Defining the “proven technology” technical criterion in the reactor technology assessment for Malaysia’s nuclear power program

2015 ◽  
Author(s):  
Nuraslinda Anuar ◽  
Wan Shakirah Wan Abdul Kahar ◽  
Jamal Abdul Nasir Abd Manan
Keyword(s):  
Technology Assessment ◽  
Nuclear Power ◽  
Reactor Technology

Seawater Desalination Using a High-Temperature Gas-Cooled Reactor (HTR): Overview of Regulatory and Safety Considerations

2020 ◽  
Author(s):  
Mishari Al-Saud ◽  
Fang Chao
Keyword(s):  
High Temperature ◽  
Nuclear Power ◽  
Water Source ◽  
Seawater Desalination ◽  
Holistic View ◽  
Reactor Technology ◽  
Wide Range ◽  
Safety Considerations ◽  
Operational Issues ◽  
High Temperature Gas

Abstract High-Temperature Gas-Cooled Reactor (HTR) is a promising Gen IV reactor technology that has a wide range of applications. Saudi Arabia expressed interest in using HTR as an energy source for seawater desalination. A pre-feasibility study showed that HTR-Desalination is economically competitive and feasible. Yet, the application of HTR power and process heat in the desalination industry faces some technical, conceptual, and regulatory challenges. These challenges are mainly because the reactor and desalination plant are co-located and share common systems and facilities. Moreover, there is a risk of radioactivity and brine discharge impact, since both plants share the water source and discharge location. All these issues challenge the reliability and safety of both plants. Therefore, it is essential to develop effective regulatory frameworks. The basic regulatory and infrastructural requirement for the HTR is like any other nuclear power plant. This study reflects on the typical operational issues and influence of accidents in both plants and their impact on the other. Concluded with regulatory recommendations with an effort to find common interfaces between the regulatory aspects of the nuclear power and desalination industries, which aim at providing a more holistic view on a more comprehensive regulatory framework for nuclear desalination.

Can gen-4 nuclear power and reactor technology be safe and reliable future energy for developing countries?

2010 ◽  
Author(s):  
Syed Bahauddin Alam ◽  
Hussain Mohammed Dipu Kabir ◽  
A B M Rafi Sazzad ◽  
Khaled Redwan ◽  
Ishtiaque Aziz ◽  
...  
Keyword(s):  
Developing Countries ◽  
Nuclear Power ◽  
Reactor Technology

Future Fuel Cycles: A Global Perspective

2008 ◽  
Author(s):  
Romney B. Duffey
Keyword(s):  
Heavy Water ◽  
Nuclear Power ◽  
Fuel Cycle ◽  
Global Perspective ◽  
Nuclear Power Reactor ◽  
Energy Futures ◽  
Fuel Cycles ◽  
Reactor Technology ◽  
Heavy Water Reactor ◽  
Enriched Uranium

Nuclear energy must be made available, freely and readily, to help meet world energy needs. The perspective offered here is a model for others to consider, adopting and adapting using whatever elements fit their own strategies and needs. The underlying philosophy is to retain flexibility in the reactor development, deployment and fuel cycle, while ensuring the principle that customer, energy market, safety, non-proliferation and sustainability needs are all addressed. Canada is the world’s largest exporter of uranium, providing about one-third of the world supply for nuclear power reactors. Canada’s Atomic Energy of Canada Limited (AECL) has developed a unique world-class nuclear power reactor technology — the CANDU® reactor based on the Pressure Tube Reactor (PTR) concept, moderated by heavy water (D2O), also sometimes called the Pressurized Heavy Water reactor or PHWR. With expectations of significant expansion in nuclear power programs worldwide and the resultant concerns about uranium availability and price, there is a growing desire to improve resource utilization by extracting more energy from each tonne of mined fissionable material. Attention is therefore being increasingly focused on fuel cycles that are more energy efficient, reduce waste streams and ensure sustainable futures. There are also many compelling reasons to utilize advanced fuel cycles in PTR (CANDU-type) thermal spectrum reactors. Because of its inherent technical characteristics, PTRs have a great deal of fuel cycle flexibility. The combination of relatively high neutron efficiency (provided by heavy water moderation and careful selection of core materials), on-line fuelling capability and simple fuel bundle design mean that PTR reactors can use not only natural and enriched uranium, but also a wide variety of other fuels including thorium-based fuels and those resulting from the recycle of irradiated fuel. In addition, the PTR can be optimized as a very effective “intermediate burner” to provide efficient fuel cycles that remove residual minor actinides. This inherent fuel cycle flexibility offers many technical, resource and sustainability, and economic advantages over other reactor technologies and is the subject of this paper. The design evolution and intent is to be consistent with improved or enhanced safety, licensing and operating limits and global proliferation concerns, and sustainable energy futures.

The IAEA Programme in Support of the Development, Design and Safety Analysis of Innovative Fast Neutron Systems

2014 ◽  
Author(s):  
S. Monti ◽  
A. Toti
Keyword(s):  
Fast Neutron ◽  
Nuclear Power ◽  
Chemical Properties ◽  
Fast Reactors ◽  
Major Step ◽  
Energy Agency ◽  
Member States ◽  
Technical Data ◽  
Reactor Technology ◽  
Experimental Facilities

The International Atomic Energy Agency (IAEA) recognizes the importance of the development and deployment of innovative fast neutron systems to assure the long-term sustainability of nuclear power. In this area the IAEA — with the fundamental support of its Technical Working Group on Fast Reactors (TWG-FR) where all the Member States with a programme on fast neutron systems are represented — acts as the major forum for international cooperation. On the basis of the recommendations provided by the TWG-FR, the IAEA defines and implements multiannual programmes which, in particular, are intended to help Member States in improving their capabilities in the development, design and safety analyses of innovative fast neutron systems. Thanks to the information and experimental data provided by the Member States, the IAEA is in the position to carry out benchmark exercises on different aspects of fast reactors, which contribute to the verification, validation and qualification of the simulation codes to be used for the design and the safety analyses of innovative concepts. Examples of such initiatives are the concluded coordinated research projects (CRPs) on BN-600, Monju and Phenix reactors, the on-going CRP on the EBR-II reactor and the planned CRPs on PFBR, CEFR, BN-800 and Monju reactors. The exchange of information and the collection of technical data within the TWG-FR also allow the IAEA to publish status reports and technical documents, as well as to develop databases with the most up-to-date information on existing and planned fast neutron systems. Furthermore, the IAEA is committed to promote the international harmonization of many aspects of the fast reactor technology. A major example is the development — together with the Generation IV International Forum — of internationally agreed Safety Design Criteria for sodium cooled fast reactors (SFR), which is a major step forward for the licensing of GEN-IV SFR prototypes and industrial demonstrators. Finally, a new CRP on “Sodium properties and safe operation of experimental facilities in support of the development and deployment of Sodium-cooled Fast Reactors (SFR) - NAPRO” has been recently launched in order to harmonize sodium physical and chemical properties to be used in the design of innovative SFRs, and to develop agreed design rules and best practices for sodium experimental facilities, as well as guidelines for the safe handling of sodium. With complementary objectives, the IAEA is also developing a catalogue of existing and planned experimental facilities in support of fast neutron system R&D programmes.

La situazione dell'energia nucleare nel mondo: un quadro di sintesi

2009 ◽  
pp. 19-36
Author(s):  
Maurizio Cumo
Keyword(s):  
Radioactive Waste ◽  
Nuclear Power ◽  
Nuclear Energy ◽  
Fuel Cycle ◽  
Technological Development ◽  
Reactor Technology ◽  
The World ◽  
Points Of View ◽  
Generation Costs ◽  
Jel Classifications

- This article gives an overview of the situation of nuclear power in the world and analyzes the problems of this source of energy from different points of view: the generation costs, fuel cycle, particularly with regard to the resources of uranium and radioactive waste, and the programs of technological development of new reactors.Key words: Nuclear energy, generation costs, uranium resources, radioactive waste, new reactor technology.JEL classifications: L94 Q40 Q31

scholarly journals Reactor Technology Rationale for Construction of Substitution and New Power Units in Ukraine after 2035

2020 ◽  
Vol 18 ◽  
pp. 10-22
Author(s):  
Y. M. Niearonov ◽  
◽  
T. Y. Baybuzenko ◽  
V. Y. Shenderovych ◽  
M. I. Vlasenko ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Renewable Energy Sources ◽  
Estimation Algorithm ◽  
Original Data ◽  
Comparative Assessment ◽  
Energy Agency ◽  
Reactor Technology ◽  
Installed Capacity

An algorithm of selecting the reactor technology type were constructed. The algorithm is based on a comparative assessment of the respective nuclear power plants. The formation of qualitative and quantitative criteria is performed for the estimation algorithm. Tools of the International Atomic Energy Agency (IAEA) INPRO-KIND project on multi-criteria comparative assessment of nuclear power plants for ranking the obtained results were adapted. The sensitivity analysis of the obtained results to change of numerical values and weight of criteria is carried out. The choice of the type of reactor technology for construction in Ukraine after 2035 is substantiated. It is shown that PWR and SMR reactor technologies in Ukraine are the most promising direction in the development of nuclear energy in Ukraine. Taking into account the factors of uncertainty and sensitivity to the values of the original data and possible risks, results of the analysis shows that there is a trend of advantages of SMR reactors, which generally have higher ratings compared to PWR, BWR and HWR. At the same time, the level of multi-criteria ratings of PWR reactors is close to SMR reactors. Making a further decision on the type of reactor technology for the conditions of Ukraine, it is necessary to take into account the possibility of its maximal total installed capacity deployment. It is necessary to conduct a separate study to determine the optimal ratio of reactor technologies PWR and SMR in the power system of Ukraine, taking into account the prospects for the deployment of renewable energy sources.

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