Instrumentation nuclear plant

The sampling of nuclear materials and the packaging of samples are very critical steps in the measurement process. Differing conditions at nuclear plants dictate the need for a variety of sample-taking and handling procedures before samples are sent for analysis. SAL has developed a set of procedures that take account of local conditions, and has been instrumental in improving the overall quality of the verification of uranium and plutonium samples. 

Avila, S.M. Horvath, D.A. Microscopic void detection as a prelude to predicting remaining life in electric cable insulation. International Topical Meeting on Nuclear Plant Instrumentation, Controls and Human-Machine Interface Technologies (NPIC HMIT 2000), Washington, DC, Nov 2000. 

The selectivity of fluorescence generally helps in avoiding the need for multi-wavelength measurements. However, a knowledge of the intensity ratio at two wavelengths is often recommended. The identiHcation of the half-life of the species to be analyzed is also a factor in selelctivity. Thus, time spectrometric instruments with pulsed lasers and photodiode arrays are ideal for process control. A recent example was given for the in-line control of traces of uranium in nuclear plants [175]. 

One major aspect of this price risk is the risk associated with the CO2 price. Indeed the attractiveness of a nuclear plant as a power producer will increase as a result of the additional cost placed on fossil fuel generation technologies by climate policies, which is reflected in the marginal price on hourly electricity markets. But CO2 policy based on a quantity instrument such as cap and trade , rather than a price instrument (CO2 tax), introduced a fundamental uncertainty to COj price. The risk is also largely... 

The International Nuelear Event Seale (INES) was eoneeived as an instrument for eommunicating to the publie, in a rapid and eoherent way, the severity of the events which take place at nuclear plants. 

Thunem, H. P-J, Hoffmann, M. Roverso, D. (2009). Mimir - A Modular Framework for Condition Monitoring and Diagnostics, Sixth American Nuclear Society Internationa Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies NPIC HMIT 2009, April 5-9, 2009, Knoxville, Tennessee. 

Chang, Y. H., Coyne, K., Mosleh, A. (2006). A Nuclear Plant Accident Diagnosis Method to Support Prediction of Errors ofCommission. Paperpresented at the American Nuclear Society Nuclear Plant Instrumentation, Control and Human-Machine Interface Technology Conference (NPIC HMIT 2006), Albuquerque, New Mexico. 

As a result of the analysis of events during the accident at the Three Mile Island nuclear plant (TMI, March 1979), the importance of human error in nuclear plants was better understood. The accident resulted from the confusion of the control room operators with inadequate instrumentation and inaccurate procedures. The most important factor was that they had to act in spite of the weaknesses in the training to respond to unexpected events. Therefore, the United States Nuclear Regulatory Commission (USNRC) called for the improvement of Emergency Operating Procedures (EOPs) and in nuclear reactor operator training. The philosophy of incident response implemented in the improved procedures was to take a symptom-based approach (operators foUow a series of yes - no questions to ensure that the reactor core remains covered and only then determine what was the cause of the problem) (USNRC, 2009). 

Draft ANS 4.5 D2, "Standard for accident monitoring instrumentation for nuclear plants. ... 

A number of elements are required to support a new or existing nuclear plant. Suppliers and fabricators of nuclear fuel and safety-related components are clearly essential, as are suppliers of balance-of-plant equipment, construction materials, electronics and instrumentation, and coundess other components. 

X. Colin, C. Monchy-Leroy, L. Audouin, J. Verdu. Lifetime prediction of polyethylene in nuclear plants. Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms 265(1), 251-255, December (2007). 

Trojovsky, M. and S. R. Brown, Data Summaries of Licensee Event Reports ui selected Instrumentation and Control Components at U.S. Commercial Nuclear Power Plants. January 1, 1976-December 31, 1981, Re vision 1, EG G, July 1984. 

Data boundary The equipment types for whieh data are presented in the resource (such as pipelines, valves or instruments) plant type (coal gasification facility, nuclear or ammonia plant, for example). 

The data on probabilities given in this example are for illustration only, and do not represent actual data for these components. Some quantitive data on the reliability of instruments and control systems is given by Lees (1976). Examples of the application of quantitive hazard analysis techniques in chemical plant design are given by Wells (1996) and Prugh (1980). Much of the work on the development of hazard analysis techniques, and the reliability of equipment, has been done in connection with the development of the nuclear energy programmes in the USA (USAEC, 1975) and the UK. 

Wainerdi, R. E., and M. P. Menon Comparison of Nuclear Activation Methods for Bromine. Instrumental Analysis of Pesticides in Plant Materials Close to the Limit of Sensitivity. Proceedings of the 1967 Symposium, Nuclear Activation Techniques in the Life Sciences, Amsterdam, May 8—12, 1967, pp. 33—50. Vienna International Atomic Energy Agency 1967. 

---