Fuzzy Win-Win: A Novel Approach to Quantify Win-Win Using Fuzzy Logic

The classic win-win has a key flaw in that it cannot offer the parties with right amounts of winning because each party believes they are winners. In reality, one party may win more than the other. This strategy is not limited to a single product or negotiation; it may be applied to a variety of situations in life. We present a novel way to measure the win-win situation in this paper. The proposed method employs the Fuzzy logic to create a mathematical model that aids negotiators in quantifying their winning percentages. The model is put to the test on real-life negotiation scenarios such as the Iranian uranium enrichment negotiations, the Iraqi-Jordanian oil deal, and the iron ore negotiation (2005-2009). The presented model has shown to be a useful tool in practice and can be easily generalized to be utilized in other domains as well.

Improving Participation in the German Search for a Nuclear Waste Repository Site: a WebGIS as a Transdisciplinary Approach to Support Dialogue?

The political and social debate on nuclear energy in Germany has been characterized for many decades by a high potential for conflict and dissatisfaction. In particular, the controversies surrounding the Gorleben salt dome achieved international attention and altered the relationship between the population and political decision makers at the local up to international levels. With the Site Selection Act from 2013 (StandAG, first revision 2017) a new approach was selected in order to find a participative, inclusive and transparent search process for the best possible site of a repository for highly radioactive waste in Germany. In connection with this a self-learning process was proclaimed, based on a white (unprejudiced) map, which aimed to give the general public an active role; however, even the first interim report of the Federal Company for Radioactive Waste Disposal (BGE) and the publication of the multicolored map, in which geologically suitable areas were extensively shown, revealed a massive potential for conflict. Many citizens and activists, who had already protested against the Gorleben salt dome, in this early phase of the process criticized the lack of transparency and opportunities to voice an opinion on possible site regions. In order to counter these criticisms, the possibilities for a web geographic information system (WebGIS) application (interactive map) as an online platform were analyzed (Walkobinger and Tauch, 2018; Brown and Kyttä, 2018). The aim was to virtualy present available geodata (Chwalisz, 2021), which enabled people to contribute to spatial information (geological, superficial) and therefore to achieve an interaction and participation option with respect to the possible site regions. For this, available geodata relevant for the site search process, such as subareas (BGE, 2020), nuclear power stations (active/inactive, research stations etc.), storage facilities (repository, central, intermediate storage etc.), historically relevant sites (sites of protest, uranium-enrichment and preparation plants etc.) and basic data on orientation were used. Based on this, two possibilities for participative interaction were analyzed: (1) the inclusion of spatially located notes that contain own experiences or local knowledge (e.g. reports, concerns, suggestions, own expert opinions) and (2) the initiation of a platform for a spatially located discussion. Against the background of transdisciplinary research, the aim was to evaluate the participative value of this application in an iterative process, in which the research process is supported by an accompanying group from civil society. For this panel we want to present our results from the transdisciplinary research process. In addition to testing the suitability of such a participation mode, we want to analyze where problems arise and which information is necessary or can lead to conflicts (Griffin, 2020). Finally, we want to gain information on how such participation modes influence the quality of the dialogue and how they contribute to an overall perception of a legally acceptable process (Rzeszewski and Kotus, 2019).

Preliminary Neutronic Analysis of 150 MWt High-Temperature Gas Reactor to Produced Electricity in Small Area

There are small areas in Indonesia with insufficient electricity. High-Temperature Gas Reactor (HTGR) is a promising nuclear power plant that can be used in such areas as its capability to produce electricity and co-generation applications. A preliminary study on the neutronic aspect of the 150 MWt HTGR design is performed in this research. High Temperature Engineering Test Reactor (HTTR) is used as a basic model. The calculation was performed by Standard Thermal Reactor Analysis Code (SRAC) code, and Japanese Evaluated Nuclear Data Library (JENDL) 4.0 as nuclear data library. As a result, by increasing HTTR fuel assembly geometry to 1.5 times its original and using higher uranium enrichment, the reactor can be operated for five years.

Neutronic Evaluation of MSBR System Using MCNP Code

The concept of Molten Salt Reactor use Th to breed fissile 233U, where an initial source of fissile material needs to be provided. However, there is no available 233U and so; the fissile fuel supply is one of the unresolved problems. Thus, it is necessary to use existing fissile materials such as 235U or Pu to produce 233U. Current studies analyze the fuel transition from 235U/Th or Pu/Th to 233U/Th and, in this context, the present work evaluates the criticality and the neutron flux of MSBR (Molten Salt Breeder Reactor) considering the fuel: (i) mix of Th and enriched U; (ii) the combination of Th and reprocessed Pu; and (iii) matrix of reprocessed Pu/minor actinides (MAs) and Th. The goal is to verify which of these fuels can be used as initial fissile supply. The MSBR core was simulated by MCNPX 2.6.0 code and the criticality model presents similar behavior of previous studies. The results show that reprocessed fuels could have a potential to be used as initial fissile supply, but these fuels present a neutron flux profile less flattens than traditional 233U/Th. It is possible that a new distribution of fuel elements may improve this profile and future simulations will be performed to evaluate this behavior. The uranium, must has high enrichment value to be used as initial seed. Other studies need be performed to evaluates the uranium enrichment and the U/Th ratio that produces similar core criticality to traditional fuel.

Nuclear Proliferation: The Next Wave in 2020

What will nuclear proliferation look like in the future? While the quest for nuclear weapons has largely quieted after the turn of the 21st century, states are still interested in acquiring nuclear technology. Nuclear latency, an earlier step on the proliferation pathway, and here defined as operational uranium enrichment or plutonium reprocessing capability, is increasingly likely to be the next phase of proliferation concern. The drivers of nuclear latency, namely security factors, including rivalries with neighboring adversaries and the existence of alliances, are especially consequential in an increasingly challenging geopolitical environment. Though poised to play a significant role in international politics moving forward, latency remains a core area of exploration and subject of debate within the nuclear weapons literature writ large. While in many ways similar to nuclear weapons’ proliferation, the pursuit of nuclear latency has distinct features that merit further attention from scholars and policymakers alike.

Correlating nanoscale secondary ion mass spectrometry and atom probe tomography analysis of uranium enrichment in metallic nuclear fuel

235U enrichment in a metallic nuclear fuel was measured via NanoSIMS and APT, allowing for a direct comparison of enrichment across length scales and resolutions.