Nuclear energy in India

Traditional safety performance requirements for nuclear reactors have been developed for critical reactors, whose kinetics characteristics differ significantly from sub-critical, accelerator-driven nuclear reactors. In a critical nuclear reactor, relatively small amounts of reactivity (negative or positive) can produce large changes in the fission rate. In sub-critical reactors, the self-multiplication (k) decreases as the sub-criticality (1-k) increases, and the responsiveness to small reactivity changes decreases. This makes sub-critical nuclear reactors less responsive to positive reactivity insertions than critical reactors. Also, larger negative reactivity insertions are needed in sub-critical reactors to shut down the fission chain if the neutron source remains. This paper presents the results from a computational analysis of the safety performance of sub-critical, accelerator-driven nuclear reactors. Coupled kinetics and thermal-hydraulics models are used to quantify the effectiveness of traditional protection and control system designs in sub-critical reactors. The analyses also quantify the role of inherent, passive reactivity feedback mechanisms in sub-critical reactors. Computational results are used to develop conclusions regarding the most favorable and effective means for reactor control and protection in sub-critical, accelerator-driven nuclear reactors.

Nuclear power represents an unfulfilled promise in India. Yet the ambition to become a developed economy by 2047 and achieve net zero emissions by 2070 will require large investments in nuclear energy. Achieving success on this counts, however, will require three major transformations simultaneously: an ideational transformation, an institutional transformation, and a legal transformation—changes that demand deeper and more systematic thinking in India. New Delhi's economic and climate change ambitions going forward cannot be realized without greater foreign participation in its nuclear industry, which in turn demands bold reforms in India’s nuclear estate.

This publication has been prepared from contributions submitted by many international experts to the five Working Groups for the preparation of the technical volumes. The content does not necessarily reflect the views of IAEA Member States, or the organizations nominating experts. Great care has been taken to maintain the accuracy of information contained in this publication. Neither the IAEA, nor its Member States, however, assume any responsibility for consequences that may arise from its use, nor are any warranties made of any kind in connection with this publication. This publication is not intended to address issues of responsibility, legal or otherwise, for acts or omissions on the part of any person or entity. Extracts from this publication may be freely used elsewhere, provided that acknowledgement of the source is made. If any attribution in this publication indicates that the information (including photographs and graphics) is from a source or site external to the IAEA, permission for reuse must be sought from the originating source. The use of particular designations of countries or territories does not imply any judgement by the IAEA as to the legal status of such countries or territories, or of the delimitation of their boundaries, or of their authorities and institutions. The mentioning of names of specific companies or products, whether or not indicated as registered, does not imply any intention to infringe proprietary rights, nor should it be construed as an endorsement or recommendation on the part of the IAEA. The IAEA assumes no responsibility for the accuracy or continued existence of URLs for external or third party Internet web sites referred to in this publication and does not guarantee that any content on such web sites is, or will remain, accurate or appropriate.

This paper introduces the concept of the VSM method being used to represent the organization of NPPs in responding to accidents. The Fukushima accident is addressed as a method for the examination of the VSM method and its utility is seeing the ‘big’ picture as far as the decision-making aspects of organizations are concerned. The impact of accidents upon the NPP management operations is covered and how the organization has to change following an accident is covered. The paper points out the fact that often accident situations and their responses are affected by the long term decisions of management. The decision of TEPCO to disregard advice on the possibility of a large tsunami occurring was a critical fault and preventive methods should have been considered along with the risk of not taking actions. Recommendations are made for improvements in emergency procedures during accident control and mitigation, the procedures should be flexible and based upon something like the symptom-ba...

This paper explores the nature of expert knowledge-claims made about catastrophic reactor accidents and the processes through which they are produced. Using the contested approval of the AP1000 reactor by the US Nuclear Regulatory Commission (NRC) as a case study and drawing on insights from the Science and Technology Studies (STS) literature, it finds that the epistemological foundations of safety assessments are counterintuitively distinct from most engineering endeavors. As a result, it argues, those assessments (and thus their authority) are widely misconstrued by publics and policymakers. This misconstrual, it concludes, has far-reaching implications for nuclear policy, and it outlines how scholars, policymakers, and others might build on a revised understanding of expert reactor assessments to differently frame, and address, a range of questions pertaining to the risks and governance of atomic energy.

The development of fast breeder reactor (FBR) design codes in Europe has been determined by the way in which the FBR itself has developed. Until 4 yr ago, there were four main streams of development, each largely independent, but with a small amount of international participation. In parallel with the independent development of reactor systems in Europe, different approaches to design codes have emerged. Until the Superphénix project, there was a deliberate attempt to avoid developing any formal code before proceeding with design and construction. France is the only European country to have published a complete code concerning FBR components: RCC-MR (Règles de Construction et de Conception des Matériels mécaniques des Réacteurs rapides-Design and Construction Rules for Mechanical Equipment in Fast Breeder Reactors). In 1984, five European governments (Belgium, France, Italy, the United Kingdom, and the Federal Republic of Germany) agreed to a coordinated program for FBR research, development, and construction. The ultimate outcome must be a common design code. Drawing up such a design code represents a major challenge in the field of international collaboration. It seems likely that the existing RCC-MR code will be used as the starting point for the development of European design rules. Recently, European manufacturers set up a committee with the object of amending and supplementing RCC-MR. BACKGROUND OF THE DEVELOPMENT OF FAST BREEDER REACTOR DESIGN CODES

The article considers the transmissions and effects of a digital letter, and its implications for multi-situated-as opposed to a multi-sited-anthropology. Multi-situated moves beyond multiple sites as supplementary contexts to the life flows of people, materials, and ideas, to consider multi-ontological, dynamic, and temporally contingent situations constitutive of such movements in the making, that are embedded and/or enfolded along several intersecting planes on-and offline. The public letter was written collaboratively in May 2012 by activists in Britain, agreed to and signed off by supportive British members of Parliament among others, and addressed to the then prime minister of India and the chief minister of the state of Tamil Nadu. The letter's contents pertained to the Kudankulam Nuclear Power Plant in south India, with concerns about mandatory procedures in the construction of a nuclear power station, and democratic and human rights abuses against nonviolent protestors. By focusing on the emergence, travels, and receptive trajectories of the letter, the article makes a case for the increasing need to encompass aspects of digital anthropology not as a discrete subdiscipline, but as an integral part of core anthropological focus and method for the study of "onlife" entanglements-what effectively has become the digitalia of everyday life.

A comparative study has been made on the mechanical energy released in a core disruptive accident resulting from an unprotected loss of flow accident (LOFA) in a medium sized liquid metal fast breeder reactor with oxide, carbide and metal fuels. The study is conducted by ignoring the passive safety features incorporated in the design so that the accident scenario culminates in an energetic disassembly of the core with large energy release. The paper further provides the salient features of the analysis and presents the results with suitable physical explanations.

This article explores the safety capabilities of the 500 MWe Prototype Fast Breeder Reactor that is under construction in India, and which is to be the first of several similar reactors that are proposed to be built over the next few decades, to withstand severe accidents. Such accidents could potentially breach the reactor containment and disperse radioactivity to the environment. The potential for such accidents results from the reactor core not being in its most reactive configuration; further, when there is a loss of the coolant, the reactivity increases rather then decreasing as in the case of water-cooled reactors. The analysis demonstrates that the official safety assessments are based on assumptions about the course of accidents that are not justifiable empirically and the safety features incorporated in the current design are not adequate to deal with the range of accidents that are possible.

This paper reviews major computer code packages presently utilized or under active development in the u.s. for deterministic liquid-metal fast breeder reactor safety analysis. Although the review covers the very large accident domain from intact predisassembly geometry through radiological consequences, an attempt was made to categorize code systems according to the physical problems solved to provide a working orientation for those not intimately involved in the field. Mathematical and computational aspects were given particular focus in the hope of stimulating development of more efficient numerical approaches in those areas of greatest need.

A follow-up calculation was made on the accident of Reactor No. 4 of the Chernobyl Nuclear Power Plant based on the literature and accident reports published by the USSR. The analysis code system used had models peculiar to a pressure tube type reactor, of which the accuracy had been verified by the experimental facilities at the O-arai Engineering Center and the tests made at the "Fugen" Nuclear Power Plant. The analysis data were prepared based on plant specifications and its operation history obtained from those published literature and accident reports. The analysis was composed of (1) a calculation of the nuclear and thermal-hydraulic characteristics, and the graphite heating and temperature distributions which were the basic data for the follow-up calculation of the accident, (2) an analysis of the plant behavior before the test started, using these basic characteristics, and (3) a follow-up calculation of the power increase which occurred after the test started. The analytical results were found to agree well with the data published by the USSR. It was confirmed from these analyses that the main factors causing the accident were the increased enthalpy at the core entrance caused by the test made at low power level and the increased void fraction due to reduced coolant flow rate, in addition to the nuclear characteristics and performance of the control system peculiar to the Chernobyl Nuclear Power Plant.

Different inherent safety concepts being considered in fast and thermal reactors are presented after outlining the basic goals of nuclear reactor safety, the 'defence in depth' philosophy to achieve these goals and the characteristics affecting the safety of liquid metal fast breeder and light water reactors. The inherent safety potential of fast reactors with respect to different sizes and types of fuel is also discussed. Finally, the approach proposed for the Indian Prototype Fast Breeder Reactor (PFBR), which is in the detailed design stage, is also presented.

Criticality and recriticality considerations in heavy liquid metal fast reactors (HLMFRs) after a hypothetical core meltdown accident are discussed. Although many aspects of system behaviour in such scenarios can be deduced directly from the classical theory of sodium-cooled fast reactors (SFRs), certain ideas that have been accepted as true for SFRs cannot be extrapolated to HLM-FRs without sufficiently careful thought. In this paper, we are concerned, as in SFRs, with fuel compaction, but with one important difference: there would be no boiling of the surrounding heavy liquid metal pool. Utilizing a Bethe-Tait model, it is shown that, due to the power flattening effect of the heavy liquid metal, explosive excursions at least an order of magnitude higher than for SFRs in similar situations are conceivable. aaaaaaaaaaa aKeywords. hypothetical core disruptive accidents, heavy liquid metal reactor, recriticality. disassembly phase, Bethe-Tait model

Atomic Energy Regulatory Board (AERB) is the national authority to ensure that the use of ionizing radiation and nuclear energy in India does not cause undue risk to the health of workers and members of the public, and the environment. AERB fulfills its mission by stipulating and enforcing rules and regulations concerned with nuclear and radiological safety. This paper describes the regulatory authorization process of AERB as applicable to nuclear power plants (NPPs) during their construction as well as operating phases. The safety review process during construction is presented as case studies. Some current issues related to operating plants are also described. Two typical examples of safety upgradations made in old generation nuclear plants are given. The regulatory process in India is continuously evolving to cater to the new developments. Some of the recent initiatives taken by AERB in that direction are briefly described. Today AERB faces new challenges like simultaneous review of a large number of new projects of diverse designs, a fast growing nuclear power program and functioning of operating plants in a competitive environment. This paper delineates how AERB is gearing up itself to meet these challenges in an effective manner.

Chapter for Human Rights in India, ed. Satvinder Juss We have been here [in Trichy Women's Prison] for over a month. We get charged with new cases every time we are taken to the Court. It is only after being part of the [anti-nuclear] struggle that we realized that trying to establish one's right to live as one wishes, pursuing traditional livelihoods and also questioning activities that are being implemented without consulting the people is equivalent to crime and sedition (Sundari 2012). 1 At the Press Club of India in New Delhi, Amnesty International launched its 2006 report among a room full of journalists, activists and scholars. It was concluded for the first time that India and China's rapid development has become another progenitor of human rights abuses. As the report reads for the two countries: 'Economic development did not prioritlze realization of economic, social and cultural rights'. 2 In comparison to China, India is renowned as the 'world's largest democracy'. 3 However, the juggernaut of neoliberal policies from the 1990s,

After the successful operation of the fast breeder test reactor for over two decades, India is now nearing the completion of a 500 MW (electrical) prototype fast breeder reactor. This commercial scale power reactor is a sodium-cooled, pool-type, mixed-oxide fuelled fast reactor. The stability characteristics of the reactor are an important safety aspect to be studied. In the present work, linear stability of the prototype fast breeder reactor analysis is carried out using the transfer function method, while the stability of the system is checked via the Nyquist criteria. For the completeness of the study, transient analysis with various kinds of reactivity perturbations was carried out. The response of the system in both cases indicated that the system is stable.

The neutronics analysis of selected start-up tests conducted from 2010 to 2011 in China Experimental Fast Reactor (CEFR) is carried out using in-house FARCOB and European ERANOS-2.1 code systems as a part of IAEA coordinated research project (CRP) on “Neutronics Benchmark of CEFR Start-Up Tests”. This exercise has the main objective of validation and verification of physical models, neutronics simulation methodology including cross-section libraries that is used for fast reactor core simulations. It is challenging to simulate such a small compact core of enriched uranium with high neutron leakage having stainless steel radial reflector by using 3-D diffusion theory codes. This benchmark analysis used a new simplified approach such as a 3-step method and experimental method for simulating temperature and sodium void reactivity coefficients. Net criticality, control rod worth, temperature and sodium void reactivity coefficients and swap reactivity could be predicted well within their measured error values. This exercise provided an additional validation of the FARCOB system against small sodium-cooled fast reactor (SFR) cores, and it can be confidently used for the design and analysis of small experimental reactor cores.

Counterfeit equipment is becoming a major threat to nuclear safety globally. The Kudankulam Nuclear Power Plant (KKNPP) in India housing two VVER-1000 reactors, imported from Russia is being delayed because of counterfiet, substandard and obsolete equitpment. The polar crane, the limb of the reactor, is defective as its hoisting capacity is less than 80% of its nameplate capacity. The crane is used for installing the equipment inside the reactor building and also for removing spent fuel. The contract said that there will be no weld in the beltline of the reactor pressure vessel (RPV). The received vessels have two circumferential welds on the beltline. RPV, the heart of the reactor is irreplaceable and hence determines the life of the reactor. RPV and polar crane are safety grade equipment. The core-damage frequency (CDF) of the reactor in the contract was 10−7 reactor-years, while the supplied reactor has a CDF of 10−5 reactor-years. Two units of generator transformers were receive...

In-service inspection (ISI) plays a major role in monitoring the condition of nuclear power plant structures and components. Based on the information gathered during inspection and the studies carried out, it is possible to assess the extent of damage and take corrective measures to keep effects of ageing under control. In nuclear power plants comprehensive ISI is dictated by issues of increased safety to personnel and equipment, and efficiently enhances the plant life. A special emphasis has been laid on the development of robotic devices for the ISI of the indigenous Indian 500 MWe Prototype Fast Breeder Reactor (FBR) components. This paper traces the experiments and simulations in the key developments of a robotic device, for the ISI of main vessel and safety vessel of FBRs, carried out at Indira Gandhi Centre for Atomic Research, India.

Malaysia has initiated a range of pre-project activities in preparation for its planned nuclear power programme. Clearly one of the first steps is the selection of sites that are deemed suitable for the construction and operation of a nuclear power plant. Here we outline the Malaysian regulatory requirements for nuclear power plant site selection, emphasizing details of the selection procedures and site characteristics needed, with a clear focus on radiation safety and radiation protection in respect of the site surroundings. The Malaysia Atomic Energy Licensing Board (AELB) site selection guidelines are in accord with those provided in International Atomic Energy Agency (IAEA) and United Stated Nuclear Regulatory Commission (USNRC) documents. To enhance the suitability criteria during selection, as well as to assist in the final decision making process, possible assessments using the site selection characteristics and information are proposed.

Tests in support of LMFBR projects for potential incidents involving a hypothetical core disruptive accident or sodium-water interactions in steam generators have two possible goals: (i) to evaluate the integrity of the primary containment after the design is frozen or (2) to investigate design options in support of primary "containment design. The test planning approach differs depending on the goal. The Fast Flux Test Facility tests had the first goal, the current Clinch River Breeder Reactor tests have the second goal. This paper discusses test planning, sources for simulating loads, modeling, and instrumentation. The main source described involves controlled venting of explosive gases. The source avoids generation of undesirable shock waves and facilitates calibration because the reaction rate of the explosive is independent of the response. It is indicated that the test program requiring the least time and cost involves a mixture of three types of models: small simple models, small complex models, and large complex models. Instrumentation is discussed that is required for validation of loading, response measurements for comparison with calculations, and response measurements on critical members where predictions are not possible. i.

A shake table of 100 MT, largest in India was established at Indira Gandhi Center for Atomic Research, Kalpakam for conducting seismic qualification experiments of large size components of Fast Breeder Reactor. The table is placed on massive block foundation. The site is collocated with major safety structures. Attenuation relations were evaluated for rock blasting to avoid blasting related damage to the structures and personal. This paper presents the details of design and construction methodology adopted for this structure.

Counterfeit equipment is becoming a major threat to nuclear safety globally. The Kudankulam Nuclear Power Plant (KKNPP) in India housing two VVER-1000 reactors, imported from Russia is being delayed because of counterfiet, substandard and obsolete equitpment. The polar crane, the limb of the reactor, is defective as its hoisting capacity is less than 80% of its nameplate capacity. The crane is used for installing the equipment inside the reactor building and also for removing spent fuel. The contract said that there will be no weld in the beltline of the reactor pressure vessel (RPV). The received vessels have two circumferential welds on the beltline. RPV, the heart of the reactor is irreplaceable and hence determines the life of the reactor. RPV and polar crane are safety grade equipment. The core-damage frequency (CDF) of the reactor in the contract was 10−7 reactor-years, while the supplied reactor has a CDF of 10−5 reactor-years. Two units of generator transformers were receive...

Vikram Sarabhai formulated an ambitious profile for the development of atomic energy in India. Despite challenges arising from denial of international cooperation for several decades, technologies envisioned in the profile have been developed and the Department of Atomic Energy is now working to implement the technologies with the objective of accelerating the growth of installed nuclear capacity in the country.

Criticality and recriticality considerations in heavy liquid metal fast reactors (HLMFRs) after a hypothetical core meltdown accident are discussed. Although many aspects of system behaviour in such scenarios can be deduced directly from the classical theory of sodium-cooled fast reactors (SFRs), certain ideas that have been accepted as true for SFRs cannot be extrapolated to HLM-FRs without sufficiently careful thought. In this paper, we are concerned, as in SFRs, with fuel compaction, but with one important difference: there would be no boiling of the surrounding heavy liquid metal pool. Utilizing a Bethe-Tait model, it is shown that, due to the power flattening effect of the heavy liquid metal, explosive excursions at least an order of magnitude higher than for SFRs in similar situations are conceivable. aaaaaaaaaaa aKeywords. hypothetical core disruptive accidents, heavy liquid metal reactor, recriticality. disassembly phase, Bethe-Tait model

Analysis of the Fukushima nuclear reactor disaster will show how to learn from failures using multi-models. This type of analysis can enrich the modelling of causal factors, provide insight into policy making and support decisions for resource allocations to prevent such disasters. The analysis presented here is based on a workshop on learning from failures in which participants were first given a brief about the related theory, then an introduction to the analytical techniques that can be used such as FTA, and RBD. They were then given a brief in the form of a narrative of the accident derived from investigation reports and divided into small groups tasked to analyse the disaster and to present their recommendations both orally and in a written report. All the participants were asked to follow a certain presentation format. Firstly there would be a technical account of the sequence of events that would be based on research of greater depth than provided in the initial summary, one related more to the scope of their analysis. This would be followed by a review of the consequences of the accident, a presentation of their multi-model analysis of the event and a summary of generic lessons and recommendations to prevent future failures of such systems. Finally, collective feedback, focused on the generic lessons gained, was offered.

The international nuclear power community has proposed six new Generation IV nuclear reactor designs for use later this century. These include reactors cooled by gas, lead and water, as well as high molten salt reactors and the SFR (Sodium-cooled Fast Reactor) [1] (Figure ). To support the development of these innovative reactors, a wideranging research and development programs are now under way. A number of technology goals lie on the research -for example, improving nuclear safety and reliability; sustainability and minimizing waste; and reducing the cost of building and running nuclear plants. The SFR, in particular, is a fast-neutron spectrum one with a closed fuel cycle for efficient conversion of fertile uranium and management of actinides. The SFR reactor uses a fast neutron spectrum and liquid sodium as coolant to remove the heat from the core. In effects, the liquid sodium is an excellent cooling agent, mainly because of his its good heat transfer capabilities, low melting point (97.8 °C at p= 1 atm) and large margins to the boiling point (883 °C, at p= 1 atm) at ambient pressure and also low viscosity. The SFR can increase the efficiency of uranium usage by breeding plutonium and it is designed to allow any transuranic isotope to be consumed (and in some cases used as fuel). In practice, due to the its fast neutron spectra, SFR has the capability to utilize almost all of Energia & Ricerca LA TERMOTECNICA luglio/agosto 2012

Nuclear power is currently the fourth largest source of electricity production in India after thermal, hydro and renewable sources of electricity. Currently, India has 20 nuclear reactors in operation and seven other reactors are under construction. Most of these reactors are indigenously designed and built Heavy Water Reactors. In addition, a 300 MWe Advanced Heavy Water Reactor has already been designed and in the process of deployment in near future for demonstration of power production from Thorium apart from enhanced safety features by passive means. India has ambitious plans to enhance the share of electricity production from nuclear. The recent Fukushima accident has raised concerns of safety of Nuclear Power Plants worldwide. The Fukushima accident was caused by extreme events, i.e., large earthquake followed by gigantic Tsunami which are not expected to hit India's coast considering the geography of India and historical records. Nevertheless, systematic investigations have been conducted by nuclear scientists in India to evaluate the safety of the current Nuclear Power Plants in case of occurrence of such extreme events in any nuclear site. This paper gives a brief outline of the safety features of Indian Heavy Water Reactors for prevention and mitigation of such extreme events. The probabilistic safety analysis revealed that the risk from Indian Heavy Water Reactors are negligibly small.

The nuclear accident at Fukushima in Japan occurred almost exactly 25 years after the Chernobyl nuclear accident in 1986. Analysis of each provides valuable late and early lessons that could prove helpful to decision-makers and the public as plans are made to meet the energy demands of the coming decades while responding to the growing environmental costs of climate change and the need to ensure energy security in a politically unstable world. This chapter explores some key aspects of the Chernobyl and Fukushima accidents, the radiation releases, their effects and their implications for any construction of new nuclear plants in Europe. There are also lessons to be learned about nuclear construction costs, liabilities, future investments and risk assessment of foreseeable and unexpected events that affect people and the environment. Since health consequences may start to arise from the Fukushima accident and be documented over the next 5–40 years, a key lesson to be learned concerns ...

Fast breeder reactors like Monju are uneconomical and will remain so for the foreseeable future; the electricity produced by them is significantly more expensive than that produced by ordinary (thermal) reactors. Obtaining the security of nuclear energy resources, the ostensible reason given for Japan's interest in breeder reactors, is not an acceptable reason for acquiring breeders. The development of fast breeder reactors,including Monju, is also a direct threat to nuclear non-proliferation, being ideal for the production of high-quality weapons usable plutonium. On these grounds alone there is no justification for the operation of Monju. This paper has focussed on an equally serious threat posed by FBR's and Monju in particular, as well as the threat of accidents leading to the contamination of the environment and human population.

This paper applies the Beer Viable Systems Model (VSM) approach to the study of nuclear accidents. It relates how organizational structures and rules are affected by accidents in the attempt to improve safety and reduce risk. The paper illustrates this process with reference to a number of accidents. The dynamic cybernetic aspect of the VSM approach to organizations yields a better understanding of the need for good decision-making to minimize risk and how organizations really operate.

This article chronicles the rise and fall of fast-reactor research in the United States. Research on fast reactors began at the end of World War II and represented a large fraction of the total U.S. research effort on civilian nuclear energy until the early 1980s. The goal of most of this research was to develop a plutonium breeder reactor capable of producing more plutonium from U-238 than is consumed. But with the termination of the Clinch River Breeder Reactor project in 1983, fast reactor development in the United States essentially ended. Safety issues played a role in this end to the fast breeder reactor program, but more important reasons were nuclear proliferation concerns and a growing conviction that breeder reactors would not be needed or economically competitive with light water reactors for decades, if ever. EARLY HISTORY Immediately after the bombing of Pearl Harbor on December 7, 1941, research on plutonium production for atomic weapons was consolidated at the University of Chicago under Nobel Laureate Arthur H. Compton. The "Metallurgical Laboratory" (later to become Argonne National Laboratory) was the code name given to Compton's facility. It was here that a small group of scientists led by Enrico Fermi built the world's first reactor, Chicago Pile-1 (CP-1), which achieved initial criticality on December 2, 1942. During the next two years, work on the development of plutonium production reactors shifted to Oak Ridge, Tennessee and then Hanford, Washington. By early 1944, Compton and the Chicago scientists began thinking about the role of the Metallurgical Laboratory after the war. 1 On the morning of April 26,

the implementation of the mitigation and upgraded safety measures. Further, the paper attempts to address the question of public trauma in the event of a serious nuclear reactor accident, a need that has been felt in view of the recent Fukushima and earlier Chernobyl accidents and the resulting large scale relocation due to the present deficient policies and the inherent limitations of Linear No Threshold (LNT) principle.

At present, nuclear energy is used in 31 countries, producing roughly 13 % of the world’s commercial electricity, and currently 15 countries are in the process of planning the building of new nuclear capacity. There are 435 nuclear power reactors in operation around the world--at the peak of nuclear generation in 2002 there were 444--of which 189 are in pan-Europe and the Russian Federation, comprising about one third of the world’s 146 civil reactors, with France alone generating close to half of the EU’s nuclear production from 58 plants (Schnieder et al, 2011; European Nuclear Society, 2012).

The 11 March 2011 tsunami was probably the fourth largest in the past 100 years and killed over 15 000 people. The magnitude of the design tsunami triggering earthquake affecting this region of Japan had been grossly underestimated, and the tsunami hit the Fukushima Dai-ichi nuclear power plant (NPP), causing the third most severe accident in an NPP ever. Interestingly, while the Onagawa NPP was also hit by a tsunami of approximately the same height as Dai-ichi, it survived the event ‘remarkably undamaged’. We explain what has been referred to as the cascade of engineering and regulatory failures that led to the Fukushima disaster. One, insufficient attention had been given to evidence of large tsunamis inundating the region earlier, to Japanese research suggestive that large earthquakes could occur anywhere along a subduction zone, and to new research on mega-thrusts since Boxing Day 2004. Two, there were unexplainably different design conditions for NPPs at close distances from ea...

A comparative study has been made on the mechanical energy released in a core disruptive accident resulting from an unprotected loss of flow accident (LOFA) in a medium sized liquid metal fast breeder reactor with oxide, carbide and metal fuels. The study is conducted by ignoring the passive safety features incorporated in the design so that the accident scenario culminates in an energetic disassembly of the core with large energy release. The paper further provides the salient features of the analysis and presents the results with suitable physical explanations.

Today energy is the major concern throughout the world. Due to rise in population there is strong energy demand around the world. The existing reserves of coals are not sufficient enough to meet this energy demand. Increase in fossil fuel based energy supply inevitably leads to environmental issues. Renewable energy sources like solar, wind, etc. are fast emerging as promising alternatives to traditional energy. The most complicating issues is the desire for energy sources to be sustainable and globally scalable in order to meet the large concentrated energy needs for industries and urban centers, the energy sources must be deployed to the fullest extent as possible. Thus, not only in India, but from a global perspective, nuclear energy has become a viable, sustainable and clean energy source of future. Traveling-wave reactor (TWR) technology, promises a potential solution to these limitations by offering a nuclear energy resource which is truly sustainable at full global scale. TWRs are capable of offering a ~40-fold gain in fuel utilization efficiency compared to conventional reactors.

This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their empioyets, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not nccessariiy constitute or imply its endorsement, m mmendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof. DISCLAIMER Portions of this document may be illegible electronic image products. Images are produced from the best available original document.

In reactor analysis, perturbation method is a well established and frequently used technique for calculating the changes in neutron multiplication factor or the neutron distribution within reactor due to perturbation. Time independent perturbation theory is mainly used for the estimation of parameters like material void worth, Doppler constant, core expansion worth etc in critical condition, which are the required inputs for safety analysis of reactor. Usually the 1 st order approximation to the perturbation theory is applied to estimate the perturbation worths. The validity of the 1 st order approximate methods for the safety analysis of medium sized core like PFBR is already carried out. The same study has been extended for a small metal fuelled fast reactor where perturbation worths from 1 st order and exact perturbation methods has been estimated and compared.

The Integral Fast Reactor (IFR) technology development program has been complemented by an industrial team, led by the General Electric Company, who have developed advanced liquid-metal reactor (ALMR) designs based on the IFR technology. These practical designs illustrate and confirm the potential of this technology to provide passive safety and favorable economics. No serious design or licensing impediments have been identified by the designers, or by the NRC in reviewing these designs.

The cause of collapsology-« study of the collapse of our thermo-industrial society »-is well established. According to the Club of Rome's model, which has proven to be quite accurate when compared to the actual data recorded over the last 30 years, this unavoidable collapse seems impending.  However, one notion is usually put aside : in such a context, what will become of our nuclear plants ?

• The International Atomic Energy Agency (IAEA) is an international organization that seeks to promote the peaceful use of nuclear energy, and to inhibit its use for any military purpose, including nuclear weapons. • The IAEA was established as an autonomous organisation on 29 July 1957. The IAEA has its headquarters in Vienna, Austria. • The IAEA exists to pursue the "safe, secure and peaceful uses of nuclear sciences and technology"

In this article, we argue that scientists and technologists associated with the nuclear industry are building support for small modular reactors (SMRs) by advancing five rhetorical visions imbued with elements of fantasy that cater to various social expectations. The five visions are as follows: a vision of risk-free energy would eliminate catastrophic accidents and meltdowns. A vision of indigenous self-energization would see SMRs empowering remote communities and developing economies. A vision of water security would see SMR-powered desalination plants satisfying the world's water needs. A vision of environmental nirvana would see SMRs providing waste-free and carbon-free electricity to preserve the earth's biosphere. A vision of space exploration would see SMRs assisting in the colonization of the moon, Mars, 1

Nuclear Power Corporation of India Limited (NPCIL) is the organization responsible for site selection,
design, construction, commissioning, operation, maintenance, plant life extension and decommissioning activities of
nuclear power plants in India. Presently, NPCIL has 17 Nuclear Power Plants (NPPs) in operation with a total
installed capacity of 4020 MWe and is constructing 5 NPPs, which will add 2660 MWe. With rich experience in all
relevant fields of nuclear power generation and to meet the emerging regulatory requirements, safety of Indian NPPs
is continuously being reviewed and upgraded. The paper details some of the safety improvements and activities for
the existing NPPs in India like life extension and safety up gradation of BWR TAPS-1&2, retrofitting of
components and Up gradation for old PHWR units and accident management.

The multifunctional backup power system for the internal needs of nuclear power plants uses an added steam turbine. This approach makes it possible to increase the power capacity of NPP with water cooled reactors and at the same time maintain high safety and reliability. The reactor cools down in 72 h in the event of an accident with total blackout of NPP. The significant results of multifunctional backup are: positive economic impact, pay back of the added capital investments in the safety system, and higher technical and economic efficiency, safety, and competitiveness of NPP.

The spectre of Fukushima continues to haunt the world, forcing governments in most parts of the globe to rethink their plans to tap this controversial source of energy. But it is in India that the world’s worst nuclear accident since Chernobyl has had its most serious fallout, with public protests forcing the authorities to delay the commissioning
of the ambitious Kudankulam project by almost a year. Fukushima, however, is just the latest spur for the campaign against the Kudankulam reactors which started in 198. LATHA JISHNU meets the villagers of Tirunelveli district in Tamil Nadu who have been saying no to nuclear energy for 25 years.