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1.1 This test method describes the nondestructive assay of scrap or waste for plutonium content using passive thermal-neutron coincidence counting. This test method provides rapid results and can be applied to a variety of carefully sorted materials in containers as large as 208-L drums. The test method applies to measurements of 238Pu, 240Pu, and 242Pu and has been used to assay items whose total plutonium content ranges from 0.01 to 6000 g (1).1.2 This test method requires knowledge of the relative abundances of the plutonium isotopes to determine the total plutonium mass.1.3 This test method may not be applicable to the assay of scrap or waste containing other spontaneously fissioning nuclides.1.3.1 This test method may give biased results for measurements of containers that include large amounts of hydrogenous materials.1.3.2 The techniques described in this test method have been applied to materials other than scrap and waste (2, 3).1.4 This test method assumes the use of shift-register-based coincidence technology (4).1.5 Several other techniques that are related to passive neutron coincidence counting exist These include neutron multiplicity counting (5,6), add-a-source analysis (7), and cosmic-ray rejection (8). Discussions of these techniques are not included in this method.1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.
1.1 This test method covers the nondestructive assay of scrap and waste for uranium and plutonium content using a 252Cf shuffler. Shuffler measurements provide rapid results and can be applied to a variety of matrix materials in containers as large as 208-litre drums. Corrections are made for the effects of matrix material. This test method has been used to assay items containing uranium, plutonium, or both. Applications of this test method include measurements for safeguards, accountability, TRU, and U waste segregation, disposal, and process control purposes (1,2,3).1.1.1 This test method uses passive neutron coincidence counting to measure 238Pu, 240Pu, and 242Pu. It has been used to assay items with plutonium contents between 0.03 g and 1000 g. It could be used to measure other spontaneously fissioning isotopes. It specifically describes the approach used with shift register electronics; however, it can be adapted to other electronics. 1.1.2 This test method uses neutron irradiation with a moveable californium source and counting of the delayed neutrons from the induced fissions to measure 235U. It has been used to assay items with 235U contents between 0.1 g and 1000 g. It could be used to assay other fissionable isotopes.1.2 This test method requires knowledge of the relative isotopic composition to determine the mass of the different elements.1.3 This test method may give biased results for measurements of containers that include large quantities of hydrogen.1.4 The techniques described in this test method have been applied to materials other than scrap and waste. These other applications are not addressed in this test method.1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use. Specific precautionary statements are given in Section 8.
1.1 This test method covers a system that performs nondestructive assay (NDA) of uranium or plutonium, or both, using the active, differential die-away technique (DDT), and passive neutron coincidence counting. Results from the active and passive measurements are combined to determine the total amount of fissile and spontaneously-fissioning material in drums of scrap or waste as large as 208 L. Corrections are made to the measurements for the effects of neutron moderation and absorption, assuming that the effects are averaged over the volume of the drum and that no significant lumps of nuclear material are present. These systems are most widely used to assay low-level and transuranic waste, but may also be used for the measurement of scrap materials. While this test method is specific to the second-generation Los Alamos National Laboratory (LANL) passive-active neutron assay system, the principle applies to other DDT systems.1.1.1 In the active mode, the system measures fissile isotopes such as 235U and 239Pu. The neutrons from a pulsed, 14-MeV neutron generator are thermalized to induce fission in the assay item. Between generator pulses, the system detects prompt-fission neutrons emitted from the fissile material. The number of detected neutrons between pulses is proportional to the mass of fissile material. This method is called the differential die-away technique.1.1.2 In the passive mode, the system detects time-coincident neutrons emitted from spontaneously fissioning isotopes. The primary isotopes measured are 238Pu, 240Pu, and 242Pu; however, the system may be adapted for use on other spontaneously-fissioning isotopes as well. The number of coincident neutrons detected is proportional to the mass of spontaneously-fissioning material.1.2 The active mode is used to assay fissile material in the following ranges.1.2.1 For uranium-bearing items, the DDT can measure the 235U content in the range from 0.02 to over 100 g. Normally, the assay of items bearing only uranium is performed using matrix-specific calibrations to account for the effect of the matrix on the active signal.1.2.2 For plutonium-bearing items, the DDT method measures the 239Pu content in the range between 0.01 and 20 g.1.3 The passive mode is capable of assaying spontaneously-fissioning nuclei, over a nominal range from 0.05 to 15 g of 240Pu, or equivalent. The passive mode can also be used to measure large (for example, kg) quantities of 238U.1.4 This test method requires knowledge of the relative abundances of the plutonium or uranium isotopes to determine the total plutonium or uranium mass.1.5 This test method will give biased results when the waste form does not meet the calibration specifications and the measurement assumptions presented in this test method regarding the requirements for a homogeneous matrix, uniform source distribution, and the absence of nuclear material lumps, to the extent that they effect the measurement.1.6 The complete active and passive assay of a 208 L drum is nominally 10 min or less.1.7 Improvements to this test method have been reported (1,2,3 ,4 ). Discussions of these improvements are not included in this test method.1.8 This standard may involve hazardous materials, operations, and equipment. This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use. Specific precautionary statements are given in Section 8.
This part 1 of the report is related to the four heavy metals specified in Art. 11 of the Directive: lead, cadmium, chromium (VI) and mercury. A second part of this CEN-report is related to the need to assess other dangerous substances present in packaging.
To update the terms and definitions to be used in CEN/TC 132 standards. The document defines general terms which are helpful for the communication within the aluminum industry and its customers relating to products of aluminium and aluminium alloys. Definitions in other standards applying to a particular field of application can be more specific than the definitions of identical terms in this standard; these can be found in the relevant standards.
This Technical Report provides some examples of substances and materials that may cause a sustained impediment in the recycling activities, and is intended to assist in the assessment requirements set out in the standard EN 13430. It describes substances or materials which cause problems or inhibit the recycling process, or which have a negative influence on the quality of recycled material, and for which it is considered that technological solutions will not be developed in the near future. These examples are however qualified by the fact that the recycling operations can vary from region to region and state to state, that technology is constantly changing, and that the use to which the recycled material is put will also determine whether such substances and materials are a problem.
This standard specifies characteristics, form, chemical composition and metal yield of scrap consisting of a mixture of used aluminium packagings. This mixture includes aluminium foil laminated with paper or plastics having a metal yield less than 28 %.
This European Standard contains definitions of terms related to scrap of aluminium and aluminium alloys which are helpful for the communication within the aluminium industry and between the industry and the authorities.\nDefinitions of general terms which are helpful for the communication within the aluminium industry are laid down in EN 12258-1.\nNOTE 1 In some terms and definitions \"aluminium\" is used for \"aluminium and aluminium alloys\".\nNOTE 2 Definitions of other standards or regulations applying to a broader field of application which includes the field of application of this Standard can be more general than the definitions of identical terms in this standard; they can be found in the relevant documents.\nNOTE 3 The definitions of terms indicating different types of scrap do not contain requirements, e. g. on metal yield or chemical composition related to the scrap category to which this type of scrap belongs.\nA glossary (Clause 10) comprises all terms which are defined in this Standard and their translations in alphabetical order.
This European Standard specifies requirements and procedures to determine the compostability and anaerobic treatability of packaging and packaging materials by addressing four characteristics :\n1) biodegradability,\n2) disintegration during biological treatment,\n3) effect on the biological treatment process and\n4) effect on the quality of the resulting compost.\nIn case of a packaging formed by different components, some of which are compostable and some other not, the packaging itself, as a whole is not compostable. However, if the components can be easily separated by hand before disposal, the compostable components can be effectively considered and treated as such, once separated from the non compostable components.\nThis European Standard covers the compostability of packaging itself but does not address regulations that may exist regarding the compostability of any residual contents.\nThis European Standard makes provision for obtaining information on the processing of packaging in controlled waste treatment plants but does not take into account packaging waste which may end up in the environment, through uncontrolled means, i.e. as litter.\nThe essential relationship between this European Standard and the four other (mandated) European Packaging Standards and one (mandated) CEN Report is specified in EN 13427:2000.
This European Standard establishes a methodology for the calculation of the rate of recycling of packaging and packaging material.\nNOTE The packaging supply chain also uses other ratios in the management of their operations. The flow diagrams used in the methodology set out in this European Standard can be used in the evaluation of such other ratios and examples are given.
This European Standard specifies characteristics, form, chemical composition and metal yield of scrap consisting of a mixture of used aluminium packagings. This mixture includes aluminium foil laminated with paper or plastics having a metal yield less than 28 %.\nEXAMPLE Mix of pet food containers and lids, food cans, semi-rigid containers such as those used for catering, domestic\nuse or distribuition, wrapping aluminium foil for household or commercial applications, beverage containers, yoghurt lids, spray containers, bottle caps, coffee pouches, etc.
This European Standard specifies characteristics, chemical composition and metal yield of decoated aluminium scrap obtained by decoating mixed used aluminium packagings through various processes, e.g. pyrolysis, mechanical delamination, chemical delamination or a combination of these. It also applies to aluminium scrap separated from the bottom ashes of incinerators.\nEXAMPLE A mix of used aluminium packaging scrap of different alloys which were decoated to be used for melting or other forms of metal recycling.