The site selection process of speculative residential developers in an urban area

1990 ◽  
Vol 5 (4) ◽  
pp. 219-228 ◽  
Author(s):  
Michael Pacione
Keyword(s):  
Urban Area ◽  
Site Selection ◽  
Selection Process

scholarly journals Experience of establishing and coordinating a nationwide network for bidirectional intussusception surveillance in India: lessons for multisite research studies

BMJ Open ◽  
2021 ◽  
Vol 11 (5) ◽  
pp. e046827
Author(s):  
Manoja Kumar Das
Keyword(s):  
Quality Assurance ◽  
Site Selection ◽  
Information Seeking ◽  
Selection Process ◽  
Tertiary Care ◽  
Vaccine Safety ◽  
Secondary Outcome ◽  
Prospective Surveillance ◽  
Surveillance Network ◽  
Nationally Representative

ObjectivesTo document and share the process of establishing the nationally representative multisite surveillance network for intussusception in India, coordination, data management and lessons learnt from the implementation.DesignThis study combined both retrospective and prospective surveillance approaches.Setting19 tertiary care institutions were selected in India considering the geographic representation and public and private mixParticipantsAll children under-2 years of age with intussusceptionPrimary and secondary outcome measuresThe experience of site selection, regulatory approvals, data collection, quality assurance and network coordination were documented.ResultsThe site selection process involved systematic and objective four steps including shortlisting of potential institutions, information seeking and telephonic interaction, site visits and site selection using objective criteria. Out of over 400 hospitals screened across India, 40 potential institutions were shortlisted and information was sought by questionnaire and interaction with investigators. Out of these, 25 institutes were visited and 19 sites were finally selected to participate in the study. The multistep selection process allowed filtering and identification of sites with adequate capacity and motivated investigators. The retrospective surveillance documented 1588 cases (range: 14–652 cases/site) and prospective surveillance recruited 621 cases (range: 5–191 cases/site). The multilayer quality assurance measures monitored and ensured protocol adherence, complete record retrieval and data completeness. The key challenges experienced included time taken for obtaining regulatory and ethical approvals, which delayed completion of the study. Ten sites continued with another multisite vaccine safety surveillance study.ConclusionThe experience and results of this systematic and objective site selection method in India are promising. The systematic multistep site selection and data quality assurance methods presented here are feasible and practical. The lessons from the establishment and coordination of this surveillance network can be useful in planning, selecting the sites and conducting multisite and surveillance studies in India and developing countries.

3D Web Visualization Tool to support HAYABUSA2-MASCOT Landing Site Selection Process

2018 ◽  
Author(s):  
Antoine F. Charpentier ◽  
Vivian Lafaille ◽  
Aurelie Moussi ◽  
Jean Christophe Malapert ◽  
Laurence Lorda ◽  
...  
Keyword(s):  
Site Selection ◽  
Selection Process ◽  
Landing Site ◽  
Visualization Tool ◽  
Web Visualization ◽  
3D Web ◽  
Landing Site Selection

scholarly journals Analysis of Multi-Criteria Evaluation Method of Landfill Site Selection for Municipal Solid Waste Management

2018 ◽  
Vol 34 ◽  
pp. 02010 ◽  
Author(s):  
Habiba Ibrahim Mohammed ◽  
Zulkepli Majid ◽  
Norhakim Bin Yusof ◽  
Yamusa Bello Yamusa
Keyword(s):  
Waste Management ◽  
Solid Waste ◽  
Site Selection ◽  
Solid Waste Management ◽  
Selection Process ◽  
Landfill Site ◽  
Decision Makers ◽  
Landfill Site Selection ◽  
Multi Criteria Evaluation ◽  
Selection For

Landfilling remains the most common systematic technique of solid waste disposal in most of the developed and developing countries. Finding a suitable site for landfill is a very challenging task. Landfill site selection process aims to provide suitable areas that will protect the environment and public health from pollution and hazards. Therefore, various factors such as environmental, physical, socio-economic, and geological criteria must be considered before siting any landfill. This makes the site selection process vigorous and tedious because it involves the processing of large amount of spatial data, rules and regulations from different agencies and also policy from decision makers. This allows the incorporation of conflicting objectives and decision maker preferences into spatial decision models. This paper particularly analyzes the multi-criteria evaluation (MCE) method of landfill site selection for solid waste management by means of literature reviews and surveys. The study will help the decision makers and waste management authorities to choose the most effective method when considering landfill site selection.

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
Keyword(s):  
Ground Water ◽  
Nuclear Waste ◽  
Site Selection ◽  
Selection Process ◽  
Natural Radionuclides ◽  
Water System ◽  
Residence Times ◽  
Naturally Occurring ◽  
Hydrologic Data ◽  
Regional Hydrology

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.

Dry-Run of Site Investigation Planning Using the Manual for Preliminary Investigation in Japan

2010 ◽  
Author(s):  
Shigeki Akamura ◽  
Tadashi Miwa ◽  
Tatsuya Tanaka ◽  
Hiroshi Shiratsuchi ◽  
Atsushi Horio
Keyword(s):  
Site Selection ◽  
Selection Process ◽  
Preliminary Investigation ◽  
Site Investigation ◽  
Geological Environment ◽  
Geophysical Prospecting ◽  
Geological Disposal ◽  
Budget Planning ◽  
Planning And Management ◽  
First Editions

A stepwise site selection process has been adopted for geological disposal of HLW in Japan. Literature surveys, followed by preliminary investigations (PI) and, finally, detailed investigations in underground facilities will be carried out in the successive selection stages. In the PI stage, surface-based investigations such as borehole surveys and geophysical prospecting will be implemented. In order to conduct the PI appropriately and efficiently within a restricted timeframe and budget, planning and management of PI are very important. NUMO therefore compiled existing knowledge and experience in the planning and managing of investigations in the form of manuals to be used to improve and maintain internal expertise. The first editions of the two manuals were prepared on the basis of experience overseas, and then they were revised by taking geological environment, laws and regulation in Japan into consideration. This paper introduces the procedure of PI planning using the manual as well as the results of the dry-run, with the Yokosuka area as a hypothetical PI area, where the demonstration study is under way. Based on the dry-run, applicability of the manual is checked and, at the same time, further revisions are made to improve the content.

Centralization of Canada’s Spent Nuclear Fuel

2013 ◽  
Author(s):  
Krista Nicholson ◽  
John McDonald ◽  
Shona Draper ◽  
Brian M. Ikeda ◽  
Igor Pioro
Keyword(s):  
Nuclear Fuel ◽  
Site Selection ◽  
Nuclear Power ◽  
Power Plants ◽  
Spent Nuclear Fuel ◽  
Selection Process ◽  
Spent Fuel ◽  
Geologic Repository ◽  
Candu Reactors ◽  
High Level

Currently in Canada, spent fuel produced from Nuclear Power Plants (NPPs) is in the interim storage all across the country. It is Canada’s long-term strategy to have a national geologic repository for the disposal of spent nuclear fuel for CANada Deuterium Uranium (CANDU) reactors. The initial problem is to identify a means to centralize Canada’s spent nuclear fuel. The objective of this paper is to present a solution for the transportation issues that surround centralizing the waste. This paper reviews three major components of managing and the transporting of high-level nuclear waste: 1) site selection, 2) containment and 3) the proposed transportation method. The site has been selected based upon several factors including proximity to railways and highways. These factors play an important role in the site-selection process since the location must be accessible and ideally to be far from communities. For the containment of the spent fuel during transportation, a copper-shell container with a steel structural infrastructure was selected based on good thermal, structural, and corrosion resistance properties has been designed. Rail has been selected as the method of transporting the container due to both the potential to accommodate several containers at once and the extensive railway system in Canada.

Airstrip Site Selection in Coastal Labrador

1981 ◽  
Vol 35 (1) ◽  
pp. 17-25
Author(s):  
J. D. Innes ◽  
E. H. Smith ◽  
Allan Fiander
Keyword(s):  
Site Selection ◽  
Coastal Area ◽  
State Of The Art ◽  
Selection Process ◽  
Geometric Design ◽  
Digital Mapping ◽  
Data Requirements ◽  
Selection Of ◽  
Design Techniques

This paper examines a case study of the selection of nine airstrip sites in the coastal area of Labrador. The procedure used involved the procurement of better mapping for the site selection process. The benefits of this process are examined in the context of the data requirements for good airstrip selection. The site selection process is then examined utilizing state of the art digital mapping and computerized geometric design techniques.

State of the scientific and technical knowledge about limiting temperatures in the Repository Site Selection process of Germany with simultaneous consideration to Europe and other European repository concepts

2020 ◽  
Author(s):  
Ute Maurer-Rurack ◽  
Axel Liebscher ◽  
Fabien Magri
Keyword(s):  
Outer Surface ◽  
Site Selection ◽  
Selection Process ◽  
Temperature Limit ◽  
Crystalline Rock ◽  
Technical Knowledge ◽  
Federal Republic Of Germany ◽  
Regulatory Frameworks ◽  
High Level ◽  
Limiting Temperatures

<p>The Federal Republic of Germany has decided to dispose its high-level radioactive waste in deep geological formations. Three types of host rock are considered: rock salt, clay rock and crystalline rock. The Site Selection Act (StandAG<sup>1</sup>), which came into effect on the 16<sup>th</sup> of May 2017, defines the successive steps of the repository siting process, which has to ensure the best possible safety conditions for a period of one million years. Based on precaution considerations, the StandAG (§27 (4) StandAG) sets a preliminary temperature limit of 100°C at the outer surface of a repository container for the preliminary safety assessment.</p><p>This contribution provides an overview about the state of the scientific and technical knowledge on the limiting temperatures in the repository site selection process of Germany. It also illustrates the different treatments of the definition of temperature limits within other European siting processes. The findings highlight that, in Europe, the proposed criteria which consider temperature at the outer surface of a repository container get more and more into focus of research and discussion especially for the three different types of host rocks.</p><p>After presenting the national regulatory frameworks, this contribution summarizes how the European countries address the different temperature related issues for their site selection, their repository concepts and how in turn these all can influence the German safety case strategy for the German site selection. Not at least, links to site selection criteria in other countries (e.g. USA, Japan, Russia) are provided.</p><p><strong>Reference</strong></p><p><sup>1</sup>  StandAG: Standortauswahlgesetz vom 5. Mai 2017 (BGBl. I S. 1074), das zuletzt durch Artikel 2 Absatz 16 des Gesetzes vom 20. Juli 2017 (BGBl. I S. 2808) geändert worden ist.</p>

Which Processes could define Temperature Limits on the Outer Surface of a Container in a Disposal Facility ?

2020 ◽  
Author(s):  
Guido Bracke ◽  
Eva Hartwig-Thurat ◽  
Jürgen Larue ◽  
Artur Meleshyn ◽  
Torben Weyand ◽  
...  
Keyword(s):  
Outer Surface ◽  
Site Selection ◽  
Selection Process ◽  
Temperature Limit ◽  
Crystalline Rock ◽  
Safety Concept ◽  
Disposal Facility ◽  
High Level ◽  
A Site ◽  
Host Rocks

<p>When the recommencement of the search for and selection of a site for a disposal facility for HLRW in Germany was stipulated by the Site Selection Act (StandAG 2017) in 2017, a <strong>precautionary </strong>temperature limit of 100 °C on the outer surface of the containers with high-level radioactive waste in the disposal facility section was set. This <strong>precautionary </strong>temperature limit shall be applied in preliminary safety analyses provided that the “maximum physically possible temperatures” in the respective host rocks have not yet been determined due to pending research. Therefore, this issue is addressed and discussed in this paper, contributing to “pending research” by a review of the literature.</p><p>This presentation briefly discusses a few examples of thermohydraulical, mechanical, chemical and biological processes in a disposal facility, because temperature limits are derived based on safety impacts regarding THMCB-processes. The temperature-dependent processes have been extracted from databases for features, events and processes (FEP-databases). Furthermore, it is dicussed if the feasibility to retrieve and recover HLRW is hampered at high temperatures.</p><p>It is concluded that a design temperature concerning single components of a disposal facility for the preservation of their features can be derived when a safety concept is established. However, the interactions of all relevant processes in a disposal concept must be considered to determine a specific temperature limit for the outer surface of the containers. Therefore, applicable temperature limits may vary for particular safety and disposal concepts in the following host rocks: rock salt, clay stone and crystalline rock.</p><p>Technical solutions for retrieval and design options for recovery seem to be viable up to temperatures of 200 °C with different, sometimes severe, downsides according to expert judgement.</p><p>It is summarized that emperature limits regarding the outer surface of the containers can be derived specifically for each safety concept and design of the disposal facility in a host rock. General temperature limits without reference to specific safety concepts or the particular design of the disposal facility may narrow down the possibilities for optimisation of the disposal facility and could adversely affect the site selection process in finding the best suitable site.</p>

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