A geoscientific site descriptive model for the Äspö Hard Rock Laboratory, SE Sweden

Author(s):  
Jesper Petersson ◽  
Peter Hultgren ◽  
Mansueto Morosini ◽  
Frédéric Mathurin

<p>The development of an updated geoscientific site descriptive model (SDM) is currently in progress for the Äspö Hard Rock Laboratory (Äspö HRL), the key underground research facility of the Swedish Nuclear Fuel and Waste Management Company (SKB). Äspö HRL is located in south-eastern Sweden, within a suite of 1.81–1.76 Ga granitoids, and consists of a tunnel system down to 460 m depth with a total length of about 5 km. Tectonically, the area is part of a contractional shear belt, primarily manifested by a NE-SW trending regional deformation zone, which partly transect the underground facility. The shear zone system has evolved gradually over a prolonged period, with an initial low-grade ductile development, followed by multiple events of brittle reactivation. The structural framework is characterised by a significant heterogeneity in the hydraulic flow properties, where the most transmissive structures belong to a set of less extensive, conjugate zones and fractures.</p><p>More than 30 years of studies, starting with the pre-investigations and construction of the facility, have generated a wealth of geoscientific data in 3-D space, and hence a sound basis for an update of existing models. The SDM under current development aims to present an integrated geoscientific understanding of the Äspö site, with special focus on geology, hydrogeology and hydrogeochemistry. The general working procedure includes basically an initial stage of data capture, followed by an intermediate interpretative stage, and finally the construction of 3-D models with associated concepts and parameters. An explicit goal throughout the work has been to encourage interaction between the different geo-disciplines, especially during the interpretative stage, as a forerunner to the final stage of deterministic/conceptual modelling. During the interpretative stage, geological and geophysical information were combined into two basic building blocks along individual boreholes, tunnels, and outcrops: rock units and possible deformation zones, which were assigned hydraulic parameters such as primarily K-values. The subsequent geological 3-D modelling comprises two components: rock domains and deformation zones with a surface trace length of ≥ 300 m. Hydrogeological feedback was provided in terms of K-anisotropies and depth trends.</p><p>The fundamental outcome of the modelling is a more profound conceptual understanding, along with geometries and properties for each domain or zone. Additional outcomes are data on and understanding of the effects of 25 years of artificial tunnel drainage on groundwater pressures, flow and chemistry. The natural groundwater system, originally formed by paleoclimatic and geological factors over a vast period, has be profoundly influenced by important monitored phenomena. Upflow of deep-lying saline water and extensive intrusion of current seawater disclose the apparent hydro-properties and interconnection between deformation zones.</p><p>Currently, geological 3-D model includes geometries for ten rock domains and 24 deformation zones, the latter with seamless transitions to zones of the regional scale Laxemar model, as developed by the SKB with the objective of siting a geological repository for spent nuclear fuel in the proximity to the Äspö HRL. As completed, the models will serve as framework for more detailed-scaled facility models.</p>

1997 ◽  
Vol 12 (3) ◽  
pp. 385-406 ◽  
Author(s):  
Gän Bäckblom ◽  
Roy Stanfors ◽  
Gunnar Gustafson ◽  
Ingvar Rhen ◽  
Peter Wikberg ◽  
...  

2019 ◽  
Vol 96 (9) ◽  
pp. 868-874
Author(s):  
O. A. Kochetkov ◽  
A. P. Panfilov ◽  
V. Yu. Usoltsev ◽  
Vladimir N. Klochkov ◽  
S. M. Shinkarev ◽  
...  

This article covers basic issues of the radiation protection in nuclear industry. It contains an overview of history of the national nuclear industry including the creation of industry-specific facilities (research centers, medical units etc.). Main stages of the creating the regulatory system for radiation protection, starting from the beginning of the industrial radiation protection, stages of introducing exposure limits and implementation of the radiation protection system in international documents are described. In 1996, for the first time, radiation protection requirements in Russia were documented in the form of the Federal Law 3-FZ of 09.01.1996 “Radiation Protection of the Public". A new stage of updating the global methodological foundation of radiation protection began in 2007. IRCP recommendations of 2007 moved from the legacy practice and intervention approach focused on the process to the approach based on characteristics of exposure situation. The evolvement of new technologies (specifically, in the field of reactor engineering and used nuclear fuel) in recent years requires a special focus on the safety of the personnel and the public. This stipulates the necessity of the appropriate radiation protection support of activities for the safe implementation of modern technologies. Handling of spent nuclear fuel and generated radioactive wastes, safe decommissioning of radiation hazardous facilities, radiation protection during operation of radiation facilities in nonstandard conditions are all the issues requiring specific examination. Regulatory and procedural documents on radiation protection of the personnel and the public during development and implementation of new technologies have been developed and approved as a result of long-term work of scientists and other professionals.


2002 ◽  
Author(s):  
Glenn E. McCreery ◽  
Keith G. Condie ◽  
Randy C. Clarksean ◽  
Donald M. McEligot

2020 ◽  
Vol 2020 (1) ◽  
pp. 67-77
Author(s):  
Nikita Vladimirivich Kovalyov ◽  
Boris Yakovlevich Zilberman ◽  
Nikolay Dmitrievich Goletskiy ◽  
Andrey Borisovich Sinyukhin

ANRI ◽  
2020 ◽  
pp. 45-53
Author(s):  
A. Lachugin ◽  
M. Kocherygin ◽  
A. Gayazov ◽  
Yury Martynyuk ◽  
A. Vasil'ev

The paper presents basic results of development of a criticality accident alarm system to ensure safe retrieval of the spent nuclear fuel from the Lepse Floating Maintenance Base. The key features and engineering aspects of the system design are described. Locations of criticality detector units and selected alarm level settings are justified, hazardous area boundaries were identified, and parameters to identify inadequately protected zones were calculated. The SRKS-01D criticality accident alarm system by SPC “Doza” was selected as base equipment. The system was commissioned in 2019 and has been successfully operated for more than 6 months.


2018 ◽  
Author(s):  
Kaushik Banerjee ◽  
Thomas M. Evans ◽  
Gregory G. Davidson ◽  
Steven P. Hamilton

2020 ◽  
Author(s):  
Benjamin Roach ◽  
Cole Hexel ◽  
Kayron Rogers ◽  
Jeffrey (Jeff) Delashmitt ◽  
Shalina Metzger ◽  
...  

Sign in / Sign up

Export Citation Format

Share Document