scholarly journals Advanced Heavy Water Reactor: A New Step Toward Sustainability

2021 ◽  
Vol 8 (3A) ◽  
Author(s):  
Ricardo Bastos Smith ◽  
Mahima Sachdeva ◽  
Indranil Bisuri ◽  
Roberto Vicente
Keyword(s):  
United States ◽  
Green Chemistry ◽  
Heavy Water ◽  
Half Life ◽  
Nuclear Power ◽  
The United States ◽  
Water Reactor ◽  
Nuclear Field ◽  
Heavy Water Reactor ◽  
Enriched Uranium

One of the great advances in the current evolution of nuclear power reactors is occurring in India, with the Advanced Heavy Water Reactor (AHWR). It is a reactor that uses thorium as part of its fuel, which in its two fueling cycle options, in conjunction with plutonium or low enriched uranium, produces energy at the commercial level, generating less actinides of long half-life and inert thorium oxide, which leads to an optimization in the proportion of energy produced versus the production of burnt fuels of the order of up to 50%. The objective of this work is to present the most recent research and projects in progress in India, and how the expected results should be in compliance with the current sustainability models and programs, especially the "Green Chemistry", a program developed since the 1990s in the United States and England, which defines sustainable choices in its twelve principles and that can also be mostly related to the nuclear field. Nevertheless, in Brazil, for more than 40 years there has been the discontinuation of research for a thorium-fueled reactor, and so far there has been no prospect of future projects. The AHWR is an important example as an alternative way of producing energy in Brazil, as the country has the second largest reserve of thorium on the planet.

Decoupling Criteria for Multi-Connected Equipment

1998 ◽  
Vol 120 (1) ◽  
pp. 93-98 ◽  
Author(s):  
G. R. Reddy ◽  
H. S. Kushwaha ◽  
S. C. Mahajan ◽  
K. Suzuki
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Internal Structure ◽  
Heavy Water ◽  
Nuclear Power ◽  
Seismic Analysis ◽  
Real Life ◽  
Water Reactor ◽  
Reactor Building ◽  
Heavy Water Reactor

Generally, for the seismic analysis of nuclear power plant structures, requirement of coupling equipment is checked by applying USNRC decoupling criteria. This criteria is developed for the equipment connected to the structure at one location. In this paper, limitations of this criteria and modifications required for application to real life structures such as pressurized heavy water reactor building are discussed. In addition, the authors endeavor to present a decoupling model for multi-connected structure-equipment. The applicability of the model is demonstrated with pressurized heavy water reactor building internal structure and steam generator.

Sensitivity Degradation Characteristics of Incore Neutron Detector for Heavy Water Reactor, Fugen NPP

2002 ◽  
Author(s):  
Tsuyoshi Okawa ◽  
Naoyuki Yomori
Keyword(s):  
Thermal Neutron ◽  
Heavy Water ◽  
Power Distribution ◽  
Neutron Detector ◽  
Nuclear Power ◽  
Operating Cost ◽  
Water Reactor ◽  
Mox Fuel ◽  
Heavy Water Reactor ◽  
Test Reactor

Fugen nuclear power plant is a 165MWe, heavy water-moderated, boiling light water-cooled, pressure tube-type reactor developed by JNC, which is the world’s first thermal neutron power reactor to utilize mainly Uranium and Plutonium mixed oxide (MOX) fuel. Fugen has been loaded a total of 726 MOX fuel assemblies since the initial core in 1978. Each incore neutron detector assembly of Fugen composed of four Local Power Monitors (LPM) is located at sixteen positions in the area of heavy water moderator in the core and monitors its power distribution during operation. The thermal neutron flux of Fugen is relatively higher than that of Boiling Water Reactor (BWR), therefore LPM, which is comprised of a fission chamber, degrades more quickly than that of BWR. An Improved Long-life LPM (LLPM) pasted inner surface wall of the chamber with 234U/235U at a ratio of 4 to 1 had been developed through the irradiation test at Japan Material Test Reactor (JMTR). The 234U is converted to 235U with absorption of neutron, and compensates the consumption of 235U. LPM has been loaded to the initial core of Fugen since 1978. JNC had evaluated its sensitivity degradation characteristics through the accumulated irradiation data and the parametric survey for 234σa and 235σa. Based on the experience of evaluation for sensitivity degradation, JNC has applied shuffling operation of LPM assemblies during an annual inspection outage to reduce the operating cost. This operation realizes the reduction of replacing number of LPM assemblies and volume of radioactive waste. This paper describes the sensitivity degradation characteristics of incore neutron detector and the degradation evaluation methods established in Fugen.

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.

scholarly journals Nuclear viewpoint in India

2017 ◽  
Vol 4 ◽  
Author(s):  
Anshu Bharadwaj ◽  
Lakshminarayana Venkat Krishnan ◽  
Subramaniam Rajagopal
Keyword(s):  
Heavy Water ◽  
Nuclear Power ◽  
Clean Energy ◽  
Pressurized Water ◽  
Heavy Water Reactor ◽  
Water Reactors ◽  
Near Term ◽  
Enriched Uranium ◽  
Installed Capacity

ABSTRACTNuclear power is a crucial source of clean energy for India. In the near-term, India is focusing on thermal reactors using natural and enriched uranium. In the long-term, India is exploring various options to use its large thorium reserves.India’s present nuclear installed capacity is 5680 MW, which contributes to about 3.4% of the annual electricity generation. However, nuclear power is an important source of energy in India’s aspirations for energy security and also in achieving its Intended Nationally Determined Contributions (INDC), of 40% fossil free electricity, by 2030. India has limited uranium reserves, but abundant thorium reserves. The Nuclear Suppliers Group (NSG) lifted restrictions on trade with India, in 2008, enabling India to import uranium (natural and enriched) and nuclear reactors. In the near–term (2030), the nuclear capacity could increase to about 42,000 MW. This would be from a combination of domestic Pressurized Heavy Water Reactors (PHWR) and imported Pressurized Water Reactors (PWR). For the long–term (2050), India is exploring various options for utilising its vast thorium reserves. This includes Advanced Heavy Water Reactor and Molten Salt Breeder Reactor. However, generating public acceptance will be crucial to the expansion of the nuclear power program.

Aerial work robot for a nuclear power plant with a pressurized heavy water reactor

2016 ◽  
Vol 92 ◽  
pp. 284-288 ◽  
Author(s):  
Hocheol Shin ◽  
Changhoi Kim ◽  
Yongchil Seo ◽  
Kyungmin Jeong ◽  
Youngsoo Choi ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Heavy Water ◽  
Nuclear Power ◽  
Water Reactor ◽  
Heavy Water Reactor

A Case Study for INPRO Methodology Based on Indian Advanced Heavy Water Reactor

2004 ◽  
Author(s):  
K. Anantharaman ◽  
D. Saha ◽  
R. K. Sinha
Keyword(s):  
Heavy Water ◽  
Nuclear Power ◽  
Fuel Cycle ◽  
Energy System ◽  
Water Reactor ◽  
Fuel Cycles ◽  
Heavy Water Reactor ◽  
Tube Type ◽  
Near Future

Under Phase 1A of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) a methodology (INPRO methodology) has been developed which can be used to evaluate a given energy system or a component of such a system on a national and/or global basis. The INPRO study can be used for assessing the potential of the innovative reactor in terms of economics, sustainability and environment, safety, waste management, proliferation resistance and cross cutting issues. India, a participant in INPRO program, is engaged in a case study applying INPRO methodology based on Advanced Heavy Water Reactor (AHWR). AHWR is a 300 MWe, boiling light water cooled, heavy water moderated and vertical pressure tube type reactor. Thorium utilization is very essential for Indian nuclear power program considering the indigenous resource availability. The AHWR is designed to produce most of its power from thorium, aided by a small input of plutonium-based fuel. The features of AHWR are described in the paper. The case study covers the fuel cycle, to be followed in the near future, for AHWR. The paper deals with initial observations of the case study with regard to fuel cycle issues.

Design- and Operating-Bases Regional Meteorological Conditions for Permitting New Nuclear Power Plants in the United States

2009 ◽  
Author(s):  
Ping K. Wan ◽  
Alice C. Carson
Keyword(s):  
United States ◽  
Nuclear Power ◽  
Greenhouse Gas Emission ◽  
The United States ◽  
Snow Accumulation ◽  
Meteorological Conditions ◽  
Boiling Water ◽  
Boiling Water Reactor ◽  
Pressurized Water ◽  
Water Reactor

Power generation is well recognized as a major prerequisite for a country’s economic development. Nuclear power has become an increasingly attractive alternative in the power market worldwide due to several factors: growing demand for electric power, increasing global competition for fossil fuels, concern over greenhouse gas emission impacts on global warming, and the desire for energy independence. Protecting people and the environment is of concern to nuclear power generators. Thus, sound engineering design that provides adequate protection against natural and man-made hazards is of utmost importance. Meteorological parameters related to structure design and system operation are the extreme and mean values for wind speed, temperature, humidity, and precipitation, as well as the seasonal and annual frequencies of severe weather conditions such as tornadoes and hurricanes, ice and snow accumulation, hail and lightning. Inherent in ascertaining values for these parameters is the need for reasonable assurance that the chosen values and frequencies will not be exceeded during the expected life of the plant. All regional meteorological and air quality conditions are classified as climate site characteristics for consideration in evaluating the design and operation of a nuclear power plant [1]. This paper discusses the regulatory requirements, methodology and sources of data for development of the design- and operating-basis regional meteorological conditions used in preparing a Combined License Permit Application (COLA) in the United States. Additionally, the differences in methodology for determination of these meteorological conditions by reactor type (i.e., Advanced Passive 1000–AP1000, Advanced Boiling Water Reactor–ABWR, Economic Simplified Boiling Water Reactor–ESBWR, U.S. Evolutionary Power Reactor–U.S. EPR, and Advanced Pressurized Water Reactor–APWR) are explored and summarized.

Instrumentation and Control Systems for Sizewell B

1993 ◽  
Vol 26 (5) ◽  
pp. 132-138 ◽  
Author(s):  
D B Boettcher ◽  
E M Hickling
Keyword(s):  
United States ◽  
Control Systems ◽  
Nuclear Power Station ◽  
Nuclear Power ◽  
The United States ◽  
Pressurized Water Reactor ◽  
Power Station ◽  
Pressurized Water ◽  
Water Reactor ◽  
And Control

Sizewell B is the first nuclear power station to be built in the UK using the pressurized water reactor system. Although the design is based on that of pressurized water reactor stations constructed in the United States, many changes and new features have been introduced to suit British practice and licensing requirements. Among the novel features of Sizewell B are entirely new designs for the man-machine interfaces in the main control and auxiliary shutdown rooms, and for the control and instrumentation systems. These new designs incorporate lessons learned by Nuclear Electric as an electrical utility and nuclear power station operator. This paper describes the development of the designs for the control rooms, and instrumentation and control systems, explaining some of the thinking that lay behind the design decisions. It also contrasts the practices employed on Sizewell B with some of the latest thinking coming out of the United States.

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