scholarly journals Mathematical Modeling of the Distribution of Natural 14C, 234U, and 238U in a Regional Ground-Water System

Radiocarbon ◽  
1983 ◽  
Vol 25 (2) ◽  
pp. 291-300 ◽  
Author(s):  
F J Pearson ◽  
C J Noronha ◽  
R W Andrews

Increasing concern with nuclear waste isolation technology is leading to additional studies of naturally occurring isotopes in ground water. Such studies provide information on 1) the use of radionuclides to estimate ground-water travel times and/or residence times. This information can he an extremely useful adjunct to conventional hydrologic data in developing the understanding of regional hydrology needed in the site selection process, and 2) the use of natural radionuclides as analogues to the behavior of radionuclides of concern in nuclear waste.

2020 ◽  
Vol 54 ◽  
pp. 157-163
Author(s):  
Axel Liebscher ◽  
Christoph Borkel ◽  
Michael Jendras ◽  
Ute Maurer-Rurack ◽  
Carsten Rücker

Abstract. The Federal Office for the Safety of Nuclear Waste Management (BASE – Bundesamt für die Sicherheit der nuklearen Entsorgung) is the German federal regulatory authority for radioactive waste disposal. It supervises the German site selection process and is responsible for the accompanying public participation. Task related research is an integral part of BASE's activities. The projects MessEr and übErStand compiled the state-of-the-art science and technology regarding surface based exploration methods suitable for addressing the criteria and requirements specified in the German Site Selection Act. The results support BASE to review and define the surface-based exploration programs to be executed by the national implementer BGE (Bundesgesellschaft für Endlagerung mbH). To support BASE in reviewing the application of the exclusion criteria “active fault zones” according to the Site Selection Act, the project KaStör reviewed the current knowledge on active faults and fault zones in Germany and recommends methodological approaches to date and identify the activity of faulting. For the time being, the Site Selection Act defines 100 ∘C as a draft limit on the temperature at the outer surface of a repository container for all host rocks. The project Grenztemperatur studied the temperature dependency of the different thermal-hydraulic-mechanical-chemical/biological (THMC/B) processes according to available features-events-processes (FEP) catalogues for rock salt, clay stone, and crystalline rock and describes ways to defining host rock specific maximum temperatures based on specific disposal and safety concepts. Safety oriented weighting of different criteria and comparison of different potential regions and sites are key challenges during the siting process. The project MABeSt studied and reviewed methodological approaches to this weighting and comparison problem with special emphasis on multi criteria analysis (MCA) and multi criteria decision analysis (MCDA). A key requirement for safe geological disposal of nuclear waste is barrier integrity. The project PeTroS performed the first triaxial flow-through experiments on natural rock salt samples at disposal relevant p−T conditions and studied potential percolation mechanisms of fluids within rock salt. The data substantiate that the minimum stress criterion and/or the dilatancy criterion are the prime “percolation thresholds” in rock salt. The research results support BASE in fulfilling its tasks as national regulator according to state-of-the-art science and technology and are also relevant to other stakeholders of the siting process.


2021 ◽  
Author(s):  
Florian Emanuel

Producing nuclear energy inherently produces high active nuclear waste (HAW), which has to be disposed of properly and safely. Disposal of HAW represents an eternal burden of nuclear power – even after the German nuclear phase-out in 2022. This intergenerational challenge is a challenge for many more countries than just Germany. Up to date, in the whole world, there is not one operational disposal facility for HAW. The author deals with the constitutional requirements for the German Site Selection Process and the evaluation criteria derived from the constitution. Based on an international legal comparison, he finally develops recommendations concerning a further legal development of this process. The legal comparison particularly emphasizes Canada, Switzerland and Finland.


2020 ◽  
Author(s):  
Axel Liebscher ◽  
Christoph Borkel ◽  
Ute Maurer-Rurack ◽  
Michael Jendras

<p>The German Site Selection Act (Standortauswahlgesetz – StandAG) defines the search for and selection of the national German site with best possible safety for a disposal facility for high-level radioactive waste. The Federal Office for the Safety of Nuclear Waste Management (BASE) is the federal regulatory authority for radioactive waste disposal. BASE supervises the site selection process for a repository for high-level radioactive waste and is responsible for the accompanying public participation. To fulfill its tasks according to the state of science and technology, task related research forms an integral part of BASEs activities. Current research activities in the context of the site selection process address geoscientific questions, methodological aspects of the implementation of the site selection process, and public participation aspects. This contribution provides an overview on the current geoscientific and methodological research activities of BASE.</p><p>According to § 16 StandAG , the national implementer (Bundesgesellschaft für Endlagerung  mbH) has to execute surface-based exploration and BASE has to review and define the respective exploration program. Therefore, the two projects <em>MessEr</em> and <em>übErStand</em> compiled state of science and technology with regard to surface based exploration methods. The foci were on methods suitable for addressing the criteria and requirements set out in the German Site Selection Act.</p><p>The project <em>KaStör</em> reviewed the current knowledge on active faults and fault zones in Germany and studied methodological approaches to date and identify the activity of faulting. The results support BASE to review the application of the exclusion criteria for areas with “active faults zones” according to § 22 (2) StandAG.</p><p>For the time being, § 27 (4) StandAG defines 100 °C as precautionary maximum temperature at the outer surface of waste canisters for all host rocks. The project <em>Grenztemperatur</em> compiled and studied the temperature dependency of the different THMC/B processes according to available FEP catalogues for rock salt, clay stone, and crystalline rock. The project also identified open and pending research questions and describes ways to define host rock specific maximum temperatures based on specific disposal and safety concepts.</p><p>During the site selection process, safety oriented weighting of different criteria and comparison of different potential regions and sites have to be performed. The project <em>MaBeSt</em> studied and reviewed methodological approaches to this weighting and comparison problem with special emphasis on multi criteria analysis (MCA) and multi criteria decision analysis (MCDA).</p><p>Key requirement for safe geological disposal of nuclear waste is barrier integrity. The project <em>PeTroS</em> experimentally studied potential percolation mechanisms of fluids within rock salt at isotropic conditions at disposal relevant pressures and temperatures.</p>


Sign in / Sign up

Export Citation Format

Share Document