Anil Kakodkar - Academia.edu (original) (raw)

Papers by Anil Kakodkar

Nuclear engineering and design, 2006

India has chalked out a nuclear power program based on its domestic resource position of uranium ... more India has chalked out a nuclear power program based on its domestic resource position of uranium and thorium. The first stage started with setting up the Pressurized Heavy Water Reactors (PHWR) based on natural uranium and pressure tube technology. In the second phase, the fissile material base will be multiplied in Fast Breeder Reactors using the plutonium obtained from the PHWRs. Considering the large thorium reserves in India, the future nuclear power program will be based on thorium-233 U fuel cycle. However, there is a need for the timely development of thorium-based technologies for the entire fuel cycle. The Advanced Heavy Water Reactor (AHWR) has been designed to fulfill this need. The AHWR is a 300 MW e , vertical, pressure tube type, heavy water moderated, boiling light water cooled natural circulation reactor. The fuel consists of (Th-Pu)O 2 and (Th-233 U)O 2 pins. The fuel cluster is designed to generate maximum energy out of 233 U, which is bred in situ from thorium and has a slightly negative void coefficient of reactivity. For the AHWR, the well-proven pressure tube technology has been adopted and many passive safety features, consistent with the international trend, have been incorporated. A distinguishing feature which makes this reactor unique, from other conventional nuclear power reactors is the fact that it is designed to remove core heat by natural circulation, under normal operating conditions, eliminating the need of pumps. In addition to this passive feature, several innovative passive safety systems have been incorporated in the design, for decay heat removal under shut down condition and mitigation of postulated accident conditions. The design of the reactor has progressively undergone modifications and improvements based on the feedbacks from the analytical and the experimental R&D. This paper gives the details of the current design of the AHWR.

Phenomenology of Baneberry Nuclear Event Revisited with 3-D Finite Element Transient Simulation

Nuclear Technology

... RANJAN Rajeev (1) ; SINGH RK (1) ; SIKKA SK (1) ; KAKODKAR Anil (1) ; ... paper highlights a ... more ... RANJAN Rajeev (1) ; SINGH RK (1) ; SIKKA SK (1) ; KAKODKAR Anil (1) ; ... paper highlights a three-dimensional (3-D) transient numerical simulation of the Baneberry event of December 18, 1970, with a 10-kT yield and a 278-m source depth, conducted at the Nevada Test Site. ...

Current Science, 2017

The objective of rapid development of rural population in a sustainable manner with a view to bri... more The objective of rapid development of rural population in a sustainable manner with a view to bridging the urban-rural divide would require leveraging knowledge and technology in an environment conducive for innovation. The concept of a CILLAGE that incorporates the best of a city in a village is developed with this objective in mind. A CILLAGE is a knowledge-based ecosystem for integrated education, research, technology development and deployment as well as capacity building in rural areas. The focus of research work at a CILLAGE is on regional problems. CILLAGE activities also include a comprehensive engagement with people in the neighbourhood for demonstration and deployment of relevant technologies through a number of Advanced Knowledge-based Rural Technology Initiative (AKRUTI) centres located in the neighbourhood. CILLAGE should thus become a centre of innovation in rural areas to solve the problems of the region and disseminate the developed technologies in the region through AKRUTI centres. This article discusses the philosophy of the CILLAGE concept and describes its implementation through an example.

Towards Sustainable, Secure, and Safe Energy Future: Leveraging Opportunities with Thorium

Thorium Energy for the World, 2016

Low Carbon Pathways for India and the World

Energy Engineering, 2016

Managing nuclear knowledge: a governmental perspective

International Journal of Nuclear Knowledge Management, 2004

This paper reviews the seismic analysis of the close-in, regional and teleseismic data correspond... more This paper reviews the seismic analysis of the close-in, regional and teleseismic data corresponding to May 1998 Indian nuclear tests. Strong Lg and Rayleigh waves (period 3.5-7 s) were observed at several in- country stations from the two large explosions of 11 May 1998 (POK2). The magnitude of POK2 based on regional Lg wave data was obtained as 5.47 ±

Sadhana, 2014

Seismic signals due to any underground nuclear explosion events are known to be influenced by the... more Seismic signals due to any underground nuclear explosion events are known to be influenced by the local geology of the test site and the yield level. In this paper, transient three-dimensional finite element code SHOCK-3D developed for the simulation of underground nuclear explosion events has been used to obtain synthetic acceleration signals for Baneberry site (Nevada) single and composite rock media. At this site an underground nuclear test of 10 kT conducted on 18th December 1970 at source depth of 278 m resulted into venting as reported by Terhune et al with 2D simulation results and later by us through 3D simulation in Ranjan et al. First, the reasons of the venting for this event are summarized. After the successful validation of the 3D numerical model for Baneberry site rock media, parametric studies are carried out for 1 and 8 kT yields at 100 m depth (Scaled Depths of Burst SDOB ∼ 100 and 50 m/kT 1/3 , respectively) for homogeneous and composite Paleozoic and Tuff media of Baneberry site. It is demonstrated that the near source local geological formations and associated nonlinear effects significantly influence the seismic signals. With this study the seismic decoupling of the source by an order of magnitude has been illustrated. Finally, it is concluded that the seismic signals alone, in the absence of in-depth information of the local geology of the specific test site, are not appropriate measures of the source strength.

Integrated safety assessment of Indian nuclear power plants for extreme events: Reducing impact on public mind

Sadhana, 2013

ABSTRACT Nuclear energy professionals need to understand and address the catastrophe syndrome tha... more ABSTRACT Nuclear energy professionals need to understand and address the catastrophe syndrome that of late seems to be increasingly at work in public mind in the context of nuclear energy. Classically the nuclear power reactor design and system evolution has been based on the logic of minimization of risk to an acceptable level and its quantification based on a deterministic approach and backed up by a further assessment based on the probabilistic methodology. However, in spite of minimization of risk, the reasons for anxiety and trauma in public mind that still prevails in the context of severe accidents needs to be understood and addressed. Margins between maximum credible accidents factored in the design and the ultimate load withstanding capacities of relevant systems need to be enhanced and guaranteed with a view to minimize release of radioactivity and avoid serious impact in public domain. A more realistic basis for management of an accident in public domain also needs to be quantified for this purpose. Assurance to public on limiting the consequences to a level that does not lead to a trauma is something that we need to be able to credibly demonstrate and confirm. The findings from Chernobyl reports point to significant psychological effects and related health disorders due to large scale emergency relocation of people that could have been possibly reduced by an order of magnitude without significant additional safety detriment. A combination of probabilistic and deterministic approaches should be evolved further to minimize consequences in public domain through enhancing safety margins and adding greater precision to quantitatively predicting accident progression and its management. The paper presents the case studies of the extreme external event such as tsunami and its impact on the coastal nuclear plants in India, the containment integrity assessment under the extreme internal event of over-pressurization and aircraft impact along with hydrogen deflagration/detonation-induced loadings. These are at the moment extremely burning issues due to the severe accidents of Fukushima, Chernobyl and Three Mile Island reactors. In the present day context identifying the extreme loadings in a separate category and the corresponding margin assessment is necessary in addition to 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.

Three-dimensional transient numerical simulation of cou- pled gas cavity and geological medium pr... more Three-dimensional transient numerical simulation of cou- pled gas cavity and geological medium problem resulting from underground nuclear explosion events is co m- plex due to the gas cavity growth, resulting into the large deformations and large strains of the geological medium and shock-induced high strain-rate dependence of the response. However, it is important to establish the effects of local inelastic and nonlinear behaviour due to crushing and cracking of the geological medium, on the shock-waves near the source and the seismic signals beyond the elastic radius. This study also helps simulate the shock-wave reflection effects from the free surface near the ground zero, mound growth, spall near the free surface and the subsequent free fall of the mound due to gravity effect resulting in crater formation. The impacting spalled rock layers give rise to secondary seismic signals in addition to the primary signals that are observed in the near field which in turn are known to inf...

Diagnosis and cure of Dhruva fuel vibration

Nuclear Engineering and Design, 1991

... and Design 125 (1991) 259266 NorthHolland 259 Diagnosis and cure of Dhruva fuel vibration RIK... more ... and Design 125 (1991) 259266 NorthHolland 259 Diagnosis and cure of Dhruva fuel vibration RIK Moorthy, A. Rama Rao and Anil Kakodkar Reactor ... In order to prove such a postulate, the outofpile flow test facility was excited externally with an elec trodynamic shaker. ...

Evolution of nuclear reactor containments in India: Addressing the present day challenges

Nuclear Engineering and Design, 2014

Post Shot Radioactivity Measurements on Samples Extracted from Thermonuclear Test Site

Annals of Nuclear Energy, 1993

The safety requirement of two shutdown systems functioning on diverse principles has led to the i... more The safety requirement of two shutdown systems functioning on diverse principles has led to the introduction of a secondary shutdown system which functions by injecting liquid neutron poison jets at high pressure into the bulk moderator. The poison enters the moderator in the form of high-speed jets, in which the cross-section increases and the poison concentration falls as the jet develops. A formalism has been developed for estimating the reactivity worth of these jets. This formalism is different from currently used formalisms, in which the conical jet is approximated by equivalent cylinders whose radius changes from cell to cell. In the formalism presented in this paper, both the cross-section of the jet and the concentration of the poison are taken to be continuously varying from the origin of the jet to the end of the jet where it starts diffusing into the moderator. The formalism has been used to calculate the reactivity worth of the secondary shutdown system of the 500 MW(e) PHWR, making use of jet growth data that have been made available from experiments performed in our laboratory.

Annals of Nuclear Energy, 1994

When attempting initial power flattening with thorium bundles, the placement of the bundles shoul... more When attempting initial power flattening with thorium bundles, the placement of the bundles should take into account not only the need for power flattening, but also the fact that sharp flux depressions caused by the presence of thorium can alter the reactivity worth of shutdown systems. Since the safety assessment of the reactor is made under the assumption of certain shutdown worths, it is important that these worths are not disturbed by the fuel loading. We describe here a method by which this problem is tackled. The thorium loading that was worked out using this method was found to satisfy all the desired criteria of full power, and no loss of worth of the two independent shutdown sysems. This loading has been used in the Indian PHWR at Kakrapar, the KAPS-I, which went critical on

Academy Proceedings in Engineering Sciences

ias.ac.in

Academy Proceedings in Engineering Sciences S¯adhan¯a ... Editor Deshpande SM Jawaharlal Nehru Ce... more Academy Proceedings in Engineering Sciences S¯adhan¯a ... Editor Deshpande SM Jawaharlal Nehru Centre for Advanced Scientific Research, Bangalore Associate Editors Anand GV Anurag Kumar Indian Institute of Science, Bangalore Indian Institute of Science, Bangalore Narsimha Murty M Natarajan KA Indian Institute of Science, Bangalore Indian Institute of Science, Bangalore Editorial Board Arakeri JH ... Indian Institute of Science, Bangalore Editor of Publications Mukunda N Indian Institute of Science, Bangalore Editorial Office ... Indian Academy of Sciences, ...

Nuclear Engineering and Design, 1995

It has now been realised that the garter springs which maintain the gap between the pressure tube... more It has now been realised that the garter springs which maintain the gap between the pressure tube (PT) and calandria tube (CT) of a PHWR can get displaced significantly from their deign position in many channels. It has also been recognised that the large unsupported span of the PT restricts the life of the channel due to premature contact of