Safety analysis of hybrid nuclear desalination plant coupled to High Temperature Gas Cooled Reactor
01 Dec 2010-pp 548-554
TL;DR: In this article, the design of the coupling system of hybrid Multi Effect Desalination-Reverse Osmosis (MED-RO) nuclear desalination plant with HTGR to utilize the waste heat in HTGR is discussed.
Abstract: High Temperature Gas cooled Reactors (HTGRs) are designed to have relatively higher thermal efficiency and enhanced safety & environmental characteristics. It can provide energy for combined production of hydrogen, electricity and other industrial applications. The waste heat available in the HTGR power cycle can also be utilized for desalination of seawater for producing potable water. Desalination is an energy intensive process, so use of waste heat from HTGR certainly makes desalination process more economical. Design of coupling system of desalination plant with HTGR as per the safety design requirement of nuclear desalination plant is very crucial. The paper describes the design of the coupling system of hybrid Multi Effect Desalination-Reverse Osmosis (MED-RO) nuclear desalination plant with HTGR to utilize the waste heat in HTGR is discussed. It also discusses the deterministic safety analysis of the coupling system is presented in detail. The analysis shows that the coupling system meets the acceptance criteria for all the Postulated Initiating Events (PIE's) limited to Design Basis Accident (DBA).
TL;DR: In this paper , the authors present an overview of the technology options suitable for nuclear desalination, their energy consumption, and economic characteristics, emissions profiles, deployment history, and current global interest in such programs.
TL;DR: In this paper, the thermal coupling system analysis of a multi-stage flash desalination plant coupled to Madras Atomic Power Station at Kalpakkam is presented along with technical and safety aspects.
Abstract: When a nuclear reactor is used to supply steam for a desalination plant, the method of coupling has a significant technical and economic impact. The exact method of coupling depends on the type of reactor and the type of desalination plant. As a part of Nuclear Desalination Demonstration Project (NDDP), BARC has successfully commissioned a 4500 m 3 /day multi-stage flash desalination plant coupled to Madras Atomic Power Station at Kalpakkam. A desalination plant coupled to nuclear reactor of pressurised heavy water reactor type is a good example of dual-purpose nuclear desalination plant. This paper presents the thermal coupling system analysis of this plant along with technical and safety aspects.
TL;DR: In this article , the strengths, weaknesses, opportunities, and threats of using nuclear reactor waste heat for desalination in the Arabian Gulf region across four main areas: technical, environmental, socioeconomic, safety, and regulatory.
TL;DR: In this paper, the authors evaluated the desalination costs of a gas turbine-modular helium cooled reactor (GT-MHR) and a pebble bed modular reactor (PBMR) in South Africa.
TL;DR: The He Brayton cycle appears to be the best near-term power conversion method for maximizing the economic potential of fusion power plants as discussed by the authors, but it is not suitable for all applications.
Abstract: The He Brayton cycle appears to be the best near-term power conversion method for maximizing the economic potential of fusion. Key factors affecting the Brayton cycle efficiency includes the turbine inlet temperature, compressor and turbine adiabatic efficiencies, recuperator effectiveness and cycle fractional pressure loss. The compression ratio is also important because for fusion conditions, structural and turbomachinery limitations often prevent use of an optimum value. This paper examines in detail these parameters and proposes near-term values for fusion power plant studies based on existing products and test results, current knowledge, and, if justified, reasonable extrapolation.
TL;DR: In this article, the various types of HTGR gas turbine cycles are concluded as three typical cycles of direct cycle, closed indirect cycle and open indirect cycle, and they are theoretically converted to three Brayton cycles of helium, nitrogen and air.
TL;DR: In this paper, the authors presented the proposed nuclear desalination system utilising MHT purification circuit waste heat of Advanced Heavy Water Reactor (AHWR) along with its coupling arrangement and technical details.
Abstract: The use of thorium for nuclear power generation is an important element of the Indian atomic energy programme. The design and development of the Advanced Heavy Water Reactor (AHWR) is a step in this direction. Intensive design activity is underway to set up a 300-MWe AHWR. The design of the AHWR incorporates several features to simplify the design and to eliminate certain systems and components, making it economically competitive with other available options for power generation. Utilisation of low-grade or waste heat is an additional feature incorporated in the overall design of the reactor system. A proposal to utilise waste heat from the Main Heat Transport (MHT) purification circuit to produce high-quality desalinated water by the low-temperature evaporation process has been envisaged. This paper presents the proposed nuclear desalination system utilising MHT purification circuit waste heat of AHWR along with its coupling arrangement and technical details.
TL;DR: In this article, a case study of the coupling aspects of the MSF desalination plant with the existing nuclear power plant and gives an estimate of the loss of electrical power generation due to extraction of steam.
Abstract: Thermal desalination technologies are very energy intensive. The utilisation of nuclear energy for seawater desalination provides a safe, feasible and economic solution for the production of very good quality water. The Multi-Stage Flash (MSF) desalination plant of the Nuclear Desalination Demonstration Project (NDDP) of the Department of Atomic Energy (DAE), Government of India, is coupled with a nuclear power plant on the south east coast of India to share the common facilities and steam. The MSF desalination plant is under construction. This paper describes a case study of the coupling aspects of the MSF desalination plant with the existing nuclear power plant and gives an estimate of the loss of electrical power generation due to extraction of steam. Loss of electrical power is also compared with the Desalination Economic Evaluation Program (DEEP) of the IAEA.
Related Papers (5)
07 Jul 2014