[en] The Q system described here represents a development and extension of the earlier A₁/A₂ system. It incorporates the latest recommendations of the ICRP and by explicitly identifying the dosimetric considerations underlying the derivation of Type A package limits provides a firmer and more defensible basis for the IAEA Transport Regulations. Overall the use of the Q system introduces only relatively minor variations in the A₁ and A₂ values compared with those in the current Regulations. Where major variations in the Type A package contents limits for beta emitters determined by Q/sub B/ and particularly Q/sub D/. Isolated relaxations in the contents limits occur due to changes in dosimetric data introduced in ICRP Publication 30, as in the case of ⁹⁰Sr, and more generally in the case of special form alpha emitters due to the revised definition of Q/sub F/. 18 references

[en] The results of the radiological impact studies, the data on shipments and the feedback from compliance assurance actions will help identify any shortcomings or weaknesses in the Regulations. The Advisory Material and the Explanatory Material, by amplifying the various requirements and elaborating the purpose and reason(s) for them, will help users understand the Regulations. These documents may also help motivate users. Quality Assurance will help prevent problems in the implementation process. Compliance Assurance will detect and lead to the rectification of failures in the implementation process. The data transfer on Certificates will aid in stopping the use of unsafe packages. 17 references

[en] The following licensing problem areas are discussed: interpretation of the regulations; relevant experience; design standards; relevance to safety; data base; calculative methods; reasoned argument; testing requirements; modelling standards; and acceptance criteria

[en] Shipment of UF₆ enriched to 1.0% or greater assay ²³⁵U currently is done in either the 30-B overpack or the Paducah tiger overpack. The former contains a 2-1/2 ton cylinder, 30 in. in diameter, while the latter contains a 10-ton cylinder, 48 in. in diameter. There are apparent economy and safety considerations associated with shipping in the larger containers due to the reduced number of shipments and connect and disconnect operations. Further reductions in connect and disconnect operations and shipping costs could be achieved through use of the 14-ton cylinder for shipment of enriched material. With this thought, a program was initiated in 1980 to develop a protective overpack for the Model 48Y cylinder. Two prototype overpacks of wood and stainless steel construction were fabricated. The results from the drop tests and the thermal exposure test are presented

[en] This paper addresses the problem of uranium hexafluoride transportation by truck and train. It consists of a probabilistic risk assessment of the potential hazards to the public that can arise from the traffice that will take place in France in 1990. The specificity of UF₆ is that it presents both chemical and radiological hazards. But, whatever the transported material, road traffic entails a risk of its own. Thus three kinds of risk are assessed for natural, depleted and enriched uranium hexafluoride. These assessments are the basis of a cost-effectiveness analysis which deals with such safety measures as using a protective overpack, avoiding populated area and escorting the trucks. The results presented here are based upon research supported by the C.E.A. (Commissariat a l'Energie Atomique). It is linked to a more general program of experiments and theoretical analyses on package safety and accidental releases for uranium hexafluoride. 7 references, 2 figures, 4 tables

[en] The different concepts of the back-end of the fuel cycle existing in the Federal Republic of Germany require that various types of radioactive materials will be transported along different pathways, for various distances and at different frequencies, thus resulting in different risks to the public. In one part of the second phase of the R + D program Projekt Sicherheitsstudien Entsorgung (PSE), the risk during normal and accident conditions will be assessed for each of the concepts of the back-end of the fuel cycle. Within this part of the safety analysis, DORNIER SYSTEM will determine the risks resulting from the transport of radioactive materials by truck, using the probabilistic method of fault tree analysis. This part of the investigation will extend until the end of 1983. 4 references, 5 tables

No abstract available

[en] With regard to the final storaging of metallic LLW from decommissioning projects, packaging into box type containers shows a variety of advantages compared to the raditionally used drum types. The design of a module container system presented herein is in line with German and IAEA requirements for transportation and final storaging into a mine. Special regard was given to the waste activity and packaging process and results in a decision chart to facilitate the selection of the appropriate container type according to the job specific necessities. 3 references, 7 figures

[en] The aim of this paper is the evaluation of individual and collective doses to transport workers and general public from the shipments of radioactive materials in Italy. The data concerning the shipments by road of radioisotopes for medical uses in the years 1981-1982 were collected and the standard shipment lists were compiled. In the standard shipment list the number of packages of each radioisotope, the average transport index and the average mileage per shipment are collected. We wish to underline that there is no substantial increase in the number of packages transported per year, and the percentage of packages among the three categories is around 50% White I, 30% Yellow II, 20% Yellow III. A statistical sampling was also carried out on packages; it appeared that for packages of Yellow III category the average radiation level at surface was 100 mrem/h at the 0.7 TI; while Yellow II category packages showed a radiation level of 30 mrem/h at the surface and 0.2 TI

[en] The availability of statistical data on the activity in the shipment of radioactive materials (RAM) is very useful both to evaluate the adequacy of the regulations set up at the international level and to assess the collective dose deriving from the transport either under normal or accident conditions. Because of this need for data, the IAEA requested that Member States collect statistical data on national and international transport of RAM. Collection of data will be completed by the end of 1983. 1 figure, 3 tables