Design and development of the AHWR—the Indian thorium fuelled innovative nuclear reactor

Sinha, R.K.; Kakodkar, A.

doi:10.1016/j.nucengdes.2005.09.026

Cited by 487 publications

(127 citation statements)

References 2 publications

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“…This limitation is removed in the present approach. A drawback of active step-back mechanism is that it lacks the essential safety feature for power failure in the nuclear power plant and this can be overcome by putting shut-off rods in the reactor to ensure safety, as reported in [18]. In this paper, unlike different controller design for different linearized models in [1], a single robust PI λ D μ controller is proposed, for an active motor driven step-back.…”

Section: Fractional Order Modeling Of a Phwr Undermentioning

confidence: 99%

Fractional Order Modeling of a PHWR Under Step-Back Condition and Control of Its Global Power With a Robust ${\rm PI}^{\lambda} {\rm D} ^{\mu}$ Controller

Das

Gupta

2011

IEEE Trans. Nucl. Sci.

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Abstract-Bulk reduction of reactor power within a small finite time interval under abnormal conditions is referred to as step-back. In this paper, a 500MWe Canadian Deuterium Uranium (CANDU) type Pressurized Heavy Water Reactor (PHWR) is modeled using few variants of Least Square Estimator (LSE) from practical test data under a control rod drop scenario in order to design a control system to achieve a dead-beat response during a stepped reduction of its global power. A new fractional order (FO) model reduction technique is attempted which increases the parametric robustness of the control loop due to lesser modeling error and ensures iso-damped closed loop response with a PI λ D μ or FOPID controller. Such a controller can, therefore, be used to achieve active step-back under varying load conditions for which the system dynamics change significantly. For closed loop active control of the reduced FO reactor models, the PI λ D μ controller is shown to perform better than the classical integer order PID controllers and present operating Reactor Regulating System (RRS) due to its robustness against shift in system parameters.

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Section: Fractional Order Modeling Of a Phwr Undermentioning

confidence: 99%

Fractional Order Modeling of a PHWR Under Step-Back Condition and Control of Its Global Power With a Robust ${\rm PI}^{\lambda} {\rm D} ^{\mu}$ Controller

Das

Gupta

2011

IEEE Trans. Nucl. Sci.

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“…All these have been achieved in the Indian design of AHWR [19][20][21][22][23] which is a heavy water moderated, vertical pressure tube type reactor with natural circulation of boiling light water coolant. It is designed to produce 920 MWt (300 MWe) power.…”

Section: Advanced Heavy Water Reactormentioning

confidence: 99%

Nuclear Power from Thorium:Different Options

2016

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Keywords: Accelerator-driven sub-critical systems, breed and burn reactors, fast reactors, light water reactors, molten salt breeder reactors, pressurized heavy water reactors, thorium fuel cycle.NATURE has provided only one fissile isotope, U 235 , splitting of which in fission chain reaction produces most of the present day nuclear energy. Natural uranium contains 0.7 wt% of U 235 , which is fissile material while the remaining 99.3 wt% U 238 is fertile. In contrast, natural thorium (Th 232 ) is only a fertile material with no fissile content in it. While examining the sustainability of nuclear power, the use of thorium was given due consideration from the early years of the nuclear power generation. In view of the fact that the total inventory of naturally available U 235 is inadequate to provide nuclear energy for a long period (beyond a century or two), the idea of utilizing fertile material by first converting them into fissile and subsequently fissioning them to produce energy was conceived way back in the 1950s. It was also recognized that the fertile to fissile conversion could be made possible only if a steady supply of neutrons can be made economically. The process of nuclear fission produces neutrons in excess of what is required for sustaining the chain reaction and these excess neutrons are utilized for the generation of fresh fissile nuclides. While the fast neutron spectrum fissioning of Pu 239 can generate more fissile nuclides than consumed, U 233 (derived from Th 232 by neutron absorption) can also do the same at a reduced level in a wide neutron energy spectrum from thermal to fast. It is this nuclear property, which was the main incentive of thorium utilization in the early years. Other advantages of the thorium fuel cycle are: reduced generation of higher actinides with long radioactive life and attractive thermo physical properties of ThO 2 (ref. and subsequently fissioning U 233 to produce nuclear energy was demonstrated in several countries, a brief account of which is provided later in this article. However no major power plant has been built with U 233 as the main fuel. This is primarily because driving a thorium-based reactor requires a driver fuel containing any of the fissile nuclides U 235 , U 233 or Pu 239 . The fissile fertile mix U 235 + U 238 in natural and enriched uranium is being used extensively over the last six decades for producing energy and generating fresh fissile nuclides. The capture crosssection of Th 232 is nearly thrice higher than that of U 238 in thermal neutron spectrum, therefore, introduction of thorium will invariably require larger fissile content in

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“…They focuses on various aspects of automation of laboratory based mini-thermal power plant and virtual simulation of same [2]. R.K. Sinha et al (2005) have developed the Stage-3 of nuclear programme in India using thorium based Advanced Heavy Water Reactor (AHWR) working principle and design 3 . Proposed pressurized water reactor simulator block diagram using ni -hardware…”

Section: The Operation Of a Pressurized Watermentioning

confidence: 99%

Design of Pressurized Water Reactor Simulator Using USB NI-6009 Data Acquisition Module

Varthamanan¹,

Sonti²,

Manikandan³

2016

Biosci., Biotech. Res. Asia

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In this work, the pressurized water reactor power model has been simulated using Lab view Data Acquisition module. Energy is the focal point of any investigation at present in the research domain and this work contributes to understand the mechanism and challenges of clean energy generation. The development of GUI for Pressurized Water Reactor is carried out using Labview and the power mode of the control panel was analyzed using test set up. This work and observations are strictly in adherence to only academic standards and is useful only for academic purpose. This work on efficient energy generation is very significant as clean energy is the focal point of any application or contemporary research.

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Design and development of the AHWR—the Indian thorium fuelled innovative nuclear reactor

Cited by 487 publications

References 2 publications

Fractional Order Modeling of a PHWR Under Step-Back Condition and Control of Its Global Power With a Robust ${\rm PI}^{\lambda} {\rm D} ^{\mu}$ Controller

Fractional Order Modeling of a PHWR Under Step-Back Condition and Control of Its Global Power With a Robust ${\rm PI}^{\lambda} {\rm D} ^{\mu}$ Controller

Nuclear Power from Thorium:Different Options

Design of Pressurized Water Reactor Simulator Using USB NI-6009 Data Acquisition Module

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