International Journal of Nuclear Desalination最新文献

{"title":"Nuclear desalination by waste heat utilisation in an advanced heavy water reactor","authors":"A. Adak, I. Rao, V. Srivastava, P. K. Tewari","doi":"10.1504/IJND.2007.013547","DOIUrl":"https://doi.org/10.1504/IJND.2007.013547","url":null,"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.","PeriodicalId":218810,"journal":{"name":"International Journal of Nuclear Desalination","volume":"1 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2007-05-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"128655395","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"IAEA's DEEP in Carlsbad: Co-producing energy and water in Southern California","authors":"G. Rothwell","doi":"10.1504/IJND.2007.013550","DOIUrl":"https://doi.org/10.1504/IJND.2007.013550","url":null,"abstract":"The joint production of energy and desalinated water is examined in the context of the construction of a Reverse Osmosis (RO) plant at the site of the (fossil-fired) Encina Power Station in Carlsbad, California. The first part of the paper reproduces cost estimates of water at the Carlsbad Desalination Project. The second part of the paper reproduces these cost estimates using the International Atomic Energy Agency's Desalination Economic Evaluation Program (DEEP). The paper shows that the cost of desalinating water with nuclear power is cheaper than at fossil-fired plants, given the high cost of fossil fuel. Further, the estimated costs of producing electricity and water with gas reactors and gas turbines are lower than light water reactors with steam turbines. The paper concludes by suggesting that the next step in nuclear desalination in the USA would be to construct an RO plant at an existing light water reactor.","PeriodicalId":218810,"journal":{"name":"International Journal of Nuclear Desalination","volume":"79 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2007-05-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"125691892","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Safety and reliability aspects of seawater reverse osmosis desalination plant of nuclear desalination demonstration project","authors":"S. T. Panicker, P. K. Tewari","doi":"10.1504/IJND.2007.013548","DOIUrl":"https://doi.org/10.1504/IJND.2007.013548","url":null,"abstract":"Desalination systems are mostly based on membrane (RO) and thermal (MSF and MED) processes. High-pressure operation and high level of corrosion are the major aspects of concern in a Seawater Reverse Osmosis (SWRO) Plant. Selection of the appropriate material for construction and the following of the proper design, fabrication and testing codes, and safe operational procedures ensure the safety of the plant. Proper selection of feed seawater source, provision of standby equipment, proper instrumentation and controls, and periodical maintenance improve the reliability. When the desalination plant is integrated into a nuclear power plant, safety measures have to be more stringent, in order to achieve smooth operation and public acceptance. In this paper, the safety and reliability aspects of SWRO desalination plants are discussed in detail, including the case study of an SWRO plant integrated with a nuclear desalination system.","PeriodicalId":218810,"journal":{"name":"International Journal of Nuclear Desalination","volume":"11 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2007-05-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"133352137","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Dynamics of reverse osmosis in a standalone cogenerative nuclear reactor (Part II: load changes)","authors":"A. Karameldin, M. M. Shamloul, M. R. Shaalan, M. Esawy","doi":"10.1504/IJND.2007.013552","DOIUrl":"https://doi.org/10.1504/IJND.2007.013552","url":null,"abstract":"The coupling of desalination units with nuclear power plants has been studied in the present work in this respect, the dynamic behaviour of the pressurised water reactor safety features, represented by the integrity of the fuel cladding, under some transient cases caused by secondary circuit load changes. A cosine-shaped heating through the reactor fuel is taken with its corresponding coolant lumps, to simulate realistic cases encountered in nuclear reactors. As an example, the mathematical model for the Westinghouse 3411 MWth pressurised water reactor, a familiar design with widely published design data was developed. The model consists of two parts; the first one is concerned with the dynamics of the primary side of the reactor; and the second, with the secondary side of the plant. To study the dynamics of the reactor, a 17-lumped parameters model was used. This is a first-order differential equation deduced from the first principles considering six groups of delayed neutrons. A computer program was developed using the Runge-Kutta method to solve these equations and to predict the behaviour of the state variables with time. Two case studies were considered as examples for normal transients. The developed model, which describes the dynamic response of the reactor, primary circuit and secondary circuit, has been analysed and verified with the relevant models. The first case, represented in Part 1 of this study, is concerned with the effect of changes of primary side transient reactivity, including the movement of the reactor control rods. The second one, represented in Part 2 of this study, considers the effect of the secondary side transient reactivity, as the load changes, on the system behaviour. As an example for the secondary side transient, load perturbations, such as load variations in standalone RO desalination units, are selected to study the effect of changing the secondary side conditions on the plant behaviour. The results showed that the reactor components and the fuel matrix should not be affected, and the fuel-cladding integrity is maintained within the safe limits, in all scram cases of RO desalination units coupled with nuclear power plants in the case of either a planned shutdown or an accidental shutdown.","PeriodicalId":218810,"journal":{"name":"International Journal of Nuclear Desalination","volume":"15 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2007-05-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"117202510","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Freezing-melting process and desalination: Review of present status and future prospects","authors":"M. S. Rahman, Mushtaque Ahmed, X. D. Chen","doi":"10.1504/IJND.2007.013549","DOIUrl":"https://doi.org/10.1504/IJND.2007.013549","url":null,"abstract":"The main factors affecting the use of freezing-melting (FM) process are the capital cost and the process complexity. The FM technology was successful when these two factors were compensated by other advantages. The success in food industry was mainly due to its ability of producing high-quality products compared to the available thermal technology in the market. In chemical industry it is generally adopted when there are no other alternatives. It would be difficult to utilise the above advantages to adopt FM process for desalination. Furthermore, misconceptions and negative attitudes also affected the progress of FM process. In desalination, a number of existing technologies are available. The pilot studies in several countries indicated that the hybrid techniques of combining FM process and other desalination methods have high potential for development. The strategies for the commercial success of the FM process in desalination industry are identified in this paper.","PeriodicalId":218810,"journal":{"name":"International Journal of Nuclear Desalination","volume":"24 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2007-05-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"125025743","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Water monitoring as a safety feature for nuclear desalination","authors":"Nestor A. Masriera, A. Doval, M. D. Tada","doi":"10.1504/IJND.2006.009504","DOIUrl":"https://doi.org/10.1504/IJND.2006.009504","url":null,"abstract":"It is widely accepted that the general safety approach for nuclear facilities is valid for a Nuclear Desalination Plant (NDP), thus IAEA standards and guides are applicable. The coupling of a NDP should be designed with the safety objective of ensuring that it results in no adverse effect on the Nuclear Power Plant (NPP) safety. The first objective (provisions of barriers) is complied with by the known NDP design, so the relevant issue becomes the design features preventing the transfer of radioactive material to the product water, even in the event of system failures. This presentation drafts a coupling-system safety assessment, from fundamentals and general requirements down to specific design requirements. The state of the art of monitoring systems imposes constraints on the coupling design, in terms of hold-up capability and piping interconnection. This conceptual design shows the system's complexity implied in having monitoring of product water as a safety feature, and conclusions are extremely relevant when drafting general user requirements for a NDP project.","PeriodicalId":218810,"journal":{"name":"International Journal of Nuclear Desalination","volume":"19 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2006-04-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"121639825","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Optimisation of the coupling of nuclear reactors and desalination systems in Morocco","authors":"M. Tabet, Abderrahim Htet, A. Alami","doi":"10.1504/IJND.2006.009501","DOIUrl":"https://doi.org/10.1504/IJND.2006.009501","url":null,"abstract":"This study has been undertaken in the framework of IAEA CRP on 'Optimisation of the Coupling of Nuclear Reactors and Desalination Systems in Morocco'. Two sites have been selected to host nuclear desalination plants, and different combinations with nuclear reactors have been investigated. Other combinations with fossil fuel plants have been examined for comparison. The results obtained showed the competitiveness of nuclear energy, which could be a solution to supply the region that will suffer from water shortage. On the other hand, this study could help the decision makers in the management and planning of water, energy resources and supply.","PeriodicalId":218810,"journal":{"name":"International Journal of Nuclear Desalination","volume":"14 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2006-04-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"114871814","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Comparative analysis of the thin-film desalination plant process","authors":"V. Slesarenko","doi":"10.1504/IJND.2006.009502","DOIUrl":"https://doi.org/10.1504/IJND.2006.009502","url":null,"abstract":"Thin-film installations with different heating surface orientations are widely used in seawater technology. Despite the presence of various thermal schemes and the construction of evaporating devices for installations of this type, comparisons of their power output are not available. We have carried out a comparison of the thermal schemes of MSF and thin-film installations in order to determine the latter's effectiveness. We analysed the intensification of heat transfer by thin-film installations with seawater moving along the heating surface in the form of vertical film descending and ascending two-phase flow and horizontal film flow. Analysis was carried out on basis of many of our own researches and data received by other authors.","PeriodicalId":218810,"journal":{"name":"International Journal of Nuclear Desalination","volume":"44 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2006-04-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"115835975","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Optimum thermal coupling system for co-generation nuclear desalination plants","authors":"M. Saadawy","doi":"10.1504/IJND.2006.009503","DOIUrl":"https://doi.org/10.1504/IJND.2006.009503","url":null,"abstract":"Owing to the small number of established nuclear desalination plants worldwide, there is a lack of technical data and not enough practical experience in the field of coupling systems. Therefore, in this study different coupling technologies concerning co-generation systems for linking nuclear power reactors to large thermal seawater desalination units (MED and MSF) are reviewed and optimised. Owing to the attractive and advantageous features of heat pipes, new heat-pipe heat exchangers are proposed for the Intermediate Isolating Loop (IIL), in addition to the previously reviewed types: flash steam chamber and pressurised water loops. All the studied thermal coupling methods are modelled mathematically as heat exchanger loop transfers for the safe transfer of heat energy from nuclear power plant to desalination plant. A methodology for selecting the optimum coupling system is derived, taking into consideration several preference indices, which mainly depend on IIL characteristics: heat transfer surface area, thermal performance and consumed pumping power. As an exploratory case study, these factors are analysed and discussed for the SMART reactor type.","PeriodicalId":218810,"journal":{"name":"International Journal of Nuclear Desalination","volume":"2 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2006-04-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"133779957","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Desalination and water recovery: control of membrane fouling","authors":"A. Reddy, D. Mohan, P. R. Buch, S. Joshi, P. Ghosh","doi":"10.1504/IJND.2006.009509","DOIUrl":"https://doi.org/10.1504/IJND.2006.009509","url":null,"abstract":"Ultrafiltration (UF), Nanofiltration (NF) and Reverse Osmosis (RO) technologies are widely used for the production of safe drinking water, and for the recovery of reusable water from various industrial effluent streams. The most commonly encountered phenomenon in these processes, especially in water recovery application, is membrane fouling, and control of membrane fouling is regarded as a significant challenge. Membranes with charged and hydrophilic surfaces are reported to be less susceptible to fouling and often reversible. UF/RO membranes containing negatively charged and/or neutral hydrophilic functional groups on the surface were prepared by surface modification of suitable membranes. The surface modified membranes exhibited separations of 68%–85% for Na2SO4, 19%–31% for MgSO4, 10%–26% for NaCl and 2%–12% for CaCl2 with water permeation rates of 9–50 l/m²-h at the operating pressure of 4 kg/cm². The UF membranes were tested for water recovery from reactive dye effluents containing solutes with molecular sizes in the range of 600–1000 Da along with inorganic solutes. Surface-modified RO membranes were utilised for desalination of brackish water.","PeriodicalId":218810,"journal":{"name":"International Journal of Nuclear Desalination","volume":"2 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2006-04-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"127436297","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}