Chapter 2: Description of Methods

Abstract

This investigation encompasses the determination of potential radiological consequences from normal (accident-free) waste transport and the transport accident risk. The investigation is based on the developmental stage as of autumn 1990 of the planning and licencing documents for the Konrad repository. This applies in particular to: (i) the intended waste and transport containers, (ii) the local dose rates and radioactivity inventories of the waste packages, and (iii) the planned sequence of the storage operations.     

Chapter 8: Transport Accident Risk

Abstract

On their way to the waste disposal site, waste transporters can become involved in accidents. In certain circumstances the waste containers may not be able to withstand the accident forces, thus causing radioactive material to be released into the environment. Depending on the radioactive materials held in the waste containers concerned and the amount released into the environment, the radiological consequences — such as radiation exposure of individuals and contamination of the biosphere — vary over a wide range.     

Chapter 1: Principles and Objectives

Abstract

Like all activities in our civilised world the transport of radioactive waste on public routes or routes to which the public has access (e.g. rail/road) entails some elements of risk — nuclear and nonnuclear — for man and his environment. The risks involved in waste transport comprise the radiation exposure of the population and transport personnel from normal, accident-free transport, as well as from possible transport or handling accidents with the potential of causing radiation exposure of people and contamination in the surrounding area.     

Chapter 6: Radiation Protection Regulations

Abstract

The basis for the radiation protection regulations that apply to the transport of radioactive materials are the Atomic Energy Act related provisions in the Radiation Protection Ordinance (StrlSchV) and the provisions of the Directives on the Transport of Hazardous Goods. The applicability of the Radiation Protection Ordinance is, however, limited as the provisions of §§ 29 to 80 do not apply to the transport of radioactive materials according to current legislation, with the exception of the principles of radiation protection contained in § 28 (e.g. minimisation principle).     

Chapter 5: Waste Transport; Transport Scenarios and Arrangements

Abstract

The potential radiological consequences of waste transport to the Konrad waste disposal site depend on the nature and number of shipments and the associated waste transport routes.     

Chapter 3: Type and Quantity of Radioactive Waste Destined for Disposal

Abstract

According to the current planning status, radioactive waste with negligible heat generation is destined for storage in the Konrad waste repository in accordance with the Provisional Waste Acceptance Requirements⁽⁴⁾. Waste of this kind occurs in the nuclear fuel cycle, research, medicine and technology. In its original state, the primary wastes of this type have various forms, such as: liquids, concentrates, sludges; ion exchange resins; compressible and/or combustible solids; incompressible solids, e.g. structural material components; filters, filter candles; other types of waste. The radioactive waste is appropriately conditioned and packaged before transport to the waste disposal site. To meet the basic requirements specified in the Waste Acceptance Requirements, primary waste must be solidified, for which the most common solidifying agents are cement and concrete although bitumen is also used. Waste products in decomposing, fermenting or liquid form or which contain a significant fraction in such states are not accepted for disposal.     

Chapter 7: Radiological Consequences from Normal (Accident-Free) Waste Transport

Abstract

On the basis of the waste transport volume, the radiological characteristics of the waste and transport containers, and the transport arrangements dose estimates were carried out for various groups of people for the two transport scenarios considered in this study (80% rail/20% road and 100% rail). In order to assess the radiation exposure with accident-free transport, the collective and individual doses are considered on the basis of the effective dose.     

Vaporization and Surface Ionization of LaC2, CeC2, PrC2, NdC2, ThC2 and UC2

The Langmuir vaporization and the surface ionization of LaC₂, CeC₂, PrC₂, NdC₂, ThC₂ and UC₂ from a heated graphite filament have been studied mass spectrometrically. It was found that there were present small amounts of neutral and ionic metal dicarbide molecules in addition to neutral and ionic metal atoms in the LaC₂, CeC₂, PrC₂, ThC₂ and UC₂-C systems with the exception of NdC₂-C, where neither neutral nor ionic metal dicarbide molecules were observed. The reason for this exceptional behavior of the NdC₂-C system is explained by the very small vaporization coefficients, as estimated from the measurements of neutral MC₂/M ratios and ionic MC₂/M ratios.

From the measurements of the heats of vaporization, it was surmised that the ionization potential of Th measured by the surface ionization comparison technique might be too high.     

Vapor Species over Na2O-B2O3-SiO2-Cs2O Glass

Methods for suppression and control of the axisymmetric vertical positional instability are described on the basis of conceptural design studies with the International Tokamak Reactor (INTOR). The shell effect is well known to be useful for suppression of the fast instability. Here shell structures are presented and their usefulness is assessed. Included in the assessments are required modellings of the plasma current for determination of mutual inductances between the plasma and the inductive components around it. Three kinds of models are described and their features are compared to the shell effect. Two kinds of simplified reactor structures are described and studied by comparing them with some control characteristics of the slow instability by a pair of control coils. Their structures are selected so as to result in different shell effects between them, and are consequently found to produce different capacities of power supply, too.