Showing papers in "International Journal of Radioactive Materials Transport in 1997"
117 citations
TL;DR: In this paper, the authors proposed a new generation of ISO freight container, Design No. 2044, which incorporates a readily decontaminable stainless steel interior, a comprehensive load load distribution, and high force compaction techniques.
Abstract: Solid low level radioactive waste (LLW) which arises at nuclear power stations and other nuclear facilities in the UK, is routinely transported to British Nuclear Fuels site at Drigg in Cumbria for disposal. A requirement was identified for the use of an ISO freight container of the full-height design, to transport drummed LLW to the site of a supercompaction facility prior to disposal at Drigg. This was initially accomplished using refurbished containers incorporating a number of enhanced features. It was recognised that the use of a refurbished container was only an interim measure and as a result of significant changes in the acceptance criteria for disposal, the increased use of high force compaction techniques and the proposed amendments to the IAEA Transport Regulations, Nuclear Electric embarked upon the development of a new generation of ISO freight container. The new design of container, Design No. 2044, incorporates a readily decontaminable stainless steel interior, a comprehensive load ...
38 citations
TL;DR: In this paper, the main characteristics of such cask designs and important tests performed with DCI casks during the past six years are discussed in more detail, including the design concept of the CASTOR V/HAWC cask to be used for the transport of high-level radioactive waste concentrates, the evaluation of DCI material properties, and problems arising from the simulation of the mechanical IAEA tests by computer code analyses.
Abstract: Large Type B packages used in Germany for the transport of spent reactor fuel and high activity radioactive waste are mostly manufactured from ductile cast iron (DCI) An overall view is given about the main characteristics of such cask designs and important tests performed with DCI casks during the past six years Selected topics discussed in more detail are the design concept of the CASTOR V/HAWC cask to be used for the transport of high-level radioactive waste concentrates, the evaluation of DCI material properties, and problems arising from the simulation of the mechanical IAEA tests by computer code analyses
5 citations
TL;DR: In this paper, the main features of the Intertran 2 are discussed and the methodology adopted for the assessment of radiation dose which could be received by transport workers and the public in certain situations due to radioactive shipments is briefly analyzed.
Abstract: The main features of the computer code, Intertran 2 are discussed. The methodology adopted for the assessment of radiation dose which could be received by transport workers and the public in certain situations due to radioactive shipments is briefly analysed. The advantages as well as the limitations of the code are pointed out.
4 citations
TL;DR: The 1996 edition of the International Atomic Energy Agency's regulations for the Safe Transport of Radioactive Material has been published and is being implemented by Member States and international transport organisations as mentioned in this paper.
Abstract: The 1996 Edition of the International Atomic Energy Agency's Regulations for the Safe Transport of Radioactive Material has been published and is being implemented by Member States and international transport organisations. Several major changes were made in the requirements, particularly those applicable to uranium hexafluoride packaging, air transport of larger quantities of material, and the specification of material which is exempt from the regulations. The international transport organisations are working toward a uniform effective implementation date of 1 January 2001. Shippers and carriers should begin preparation for compliance with the revised requirements in order to ease implementation.
3 citations
TL;DR: In this paper, a cubic multipurpose container made of ferritic ductile cast iron (DCI) is investigated for the most critical container accident scenarios, a drop from 5 m height flat onto the ground of the German Konrad repository without additional impact limiters and a one hour fire with an average temperature of 800°C.
Abstract: A cubic multipurpose container made of ferritic ductile cast iron (DCI) is investigated for the most critical container accident scenarios, a drop from 5 m height flat onto the ground of the German Konrad repository without additional impact limiters and a one hour fire with an average temperature of 800°C. For the mechanical drop test analysis BAM has developed special finite element modelling for numerical calculation of container stresses as the result of such a violent impact. The calcu- lation results are compared with representative strain measurement data from several drop tests with an original prototype con- tainer. Referring to the fire test scenario the results from thermal tests by BAM with an original prototype container loaded with representative but inactive ion exchanger resin are presented and discussed.
3 citations
TL;DR: InterTRAN 2 as discussed by the authors is an improvement upon its earlier version, INTERTRAN, and is available in a user-friendly PC version, which can handle 20 categories of accident severities and uses PSA techniques.
Abstract: The computer code, INTERTRAN 2 which has been developed by IAEA under a recently concluded Co-ordinated Research Programme is an improvement upon its earlier version, INTERTRAN, and is available in a user-friendly PC version. It can handle 20 categories of accident severities and uses PSA techniques. The code can be used for assessing the dose commitment from transport of radioactive materials. It can be employed for selecting and optimising the mode of transport and the route. This paper explores the capabilities of INTERTRAN 2 and cites some examples.
3 citations
TL;DR: In this paper, the authors established an evaluation method for high temperature water leakage rates from wet-type transport casks of spent fuel in light-water nuclear power plants, and they investigated the leakage paths of water at high pressure and temperature with leak paths simulated by very narrow orifices and capillary tubes whose configuration and dimension are known.
Abstract: In Japan, as part of the development programmes for light water reactors, a programme for enhancement of fuel burnup in the core is being promoted in order to reduce the fuel cost and to minimise the amount of spent fuel generation. To be consistent with this attempt, a new wet-type cask has been developed for effective transport of high burnup spent fuels. The aim is to establish an evaluation method for high temperature water leakage rates from wet-type transport casks of spent fuel. Leakage rates of water at high pressure and temperature are investigated with leak paths simulated by very narrow orifices and capillary tubes whose configuration and dimension are known. From the results, the flashing inception condition of superheated water and the effect of the flashing on water leakage rates are clarified, and an evaluation method for the leakage rates of high temperature and high pressure water is proposed.
2 citations
TL;DR: In this paper, a new 20' box container, designed by the firm CORROBESCH/STM as a Type A package for the transport of radioactive and other dangerous materials, and having a carrying capacity of 22 tons, is presented.
Abstract: A first technical report is presented on a new 20' box container, designed by the firm CORROBESCH/STM as a Type A package for the transport of radioactive and other dangerous materials, and having a carrying capacity of 22 tons. The container itself weighs only 4 tons, and it incorporates a proprietary corrosion finish that is highly resistant to mechanical wear, deformation, and radioactive contamination. The Type A Package, which also can be used as industrial package Type 2 and Type 3, is designed to withstand accelerations of up to 6g. This design criterion was established based on the European Railroad Associations requirement of considering dynamic loads of 4g arising during routine transport times a safety factor of 1·5. In contrast, the ISO Norm 1496, part 1, does not require explicit consideration of dynamic loads but only requires a static load test. Therefore, the main motivation behind the dynamic load design criteria was the complete lack of freight containers capable of withstanding ...
2 citations
TL;DR: In this paper, the authors implemented a four-year investigation into the behaviour of tie-down systems, which was funded by the Department of Trade and Industry and carried out by AEA Technology.
Abstract: UKAEA has implemented a four year investigation into the behaviour of tie-down systems funded by the Department of Trade and Industry and carried out by AEA Technology. The aims were: (i) to obtain empirical data on acceleration and tie-down loads; (ii) to measure the effects of ‘minor incidents’; (iii) to model a rail wagon carrying a fuel flask undergoing a minor collision; and (iv) to use the data to produce a PC-based simulator of a tie-down. The work shows that the accelerations experienced by a package under routine conditions of transport are low and that tie-downs designed using existing criteria for road transport can retain a package on a vehicle even under minor accident conditions. Modelling work supports existing practical evidence to show that the high design accelerations for rail transport given in Safety Series 37 could be relaxed.
2 citations
TL;DR: In this article, a new Type of 20' box container with interchangeable tray for the drums that can easily be handled and loaded into the container, together with passive restraining devices that prevent this assembly from moving inside the container when subjected to dynamic forces.
Abstract: Dynamic analysis has been performed with a new Type of 20' box container qualified as an industrial package Type 2 and 3 and as a Type A container. In the model for a numerical collision experiment the container was partially loaded with 21 × 1000 kg drums, arranged along three parallel rows forming a single layer. One of the aims in the container development was to achieve a system that could transport cargoes with a variable number of drums stacked in changeable configurations, while ensuring the safety of the container for dynamic forces that could arise during normal conditions of transport. This led to the design of an interchangeable tray for the drums that can easily be handled and loaded into the container, together with passive restraining devices that prevent this assembly from moving inside the container when subjected to dynamic forces. The container system is designed to withstand accelerations of up to 6g in the longitudinal direction. These can be expected during normal switchyard o...
TL;DR: The LR56 system is a radioactive liquid transport cask licensed for use in France for on-site and off-site road transfer of Type B bulk quantities of radioactive liquids as discussed by the authors.
Abstract: The LR56 system is a radioactive liquid transport cask licensed for use in France for on-site and off-site road transfer of Type B bulk quantities of radioactive liquids. Three LR56 systems (with a...
TL;DR: Transnucleaire has carried out considerable transport of radioactive materials by sea, in full compliance with the regulations, at a cost which is as close as possible to that of other industrial goods and without the need to dedicate the Bouguenais fully to this type of transport as mentioned in this paper.
Abstract: Due to the application of the new IMDG regulations for the transport of radioactive material by sea, the conditions of transport have been analysed in detail by Transnucleaire in order to comply with these regulations. Following a commercial agreement between Transnucleaire and the French ship owner Company Morbihannaise de Navigation, to equip the ship named Bouguenais according to the INF Code Class 2, Transnucleaire has carried out considerable transport of radioactive materials by sea, in full compliance with the regulations, at a cost which is as close as possible to that of other industrial goods and without the need to dedicate the Bouguenais fully to this type of transport. Starting in July 1996 Transnucleaire has operated the sister ship of the Bouguenais, named Beaulieu, after fitting equipment to satisfy the INF (Class INF2) code requirement, in response to customers' demands and to offer more flexibility for ship availability. The two ships continue to be able to transport other indust...
TL;DR: In this article, the authors describe the requirements for the LOGCOST model and the solutions adopted, and then examples shown of the graphical and tabular outputs that LogCOST can provide.
Abstract: UK Nirex Ltd is planning a deep repository for intermediate level radioactive. waste, and also some low le.vel waste. Part of this work is to develop a transport system to bring the packaged waste to the repository from nuclear industry sites across the United Kingdom. To assess the logistics and costs of this transport system and to provide inputs to the repository specification and design, Nirex has commissioned the development of a flexible computer model Which can be used on a desktop PC. The requirements for the LOGCOST model are explained, and the solutions adopted, and then examples shown of the graphical and tabular outputs that LOGCOST can provide.
TL;DR: The RADTRAN code verification process addresses format changes, model changes, output formatChanges, and error correction, and the usefulness of the quality assurance record created by following the verification process is discussed.
Abstract: The RADTRAN code verification process addresses (1) format changes, (2) model changes, (3) output format changes, and (4) error correction. The process is described, and examples of a model change and error correction are illustrated. The usefulness of the quality assurance record created by following the verification process is discussed.
TL;DR: In this article, the effects of waste package limitations for low and intermediate level waste taking into account LSA/SCO regulations for transport and waste acceptance criteria are discussed, in particular for low-and intermediate-level waste.
Abstract: In the management of radioactive waste, different processes have to be considered such as conditioning, interim storage and final disposal together with transport as the linking process. Attention should be paid to all the relevant steps within these processes, in particular to derive appropriate waste package requirements for a safe waste management system as well as to obtain a consistent regulatory framework. Radioactive waste arising from research and development centres, nuclear power plant operation, decommissioning, the nuclear fuel cycle industry, and applications of radioisotopes in medicine, industry and research, has finally to be shipped to a final disposal site. Therefore waste packages are subject to both the regulatory requirements of transport and the requirements of disposal. Resulting consequences for waste package limitations will be discussed, in particular for low and intermediate level waste taking into account LSA/SCO regulations for transport and waste acceptance criteria ...
TL;DR: The International Atomic Energy Agency (IAEA) Transport Regulations have been adopted by all countries which participate in the movement of radioactive material (RAM) in the UK since 1968 as discussed by the authors.
Abstract: The safety record of the transport of radioactive material (RAM) is excellent. This level of safety has been achieved on a global scale principally through the adoption into national legislation of the International Atomic Energy Agency (IAEA) Transport Regulations by all countries which participate in the movement of RAM. Over more than 30 years of operations, involving millions of shipments, the effectiveness of these regulations has been demonstrated by the continued low incident rate. In the UK there has been a notable absence of any transport accidents with serious radiological consequences since incident logging began in 1968. The IAEA Regulations are prescriptive in nature and they aim to achieve a uniform level of safety through controls graded to match the potential hazard of the radioactive cargo. The engineered and operational controls address containment of the RAM, radiation emitted from the package, dissipation of heat and prevention of criticality. The nuclear industry and its regu...
TL;DR: The role of the Competent Authority as a key figure in implementing the Regulations and in assuring compliance with them at both national and international levels is outlined in this article, where the main duties involved in the CAs day-to-day work in its aim of achieving safety in the transport of radioactive materials are described.
Abstract: The role of the Competent Authority as a key figure in implementing the Regulations and in assuring compliance with them at both national and international levels is outlined. The paper describes the main duties involved in the Competent Authority's day-to-day work in its aim of achieving safety in the transport of radioactive materials. The contribution of the Radioactive Transport Study Group — an autonomous association of national Competent Authorities — is also described.
TL;DR: In this paper, a new model of Type A box container is presented which can also be used as industrial package Type 2 and Type 3 (IP-3) for the transport of solid radioactive wastes and other hazardous materials, which Corrobesch/STM recently developed and tested.
Abstract: —A new model of Type A box container is presented which can also be used as industrial package Type 2 (IP-2) and Type 3 (IP-3) for the transport of solid radioactive wastes and other hazardous materials, which CORROBESCH/STM recently developed and tested. One of the principal goals in the development of these new containers has been to address and remedy an issue that until now has received only secondary attention in the transport industry, namely the dynamic forces that can arise while hauling the cargo. In response to this shortcoming, the Federal Republic of Germany has newly issued an emergency regulation decreeing that such accidental forces must be taken into account. On the other hand, a number of domestic ordinances and international codes of regulation also contain prescriptions for dynamic forces, which vary from code to code. This new CORROBESCH/STM box container system implements a set of special shock-absorbing elasto-plastic trays with selftensioning straps, which can withst...
TL;DR: In this paper, the authors investigated leakage rates of water under high pressures and at high temperatures from two kinds of leak path models: a disc with a scratch on the surface and narrow stainless steel wires installed on the O-ring surface.
Abstract: A programme for enhancement of fuel burnup has been promoted in Japan as part of the sophistication programme for light water reactors to reduce the fuel cost and the amount of spent fuel. As part of this fuel programme, a new wet-type transport cask has been developed to transport the high burnup fuels efficiently. The purpose of this work is to clarify the margin of safety in the evaluation of the release rate of radioactive materials from the wet-type transport cask into the environment and to establish a practical evaluation method for leakage rates based on leak behaviour of high temperature water from the casks. In this paper, leakage rates of water under high pressures and at high temperatures are investigated from two kinds of leak path model. One is a disc with a scratch on the surface which simulates a defect on the seal surface of the O-ring flange and the other is narrow stainless steel wires installed on the O-ring surface which simulates hair adhering to the O-ring surface. From the ...
TL;DR: In this article, different chemical and physical processes involved in the containment of radionuclides are analyzed, and the effects of a container drop on the mortar and concrete retention are discussed. And the reference scenario of container degradation during transport considers a 9 m drop and a 800°C fire for 30 min.
Abstract: Different concrete waste packages have been designed by Electricite de France (EDF) for the long-term storage of radioactive Low Level Waste (LLW). Their main function is to confine radionuclides from the biosphere for three hundred years in a near-surface disposal. According to the transport regulation, a Type B package is needed for some waste like water filters. The water filters from EDF nuclear power plants are encapsulated in mortar and placed in a concrete container. Transport regulations for these containers have required the development of a methodology for safety assessment. The reference scenario of container degradation during transport considers a 9 m drop and a 800°C fire for 30 min. First, the different chemical and physical processes involved in the containment of radionuclides are analysed. In particular, the radionuclide transport mechanisms in cement-based materials have been reviewed. Secondly, the effects of a container drop on the mortar and concrete retention are discussed. ...
TL;DR: BNFL Transport has established an integrated management system which includes quality, safety and environmental aspects and covers the design, manufacture, testing, documentation, use, maintenance, inspection and decommissioning of all packages used for the transport of radioactive materials.
Abstract: Quality Assurance (QA) is a requirement of the International Atomic Energy Agency (IAEA) Safety Series No 6 Regulations for the Safe Transport of Radioactive Materials and is also increasingly becoming a customer requirement. BNFL Transport has established an integrated management system which includes quality, safety and environmental aspects and covers the design, manufacture, testing, documentation, use, maintenance, inspection and decommissioning of all packages used for the transport of radioactive materials. The management system also covers planning, programming and transport operations, and covers all modes of transport by road, rail, sea and air. The management system, which was certificated in 1994 to ISO 9001 and BS 5882 by an independent third-party certification body, Lloyds Register Quality Assurance Limited (LRQA), was developed to enable BNFL Transport to demonstrate to Competent Authorities, customers and the general public that the arrangements are in place, being adhered to and ...
TL;DR: The regulatory aspects of the transport of radioactive materials in Belgium are summarised in this article, where the radiological protection regulations for transport are part of the general radiological Protection regulations.
Abstract: The regulatory aspects of the transport of radioactive materials in Belgium are summarised. The radiological protection regulations for transport are part of the general radiological protection regulations. For the transport of radioactive waste, additional administrative provisions are based on the European Directive on the supervision and control of shipments of radioactive waste between member states and into and out of the Community.
TL;DR: The guidance will present examples of acceptable methods for demonstrating compliance with the revised rules, and will be issued for public comment prior to final issuance of the guidance in 1997.
Abstract: In 1985, the International Atomic Energy Agency issued revised regulations for the safe transport of radioactive material. Significant among the changes were major revisions to requirements for Low Specific Activity (LSA) material and Surface Contaminated Objects (SCOs). In preparation for the adoption of these requirements into regulations in the United States, it became apparent that guidance on how to apply these requirements, clarifying technical uncertainties and ensuring proper implementation, would be needed both by the regulators and those regulated. Thus, the US Department of Transportation and the US Nuclear Regulatory Commission, with the assistance of staff from Oak Ridge National Laboratory, are preparing regulatory guidance for LSA material and SCO transport. The guidance will present examples of acceptable methods for demonstrating compliance with the revised rules. Ideas being investigated for inclusion in the pending guidance are discussed in this paper. Under current plans, the guidance will be issued for public comment prior to final issuance of the guidance in 1997.
TL;DR: In this paper, the use of non-linear finite element analysis (FLEA) was used to demonstrate the impact resistance of packages by means of full scale or scale model physical drop tests.
Abstract: The IAEA Regulations for Safe Transport of Radioactive Materials require that packages for transport of significant quantities of radioactive material be capable of withstanding specified tests which are representative of accident conditions such as fire or impact. The use of calculations has been generally agreed to be reliable or conservative for the fire test, but not sufficiently so for the impact tests. Hence, it is normal practice in the industry to demonstrate the impact resistance of packages by means of full scale or scale model physical drop tests. In recent years however the power of computers and software has increased significantly with the result that it is now possible to claim that computer impact analysis is sufficiently reliable or conservative for demonstrating the safety of transport packages. In the future computer impact analysis will be used increasingly for licensing of packages for transport of radioactive materials.This paper describes the use of the non-linear finite ele...
TL;DR: In this paper, the authors used INTERTRAN 2 to carry out the risk calculations for a large number of radioactive material transport activities, for both incident-free and accident conditions of transport.
Abstract: The limited number of accidents that have occurred during transport of radioactive materials do not provide a large enough database for examining the effects of all potential transport conditions. Assessment of risk from transport programmes therefore depends on calculations, using a database for a larger group of transport activities. The computer code INTERTRAN 2 may be used to carry out the risk calculations. Generation of input data for INTERTRAN 2 can be a formidable task. Some of the data requirements are described and some of the sources that may be used in generating a set of input data are reviewed, for both incident-free and accident conditions of transport.
TL;DR: The regulatory framework which governs the transport of MOX fuel is set out in this article, including packages, transport modes and security requirements, and technical requirements for the packages are reviewed and discussed.
Abstract: The regulatory framework which governs the transport of MOX fuel is set out, including packages, transport modes and security requirements. Technical requirements for the packages are reviewed and ...
TL;DR: In this article, a Gas Circulator Transportation Module based on ISO container standards was designed, manufactured and tested, and a Safety Case prepared addressing the radiological hazards associated with the transport of a gas circulator and demonstrating regulatory compliance.
Abstract: Heysham 1 and Hartlepool Nuclear Power Stations share a common design of gas circulator and a requirement was identified to transport a spare circulator between the Stations. The circulators are 6 m long, 2 m diameter and weigh approximately 38 tonnes. The circulator becomes contaminated in use and is classified as suitable for transport as SCO-II. It can therefore be transported within a Type 2 Industrial Package (IP-2), in accordance with the IAEA Transport Regulations. An appropriate package, the Gas Circulator Transportation Module, based on ISO container standards, was designed, manufactured and tested, and a Safety Case prepared addressing the radiological hazards associated with the transport of a gas circulator and demonstrating regulatory compliance. Following the issue of a Certificate of Regulatory Compliance, the container module was used· to transport a gas circulator from Heysham 1 to Hartlepool, paving the way for similar purpose-designed modules for the transport of large components.
TL;DR: In this article, the authors trace the development of international legal attitudes to transboundary transport of radioactive and other hazardous waste and conclude that as international law now stands it would be very difficult to establish a network of international wast...
Abstract: The recent decision not to grant planning permission for construction of a Rock Characterisation Facility near Sellafield has reopened the question of long-term radioactive waste disposal policy in the UK. One possible solution would be the construction and operation of a small number of international radioactive waste disposal facilities, taking waste from several countries. Such an approach would allow pooling of international expertise; would allow the choice of excellent sites from geological and demographical standpoints; and may be economically attractive depending on economies of scale. However, the approach would also increase the amount of waste transport, and may reduce the pressure on producers to reduce the volumes of waste arising. This paper traces the development of international legal attitudes to transboundary transport of radioactive and other hazardous waste. It concludes that as international law now stands it would be very difficult to establish a network of international wast...
TL;DR: In this article, the use of small size seal leakage test rigs to demonstrate the compliance of full size container seals against the IAEA Transport Regulation's limits for activity release for normal transport and accident conditions is discussed.
Abstract: This paper looks at the use of small size seal leakage test rigs to demonstrate the compliance of full size container seals against the IAEA Transport Regulation's limits for activity release for normal transport and accident conditions. The detailed requirements of the regulations are discussed and it is concluded that an appropriate test programme to meet these requirements, using only small size test rigs, can normally be set up and carried out on a relatively short time scale. It is important that any small test rigs should be designed to represent the relevant features of the seal arrangement and the overall test programme should cover all of the conditions, specified by the regulations, for the type, classification and contents of the container under consideration. The parameters of elastomer O-rings, which affect their sealing ability, are considered and those which are amenable to small scale testing or have to be modelled at full size are identified. Generally, the seals used in leakage t...