Material Verification Program

A Material Verification Program is essential to Process Safety. Investigators recommended that management implement the recently developed procedures/guidelmes for a materials verification program. 

The hybrid K-edge densitometer (HKED) turned out to find quicker applications for safeguards verifications (Ottmar et al. 1986 Ottmar and Eberle 1991) at the input of spent fuel reprocessing plants, as the sample needs neither a dilution nor any treatment before measurement. The technique, considered as an NDA method and described in Sect. 63.3.1, is installed in particular in on-site analytical laboratories and operated by analytical chemists on duty there. Operators have found the instrument so practical and reliable that they use it in their nuclear material accountability program (Brousse et al. 1993). The HKED fluorescence channel is also used for DA of Th or mg-size Pu samples. 

More specifically, the basic notions of a Turing Machine, of computable functions and of undecidable properties are needed for Chapter VI (Decision Problems) the definitions of recursive, primitive recursive and partial recursive functions are helpful for Section F of Chapter IV and two of the proofs in Chapter VI. The basic facts regarding regular sets, context-free languages and pushdown store automata are helpful in Chapter VIII (Monadic Recursion Schemes) and in the proof of Theorem 3.14. For Chapter V (Correctness and Program Verification) it is useful to know the basic notation and ideas of the first order predicate calculus a highly abbreviated version of this material appears as Appendix A. 

In this chapter we discuss techniques for program verification and their mathematical justification. The basic idea behind these methods was originally presented by Floyd mathematical formulations and logical justifications were developed by Cooper and Manna, and others, and continued in King s Ph.D. thesis in which he presented the development of a partial implementation for these techniques. A sanewhat different axiomatic approach has been pursued by Hoare et al. The reader who has never made acquaintance with the formalism of the first order predicate calculus should at this point turn to Appendix A for a brief and unrigorous exposition of the material relevant to this chapter. 

Design Qualification (DQ) is the first validation element of a new facility system or equipment, where adherence to the user s specifications and to GMP rules is demonstrated. Installation Qualification (IQ) follows with the verification of adequacy of the area, installation of equipment pipelines, utilities, instrumentation, and conformity of the material used to the project specifications. At the Operational Qualification (OQ) phase, carried out after installation of all equipment, it is verified whether the system, when in operation, complies with the acceptance criteria defined in the validation plan. Once the OQ phase is successfully finalized it is possible to proceed with the calibration procedures, operation and cleaning, operator training, and preventive maintenance program. After IQ and OQ are concluded, it is time for the Performance Qualification (PQ), with the aim of verifying that what was designed, built, and operated results in a product that meets the expected specifications. Production and QC personnel are specially trained for these assessments. The tests can be done with the product of interest or a placebo, and are related to all operations, from raw material reception to product release (EC, 2001). 

Quality assurance is part of the regulations specified by the national standards organizations such as the Nuclear Regulatory Commission. Quality assurance applies to any material or component or a fabricated structure in the sense that their satisfactory performance in service conditions is assured. The quality assurance and control programs in Canada are contained in Canadian Standards Association document CAN3-Z 299.1-85 consisting of four parts. The four parts of the standard are such that Part 1 covers quality assurance, Part 2 refers to quality control, Part 3 refers to quality verification, and Part 4 deals with quality inspection. 

However, it is still necessary to consider whether it is possible to perform easily all transport-property measurements that industry requires. Let us assume that we need to measure only three properties at just 10 temperatures and 10 pressures, for 15 pure fluids and all their possible multicomponent mixtures, at five compositions in the liquid and gas phases. Then, the total number of measurements required is of the order of 10 (3x10x10x32766x5x2). If one further assumes that one can perform three measurements per day, then it is obvious that even for the above program of measurements, 90.000 man-years will be required and it considered only 15 materials from among the set of several thousand involved routinely in industry. It is clear that measurement alone cannot serve the industrial appetite for transport property data. Nevertheless, accurate measurements will continue to be vital for the verification of theory and the validation of predication. 

To facilitate a full systems approach to designing physical protection from CB threats by 2020 will require coordination with academic curricula and research programs. Effective integration of sensor data with material response will need directed research and development, as will verification and validation programs of these systems. Appropriate infrastructure - testing facilities and equipmenf and enhanced supercomputing facilities - may be focused on this problem domain at DoD and Department of Energy laboratories. 

This Handbook consists of two volumes. Voliune 1 contains the core material, including a discussion of the elements of a quality chemical program and information on applicable DOE, Occupational Safety and Health Administration (OSHA) and Environmental Protection Agency (EPA) directives, standards, and requirements. The appendices to Volume 1 contain sample lines of inquiry, which may be used for ISM verification lessons learned to allow readers an opportunity to learn from the experiences of their peers and a listing of program resources. 

It is clear that although the exponential pile and criticality experiments would be required ultimately in any large-scale reactor development program, it would be desirable to obtain some preliminary experimental verification of reactor calculations by means of other more modest tests. One experiment which appears to be eminently suited to this purpose is based on the pulsed neutron-beam technique. This technique has been applied by several investigators to the determination of the thermal-diffusion coefficient and macroscopic absorption cross sections of reactor materials.More recently, it has been used by E. C. Campbell and P. H. Stelson in the study of short-lived isomers and for the measurement of reactor parameters of multiplying media. The experiment con-... 

Note A2.3—Materials, purities, flash point values and limits stated in Table A2.1 were develop in an ASTM interiaboratoiy program (see RR SI5-1010) to determine suitability of use for verification fluids in flash p( test methods. Other matmials, purities, flash point values, and Ufflits can be suitable when produced acooiding to the practices of ASTM RR D02-I0()7 or ISO Girides 34 and 35. Certificates of performance of such materials should be consulted before use, as the flash point value wUl vary dependent on the condition of each CRM batch. 

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