for minimum detectable activity (MDA) has served for decades as the standard method for estimating radiological detection limits-it is simple and statistically defendable. It does, however, lack a means to account for the effects of systematic uncertainties. In recent years we have seen various efforts to incorporate systematic uncertainties into an MDA framework. Perhaps most notable of these is the recent ISO standard 11929 for the determination of characteristic limits in ionizing radiation measurements. This standard brings a Bayesian perspective to the problem of characteristic limits in radiation measurements that are in many ways both welcome and long overdue. In this paper, however, we note some apparent drawbacks to the ISO 11929 approach. Namely, for small values of the systematic uncertainty the correction it makes to the Currie MDA is negligible, while for large systematic uncertainties the calculated MDA values can become infinite. In between these two extremes, the user has little basis for evaluating the reliability of the result. To address these issues, we consider the problem from a new approach, developing a straightforward phenomenological statistical model of the MDA that treats systematic uncertainties explicitly. We compare predictions from our model with results of the ISO 11929 formulation as well as the traditional Currie approach. Finally, some recommendations for alternative handling of the MDA in the face of significant systematic uncertainties are presented.

Mathematical efficiency calibration methods for high quality laboratory based gamma spectrometry systems

The efficiency calibration of laboratory based gamma spectrometry systems typically involves the purchase or construction of calibration samples that are supposed to represent the geometries of the unknown samples to be measured. For complete and correct calibrations, these sample containers must span the operational range of the system, which at times can include difficult configurations of size, density, matrix, and source distribution. The efficiency calibration of a system is dependent not only on the detector, but on the radiation attenuation factors in the detector–source configuration, and therefore is invalid unless all parameters of the sample assay condition are identical to the calibration condition. An alternative to source-based calibrations is to mathematically model the efficiency response of a given detector–sample configuration. In this approach, the measurement system is calibrated using physically accurate models whose parameters can generally be easily measured. Using modeled efficiencies, systems can be quickly adapted to changing sample containers and detector configurations. This paper explores the advantages of using mathematically computed efficiencies in place of traditional source-based measured efficiencies for laboratory samples, focusing specifically on the possibility of sample optimization for a given detector, uncertainty estimation, and cascade summing corrections.

Gamma spectroscopy with automated efficiency optimization for nuclear safeguards applications

In all applications of gamma-ray spectroscopy, one of the important parts of the data analysis is to measure the detection efficiency which depends on the geometrical conditions of the source-detector arrangement. As the samples commonly measured can vary greatly in volume and shape, it is impractical to manufacture standard sources for large and complex measurement items and packagings for the purpose of efficiency calibration. Canberra Industries developed the mathematical efficiency software called In Situ Object Calibration Software (ISOCS) to overcome the difficulties presented above. Recently, Canberra has extended the capability of ISOCS and has developed a software package for the International Atomic Energy Agency (IAEA) that simplifies, automates, and optimizes mathematical efficiency analysis for a given set of experimental parameters. The new optimization software called the “Advanced-ISOCS” varies the “not well known” parameters of the source geometry within user specified intervals and determines the optimal efficiency. The efficiency optimization capability is carried out using either a random search based on standard probability distributions or using numerical technique that carry out more directed search. The radionuclide mass is determined using the optimum efficiency and compared against the known mass. Results of optimizations carried out using the numerical technique are presented in this paper.