Pub Date : 2005-05-04DOI: 10.1504/IJND.2005.007011
D. Nicholls
The Pebble Bed Modular Reactor (PBMR) is a development lead by Eskom, the South African state power utility. The technology used is based on the previous German HTGR work linked to a direct cycle gas turbine (or Breyton Cycle) being developed in conjunction with Mitsubishi Heavy Industry. The initial commercial plant design has a thermal output of 400 MW with an electrical output (nett) of over 165 MW. The interesting feature of desalination is that the nature of the inter-cooled closed cycle is the rejection of waste heat (about 200 MW) at temperatures of up to 120°C to cooling water circuits. The options that could be considered include a reverse osmosis plant using a sea water inlet temp of 25°C with an outlet from the reactor's coolers of 40°C. This would result in a power consumption of some 14 MW from the reactor with a water production of 78,000 m³/day per reactor. If the evaporative approach is to be used, the current design can yield 400kg/s of water @ 102°C, or (with minor modifications to the coolers and some increased limits on the operating flexibility of the reactor) 342 kg/s @ 115°C. In both these last two cases, there would be no reduction in the electrical power dispatched to the grid. The advantages of such a system to desalination applications are several. The size of the reactor means that even in reasonably small electrical grids (as small as 1000 MW total) a number of PBMRs could be grouped together. This would avoid the problem of backing up the desalination system with a fossil fuel source when the reactor is in maintenance. An effective installation could be four PBMRs linked through a common cooling water system to two desalination plants (each to be supported by one reactor). Since the PBMR uses on-load fuelling systems, the plant does not have the problem of short operating cycles (12–18 months) but can operate for six years between 30-day maintenance periods. It is also designed, due to the inherent safety features of small HTGRs, to be operated with a far smaller nuclear infrastructure, using extensive turnkey vendor support (as with current gas fired power stations). These features make the PBMR far more suitable for developing countries, where the application of existing nuclear designs (e.g. a. 1000 MW PWR) would be problematic.
{"title":"The pebble bed modular reactor, desalination challenges and options","authors":"D. Nicholls","doi":"10.1504/IJND.2005.007011","DOIUrl":"https://doi.org/10.1504/IJND.2005.007011","url":null,"abstract":"The Pebble Bed Modular Reactor (PBMR) is a development lead by Eskom, the South African state power utility. The technology used is based on the previous German HTGR work linked to a direct cycle gas turbine (or Breyton Cycle) being developed in conjunction with Mitsubishi Heavy Industry. The initial commercial plant design has a thermal output of 400 MW with an electrical output (nett) of over 165 MW. The interesting feature of desalination is that the nature of the inter-cooled closed cycle is the rejection of waste heat (about 200 MW) at temperatures of up to 120°C to cooling water circuits. The options that could be considered include a reverse osmosis plant using a sea water inlet temp of 25°C with an outlet from the reactor's coolers of 40°C. This would result in a power consumption of some 14 MW from the reactor with a water production of 78,000 m³/day per reactor. If the evaporative approach is to be used, the current design can yield 400kg/s of water @ 102°C, or (with minor modifications to the coolers and some increased limits on the operating flexibility of the reactor) 342 kg/s @ 115°C. In both these last two cases, there would be no reduction in the electrical power dispatched to the grid. The advantages of such a system to desalination applications are several. The size of the reactor means that even in reasonably small electrical grids (as small as 1000 MW total) a number of PBMRs could be grouped together. This would avoid the problem of backing up the desalination system with a fossil fuel source when the reactor is in maintenance. An effective installation could be four PBMRs linked through a common cooling water system to two desalination plants (each to be supported by one reactor). Since the PBMR uses on-load fuelling systems, the plant does not have the problem of short operating cycles (12–18 months) but can operate for six years between 30-day maintenance periods. It is also designed, due to the inherent safety features of small HTGRs, to be operated with a far smaller nuclear infrastructure, using extensive turnkey vendor support (as with current gas fired power stations). These features make the PBMR far more suitable for developing countries, where the application of existing nuclear designs (e.g. a. 1000 MW PWR) would be problematic.","PeriodicalId":218810,"journal":{"name":"International Journal of Nuclear Desalination","volume":"44 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2005-05-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"131284881","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}
Pub Date : 2005-05-04DOI: 10.1504/IJND.2005.007014
Ü. Çolak
Of late, high temperature gas cooled reactors have received significant attention due to many desirable operational and safety characteristics. Potable water has become more and more scarce due to the increasing population and environmental problems. Seawater desalination is an important consideration when searching for a supply of potable and industrial water. This study deals with possible coupling schemes for desalination and gas cooled reactors. A number of possible combinations are taken into account. Economical analysis and performance data obtained by DEEP (Desalination Economic Evaluation Program) for these alternatives are compared. Desalination with energy obtained by fossil fuel fired power plants is also considered.
{"title":"Coupling strategies for desalination plants with gas cooled reactors","authors":"Ü. Çolak","doi":"10.1504/IJND.2005.007014","DOIUrl":"https://doi.org/10.1504/IJND.2005.007014","url":null,"abstract":"Of late, high temperature gas cooled reactors have received significant attention due to many desirable operational and safety characteristics. Potable water has become more and more scarce due to the increasing population and environmental problems. Seawater desalination is an important consideration when searching for a supply of potable and industrial water. This study deals with possible coupling schemes for desalination and gas cooled reactors. A number of possible combinations are taken into account. Economical analysis and performance data obtained by DEEP (Desalination Economic Evaluation Program) for these alternatives are compared. Desalination with energy obtained by fossil fuel fired power plants is also considered.","PeriodicalId":218810,"journal":{"name":"International Journal of Nuclear Desalination","volume":"8 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2005-05-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"128779305","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}
Pub Date : 2005-05-04DOI: 10.1504/IJND.2005.007016
M. Metaiche, A. Kettab
The subject of the present article is the technical simulation of seawater desalination, by a one stage reverse osmosis system, the objectives of which are the recent valuation of cost price through the use of new membrane and permeator performances, the use of new means of simulation and modelling of desalination parameters, and show the main parameters influencing the cost price. We have taken as the simulation example the Seawater Desalting centre of Djannet (Boumerdes, Algeria). The present performances allow water desalting at a price of 0.5 $/m 3 , which is an interesting and promising price, corresponding with the very acceptable water product quality, in the order of 269 ppm. It is important to run the desalting systems by reverse osmosis under high pressure, resulting in further decrease of the desalting cost and the production of good quality water. Aberration in choice of functioning conditions produces high prices and unacceptable quality. However there exists the possibility of decreasing the price by decreasing the requirement on the product quality. The seawater temperature has an effect on the cost price and quality. The installation of big desalting centres, contributes to the decrease in prices. A very important, long and tedious calculation is effected, which is impossible to conduct without programming and informatics tools. The use of the simulation model has been much efficient in the design of desalination centres that can perform at very improved prices.
{"title":"Water desalination price from recent performances: modelling, simulation and analysis","authors":"M. Metaiche, A. Kettab","doi":"10.1504/IJND.2005.007016","DOIUrl":"https://doi.org/10.1504/IJND.2005.007016","url":null,"abstract":"The subject of the present article is the technical simulation of seawater desalination, by a one stage reverse osmosis system, the objectives of which are the recent valuation of cost price through the use of new membrane and permeator performances, the use of new means of simulation and modelling of desalination parameters, and show the main parameters influencing the cost price. We have taken as the simulation example the Seawater Desalting centre of Djannet (Boumerdes, Algeria). The present performances allow water desalting at a price of 0.5 $/m 3 , which is an interesting and promising price, corresponding with the very acceptable water product quality, in the order of 269 ppm. It is important to run the desalting systems by reverse osmosis under high pressure, resulting in further decrease of the desalting cost and the production of good quality water. Aberration in choice of functioning conditions produces high prices and unacceptable quality. However there exists the possibility of decreasing the price by decreasing the requirement on the product quality. The seawater temperature has an effect on the cost price and quality. The installation of big desalting centres, contributes to the decrease in prices. A very important, long and tedious calculation is effected, which is impossible to conduct without programming and informatics tools. The use of the simulation model has been much efficient in the design of desalination centres that can perform at very improved prices.","PeriodicalId":218810,"journal":{"name":"International Journal of Nuclear Desalination","volume":"1 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2005-05-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"129888579","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}
Pub Date : 2004-10-04DOI: 10.1504/IJND.2004.005441
K. Zverev, Y. Baranaev, G. Toshinsky, V. Polunichev, A. Romenkov, V. Shamanin, V. L. Podberezny
In the document "Strategy of Nuclear Power Development in Russia for the First Half of XXI Century" approved by the Government of the RF, seawater desalination is considered as a prospective area of application of the small-sized nuclear power plants (SNPP). Taking into account vast water resources of Russia evenly distributed over the territory of the country, seawater desalination is not a vital domestic demand for this country. Therefore, the R&D activities of the RF MINATOM institutions on nuclear desalination are aimed mainly at the assessment of implementation of the SNPP based nuclear desalination system in the developing countries suffering from the lack of fresh water supply. Within these activities, analysis of engineering and economical problems related to optimisation of the use of different type nuclear reactors as a source of electricity and heat for seawater desalination plants has been performed. The objective of the work is to develop scientific and technological basis for comprehensive design studies required for practical implementation of the projects.
{"title":"Status and prospect of R&D aimed at application of nuclear reactors for seawater desalination in Russia","authors":"K. Zverev, Y. Baranaev, G. Toshinsky, V. Polunichev, A. Romenkov, V. Shamanin, V. L. Podberezny","doi":"10.1504/IJND.2004.005441","DOIUrl":"https://doi.org/10.1504/IJND.2004.005441","url":null,"abstract":"In the document \"Strategy of Nuclear Power Development in Russia for the First Half of XXI Century\" approved by the Government of the RF, seawater desalination is considered as a prospective area of application of the small-sized nuclear power plants (SNPP). Taking into account vast water resources of Russia evenly distributed over the territory of the country, seawater desalination is not a vital domestic demand for this country. Therefore, the R&D activities of the RF MINATOM institutions on nuclear desalination are aimed mainly at the assessment of implementation of the SNPP based nuclear desalination system in the developing countries suffering from the lack of fresh water supply. Within these activities, analysis of engineering and economical problems related to optimisation of the use of different type nuclear reactors as a source of electricity and heat for seawater desalination plants has been performed. The objective of the work is to develop scientific and technological basis for comprehensive design studies required for practical implementation of the projects.","PeriodicalId":218810,"journal":{"name":"International Journal of Nuclear Desalination","volume":"127 8 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2004-10-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"124241637","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}
Pub Date : 2004-10-04DOI: 10.1504/ijnd.2004.005446
Y. Kuznetzov, A. Romenkov, Y. A. Mishanina
RDIPE has developed a detailed design of an enhanced safety nuclear steam supply system (NSSS) with a VK-300 boiling water reactor for combined heat and power generation. The thermal power of the reactor is 750 MW. The maximum electrical power in the condensation mode is 250 MWe. The maximum heat generation capacity of 400 Gcal/h is reached at 150 MWe. This report describes, in brief, the basic technical concepts for the VK-300 NSSS and the power unit, with an emphasis on enhanced safety and good economic performance. With relatively small power, good technical and economic performance of the VK-300 reactor that is a base for the desalination complex is attained through: reduced capital costs of the nuclear plant construction thanks to technical approaches ensuring maximum simplicity of the reactor design and the NSSS layout; a single-circuit power unit configuration (reactor-turbine) excluding expensive equipment with a lot of metal, less pipelines and valves; reduced construction costs of the basic buildings thanks to reduced construction volumes due to rational arrangement concepts; higher reliability of equipment and reduced maintenance and repair costs; longer reactor design service life of up to 60 years; selection of the best reactor and desalination equipment interface pattern. The report considers the potential application of the VK-300 reactor as a source of energy for distillation desalination units. The heat from the reactor is transferred to the desalination unit via an intermediate circuit. Comparison is made between variants of the reactor integration with desalination units of the following types: multi-stage flash (MSF technology); multi-effect distillation horizontal-tube film units of the DOU GTPA type (MED technology). The NDC capacity with the VK-300 reactor, in terms of distillate, will be more than 200,000 m³/day, with the simultaneous output of electric power from the turbine generator buses of around 150 MWe. The variants of the desalination technologies applied are compared, based on economic estimates performed. Acceptable values of the distillate cost have been obtained.
{"title":"A nuclear desalination complex with a VK-300 boiling type reactor facility","authors":"Y. Kuznetzov, A. Romenkov, Y. A. Mishanina","doi":"10.1504/ijnd.2004.005446","DOIUrl":"https://doi.org/10.1504/ijnd.2004.005446","url":null,"abstract":"RDIPE has developed a detailed design of an enhanced safety nuclear steam supply system (NSSS) with a VK-300 boiling water reactor for combined heat and power generation. The thermal power of the reactor is 750 MW. The maximum electrical power in the condensation mode is 250 MWe. The maximum heat generation capacity of 400 Gcal/h is reached at 150 MWe. This report describes, in brief, the basic technical concepts for the VK-300 NSSS and the power unit, with an emphasis on enhanced safety and good economic performance. With relatively small power, good technical and economic performance of the VK-300 reactor that is a base for the desalination complex is attained through: reduced capital costs of the nuclear plant construction thanks to technical approaches ensuring maximum simplicity of the reactor design and the NSSS layout; a single-circuit power unit configuration (reactor-turbine) excluding expensive equipment with a lot of metal, less pipelines and valves; reduced construction costs of the basic buildings thanks to reduced construction volumes due to rational arrangement concepts; higher reliability of equipment and reduced maintenance and repair costs; longer reactor design service life of up to 60 years; selection of the best reactor and desalination equipment interface pattern. The report considers the potential application of the VK-300 reactor as a source of energy for distillation desalination units. The heat from the reactor is transferred to the desalination unit via an intermediate circuit. Comparison is made between variants of the reactor integration with desalination units of the following types: multi-stage flash (MSF technology); multi-effect distillation horizontal-tube film units of the DOU GTPA type (MED technology). The NDC capacity with the VK-300 reactor, in terms of distillate, will be more than 200,000 m³/day, with the simultaneous output of electric power from the turbine generator buses of around 150 MWe. The variants of the desalination technologies applied are compared, based on economic estimates performed. Acceptable values of the distillate cost have been obtained.","PeriodicalId":218810,"journal":{"name":"International Journal of Nuclear Desalination","volume":"35 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2004-10-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"131956302","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}
Pub Date : 2004-10-04DOI: 10.1504/IJND.2004.005443
S. Nisan, S. Dardour, Y. Dumont, N. Reguigui
This paper summarises our on-going investigations on the elaboration of a strategy for the possible application of nuclear energy for seawater desalination in a North African country such as Tunisia. The basic aim of the work undertaken is to estimate the realistic costs (under Tunisian conditions) of an integrated nuclear desalination system, operating in the co-generation mode at a specific site in Tunisia, la Skhira, situated between the towns of Sfax and Gabes. However, in order to furnish a choice of technical options, our investigations include studies with two nuclear reactors: the first an existing reactor, the PWR-900 as a reference base case and the second a new generation safe integral reactor, SCOR-600). These reactors were coupled to three desalination processes: the Multiple Effect Distillation, (MED); the Reverse Osmosis process (RO) and an advanced Reverse Osmosis process, (Roph), based on the utilisation of waste heat. Comparisons have also been made with two fossil energy based systems, currently being used in Tunisia: the oil fired plant (DP) and the gas turbine combined cycle plant (CC). First results indicate that desalination by nuclear options is not only technically feasible but also the least expensive solution for the la Skhira site in Tunisia.
{"title":"Inter-regional collaborative nuclear desalination studies by France and Tunisia; the TUNDESAL project","authors":"S. Nisan, S. Dardour, Y. Dumont, N. Reguigui","doi":"10.1504/IJND.2004.005443","DOIUrl":"https://doi.org/10.1504/IJND.2004.005443","url":null,"abstract":"This paper summarises our on-going investigations on the elaboration of a strategy for the possible application of nuclear energy for seawater desalination in a North African country such as Tunisia. The basic aim of the work undertaken is to estimate the realistic costs (under Tunisian conditions) of an integrated nuclear desalination system, operating in the co-generation mode at a specific site in Tunisia, la Skhira, situated between the towns of Sfax and Gabes. However, in order to furnish a choice of technical options, our investigations include studies with two nuclear reactors: the first an existing reactor, the PWR-900 as a reference base case and the second a new generation safe integral reactor, SCOR-600). These reactors were coupled to three desalination processes: the Multiple Effect Distillation, (MED); the Reverse Osmosis process (RO) and an advanced Reverse Osmosis process, (Roph), based on the utilisation of waste heat. Comparisons have also been made with two fossil energy based systems, currently being used in Tunisia: the oil fired plant (DP) and the gas turbine combined cycle plant (CC). First results indicate that desalination by nuclear options is not only technically feasible but also the least expensive solution for the la Skhira site in Tunisia.","PeriodicalId":218810,"journal":{"name":"International Journal of Nuclear Desalination","volume":"42 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2004-10-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"128683341","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}
Pub Date : 2004-10-04DOI: 10.1504/IJND.2004.005442
S. Nisan, L. Volpi
Detailed analysis has shown several discrepancies and pitfalls of coupling an economic evaluation code, such as SEMER to the desalination cost evaluation code DEEP. This paper resumes our findings, which may be of interest to other DEEP users. The paper in particular deals with the following issues: why is it that power costs from nuclear systems are systematically higher in DEEP than those given by the economic evaluations made by individual organisations, (in our case, the SEMER code for example), even when the calculated construction costs are input into DEEP? Why corresponding power costs for fossil energy systems are lower? Why in particular desalination costs from Gas-Turbine Combined Cycle power system, which is now considered to be the cheapest fossil fuel option, are higher than desalination costs by Pulverised Coal system? Why DEEP calculation results with the backup heat source are 40% higher than those without the backup heat source?
{"title":"Evaluation of desalination costs with DEEP","authors":"S. Nisan, L. Volpi","doi":"10.1504/IJND.2004.005442","DOIUrl":"https://doi.org/10.1504/IJND.2004.005442","url":null,"abstract":"Detailed analysis has shown several discrepancies and pitfalls of coupling an economic evaluation code, such as SEMER to the desalination cost evaluation code DEEP. This paper resumes our findings, which may be of interest to other DEEP users. The paper in particular deals with the following issues: why is it that power costs from nuclear systems are systematically higher in DEEP than those given by the economic evaluations made by individual organisations, (in our case, the SEMER code for example), even when the calculated construction costs are input into DEEP? Why corresponding power costs for fossil energy systems are lower? Why in particular desalination costs from Gas-Turbine Combined Cycle power system, which is now considered to be the cheapest fossil fuel option, are higher than desalination costs by Pulverised Coal system? Why DEEP calculation results with the backup heat source are 40% higher than those without the backup heat source?","PeriodicalId":218810,"journal":{"name":"International Journal of Nuclear Desalination","volume":"10 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2004-10-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"123763855","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}
Pub Date : 2004-10-04DOI: 10.1504/IJND.2004.005447
A. Adak, P. K. Tewari
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.
{"title":"Coupling aspects of an MSF desalination plant and loss of electrical power generation of a nuclear power plant: case study","authors":"A. Adak, P. K. Tewari","doi":"10.1504/IJND.2004.005447","DOIUrl":"https://doi.org/10.1504/IJND.2004.005447","url":null,"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.","PeriodicalId":218810,"journal":{"name":"International Journal of Nuclear Desalination","volume":"35 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2004-10-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"127750708","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}
Pub Date : 1900-01-01DOI: 10.1504/IJND.2004.003673
A. Doval, Nestor A. Masriera, C. Mazufri
Although it is widely accepted that coupling a Desalination Plant (DP) to a Nuclear Power Plant (NPP) does not pose any significant additional hazard, it must clearly be considered as a major modification of the design and, therefore, requires issuing an ad hoc version of the Facility Safety Analysis Report (SAR). Documentation is already available covering general safety aspects of nuclear desalination, including standards and applicable requirements, as well as methodologies for assessing potential exposure. In this report, a specific analysis of the main features to be considered for producing the safety analysis report of a nuclear desalination plant will be presented. For the sake of clarity, it is assumed that there is an existing SAR of the NPP and only the additional information to be included in the SAR will be considered. The scope of this additional information is extremely dependent on the desalination technology and the coupling scheme. Therefore, the kind of nuclear desalination process coupling, i.e. thermal, mechanical or electrical, must be defined as a previous task. A thorough review of the main contents of the SAR is performed in order to identify the relevant points, if any, which need to be included in every chapter coping with the coupling. The SAR chapters' content and scope are considered in accordance with IAEA guidelines. As part of the safety report, possible accidental event analysis and their consequences must be included and, therefore, the deterministic analysis of an envelope case of contamination release through the DP must be assessed. The elaboration of this safety case is analysed, and the justified scope of the models needed to quantify the contamination transport mechanisms is presented. Finally, the most commonly accepted techniques and codes, used for the deterministic safety analysis of nuclear plants and effectively applicable to nuclear desalination plants, are presented by the use of the modelling tool DESNU.
{"title":"Specific contents of the SAR for a nuclear desalination plant","authors":"A. Doval, Nestor A. Masriera, C. Mazufri","doi":"10.1504/IJND.2004.003673","DOIUrl":"https://doi.org/10.1504/IJND.2004.003673","url":null,"abstract":"Although it is widely accepted that coupling a Desalination Plant (DP) to a Nuclear Power Plant (NPP) does not pose any significant additional hazard, it must clearly be considered as a major modification of the design and, therefore, requires issuing an ad hoc version of the Facility Safety Analysis Report (SAR). Documentation is already available covering general safety aspects of nuclear desalination, including standards and applicable requirements, as well as methodologies for assessing potential exposure. In this report, a specific analysis of the main features to be considered for producing the safety analysis report of a nuclear desalination plant will be presented. For the sake of clarity, it is assumed that there is an existing SAR of the NPP and only the additional information to be included in the SAR will be considered. The scope of this additional information is extremely dependent on the desalination technology and the coupling scheme. Therefore, the kind of nuclear desalination process coupling, i.e. thermal, mechanical or electrical, must be defined as a previous task. A thorough review of the main contents of the SAR is performed in order to identify the relevant points, if any, which need to be included in every chapter coping with the coupling. The SAR chapters' content and scope are considered in accordance with IAEA guidelines. As part of the safety report, possible accidental event analysis and their consequences must be included and, therefore, the deterministic analysis of an envelope case of contamination release through the DP must be assessed. The elaboration of this safety case is analysed, and the justified scope of the models needed to quantify the contamination transport mechanisms is presented. Finally, the most commonly accepted techniques and codes, used for the deterministic safety analysis of nuclear plants and effectively applicable to nuclear desalination plants, are presented by the use of the modelling tool DESNU.","PeriodicalId":218810,"journal":{"name":"International Journal of Nuclear Desalination","volume":"26 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1900-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"122394812","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}
Pub Date : 1900-01-01DOI: 10.1504/IJND.2006.012513
R. Abraham, T. Singh
Seawater desalination technology is emerging as freshwater requirements are alarmingly increasing all over the world. Conventional technologies such as reverse osmosis and multistage flash evaporation have their limitations, such as chemical treatment and scaling. Low-Temperature Thermal Desalination (LTTD) is an attractive technology with vast potential. It makes use of the ocean temperature difference (thermocline) between surface water and deep seawater. Using the experimental setup established at NIOT, studies were carried out by varying the warm and cold water temperatures. A combination of a roots blower with a water ring vacuum pump was used to generate the required vacuum. Based on the experimental results, a desalination plant for technology demonstration was proposed for one of the island groups in the Indian Ocean. It is intended to draw water from a 350 m depth. This cold water is used to condense the vapour that is being flashed under vacuum from surface seawater. In order to reduce the power consumption, barometric sealing is used by placing the flash chamber and condenser at about 10 m. This paper discusses the design and technical details of the seawater desalination plant for Lakshadweep Islands, along with experimental results.
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