Pub Date : 2010-01-01DOI: 10.1787/9789264087156-41-EN
William Reckley
The use of a nuclear power plant to produce hydrogen or for other process heat applications will present challenges to the licensing process. Potential safety and regulatory issues have been evaluated to identify possible research needs, policy concerns and licensing approaches. A brief description of nuclear power plant licensing in the United States and a discussion of specific issues for using nuclear power plants for process heat applications are presented.
{"title":"Nuclear safety and regulatory considerations for nuclear hydrogen production","authors":"William Reckley","doi":"10.1787/9789264087156-41-EN","DOIUrl":"https://doi.org/10.1787/9789264087156-41-EN","url":null,"abstract":"The use of a nuclear power plant to produce hydrogen or for other process heat applications will present challenges to the licensing process. Potential safety and regulatory issues have been evaluated to identify possible research needs, policy concerns and licensing approaches. A brief description of nuclear power plant licensing in the United States and a discussion of specific issues for using nuclear power plants for process heat applications are presented.","PeriodicalId":88069,"journal":{"name":"Nuclear science abstracts","volume":"1 1","pages":"355-361"},"PeriodicalIF":0.0,"publicationDate":"2010-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"88229706","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 : 2010-01-01DOI: 10.1787/9789264087156-44-EN
Hidenori Sato, N. Sakaba, Naoki Sano, H. Ohashi, Yuu Tachibana, K. Kunitomi
One of the key safety issues for nuclear hydrogen production is the heat transfer tube rupture in intermediated heat exchangers (IHX) which provide heat to process heat applications. This study focused on the detection method and system behaviour assessments during the IHX tube rupture scenario (IHXTR) in the HTTR coupled with IS process hydrogen production system (HTTR-IS system). The results indicate that monitoring the integral of secondary helium gas supply would be the most effective detection method. Furthermore, simultaneous actuation of two isolation valves could reduce the helium gas transportation from primary to secondary cooling systems. The results of system behaviour show that evaluation items do not exceed the acceptance criteria during the scenario. Maximum fuel temperature also does not exceed initial value and therefore the reactor core was not seriously damaged and cooled sufficiently.
{"title":"Conceptual design of the HTTR-IS nuclear hydrogen production system","authors":"Hidenori Sato, N. Sakaba, Naoki Sano, H. Ohashi, Yuu Tachibana, K. Kunitomi","doi":"10.1787/9789264087156-44-EN","DOIUrl":"https://doi.org/10.1787/9789264087156-44-EN","url":null,"abstract":"One of the key safety issues for nuclear hydrogen production is the heat transfer tube rupture in intermediated heat exchangers (IHX) which provide heat to process heat applications. This study focused on the detection method and system behaviour assessments during the IHX tube rupture scenario (IHXTR) in the HTTR coupled with IS process hydrogen production system (HTTR-IS system). The results indicate that monitoring the integral of secondary helium gas supply would be the most effective detection method. Furthermore, simultaneous actuation of two isolation valves could reduce the helium gas transportation from primary to secondary cooling systems. The results of system behaviour show that evaluation items do not exceed the acceptance criteria during the scenario. Maximum fuel temperature also does not exceed initial value and therefore the reactor core was not seriously damaged and cooled sufficiently.","PeriodicalId":88069,"journal":{"name":"Nuclear science abstracts","volume":"65 1","pages":"387-395"},"PeriodicalIF":0.0,"publicationDate":"2010-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"76893556","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 : 2010-01-01DOI: 10.1787/9789264087156-26-EN
W. Summers
The DOE Nuclear Hydrogen Initiative has selected two sulphur cycles, the sulphur iodine (SI) cycle and the HyS process, as the first priority thermochemical processes for development and potential demonstration with the next generation nuclear plant. Both cycles share a common high temperature reaction step – the catalytic thermal decomposition of sulphuric acid. However, they are fundamentally different in the methods used for the hydrogen production step.
{"title":"Development status of the hybrid sulphur thermochemical hydrogen production process","authors":"W. Summers","doi":"10.1787/9789264087156-26-EN","DOIUrl":"https://doi.org/10.1787/9789264087156-26-EN","url":null,"abstract":"The DOE Nuclear Hydrogen Initiative has selected two sulphur cycles, the sulphur iodine (SI) cycle and the HyS process, as the first priority thermochemical processes for development and potential demonstration with the next generation nuclear plant. Both cycles share a common high temperature reaction step – the catalytic thermal decomposition of sulphuric acid. However, they are fundamentally different in the methods used for the hydrogen production step.","PeriodicalId":88069,"journal":{"name":"Nuclear science abstracts","volume":"33 1","pages":"223-223"},"PeriodicalIF":0.0,"publicationDate":"2010-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"74953393","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 : 2010-01-01DOI: 10.1787/9789264087156-48-EN
R. Vilim
High temperature creep in structures at the interface between the nuclear plant and the hydrogen plant and the migration of tritium from the core through structures in the interface are two key challenges for the very high temperature reactor (VHTR) coupled to the high temperature electrolysis (HTE) process. The severity of these challenges, however, can be reduced by lowering the temperature at which the interface operates. Preferably this should be accomplished in a way that does not reduce combined plant efficiency and other performance measures. A means for doing so is described. A heat pump is used to raise the temperature of near-waste heat from the PCU to the temperature at which nine-tenths of the HTE process heat is needed. In addition to mitigating tritium transport and creep of structures, structural material commodity costs are reduced and plant efficiency is increased by 1%.
{"title":"Alternate VHTR/HTE interface for mitigating tritium transport and structure creep","authors":"R. Vilim","doi":"10.1787/9789264087156-48-EN","DOIUrl":"https://doi.org/10.1787/9789264087156-48-EN","url":null,"abstract":"High temperature creep in structures at the interface between the nuclear plant and the hydrogen plant and the migration of tritium from the core through structures in the interface are two key challenges for the very high temperature reactor (VHTR) coupled to the high temperature electrolysis (HTE) process. The severity of these challenges, however, can be reduced by lowering the temperature at which the interface operates. Preferably this should be accomplished in a way that does not reduce combined plant efficiency and other performance measures. A means for doing so is described. A heat pump is used to raise the temperature of near-waste heat from the PCU to the temperature at which nine-tenths of the HTE process heat is needed. In addition to mitigating tritium transport and creep of structures, structural material commodity costs are reduced and plant efficiency is increased by 1%.","PeriodicalId":88069,"journal":{"name":"Nuclear science abstracts","volume":"131 ","pages":"433-444"},"PeriodicalIF":0.0,"publicationDate":"2010-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"72556643","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 : 2010-01-01DOI: 10.1787/9789264087156-46-EN
S. Fukada, Nobutaka Hayashi
A chemical heat pump system using two hydrogen-absorbing alloys is proposed to utilise heat exhausted from a high-temperature source such as a high-temperature gas-cooled reactor (HTGR), more efficiently. The heat pump system is designed to produce H2 based on the S-I cycle more efficiently. The overall system proposed here consists of HTGR, He gas turbines, chemical heat pumps and reaction vessels corresponding to the three-step decomposition reactions comprised in the S-I process. A fundamental research is experimentally performed on heat generation in a single bed packed with a hydrogen-absorbing alloy that may work at the H2 production temperature. The hydrogen-absorbing alloy of Zr(V1-XFeX)2 is selected as a material that has a proper plateau pressure for the heat pump system operated between the input and output temperatures of HTGR and reaction vessels of the S-I cycle. Temperature jump due to heat generated when the alloy absorbs H2 proves that the alloy–H2 system can heat up the exhaust gas even at 600°C without any external mechanical force.
{"title":"Heat pump cycle by hydrogen-absorbing alloys to assist high-temperature gas-cooled reactor in producing hydrogen","authors":"S. Fukada, Nobutaka Hayashi","doi":"10.1787/9789264087156-46-EN","DOIUrl":"https://doi.org/10.1787/9789264087156-46-EN","url":null,"abstract":"A chemical heat pump system using two hydrogen-absorbing alloys is proposed to utilise heat exhausted from a high-temperature source such as a high-temperature gas-cooled reactor (HTGR), more efficiently. The heat pump system is designed to produce H2 based on the S-I cycle more efficiently. The overall system proposed here consists of HTGR, He gas turbines, chemical heat pumps and reaction vessels corresponding to the three-step decomposition reactions comprised in the S-I process. A fundamental research is experimentally performed on heat generation in a single bed packed with a hydrogen-absorbing alloy that may work at the H2 production temperature. The hydrogen-absorbing alloy of Zr(V1-XFeX)2 is selected as a material that has a proper plateau pressure for the heat pump system operated between the input and output temperatures of HTGR and reaction vessels of the S-I cycle. Temperature jump due to heat generated when the alloy absorbs H2 proves that the alloy–H2 system can heat up the exhaust gas even at 600°C without any external mechanical force.","PeriodicalId":88069,"journal":{"name":"Nuclear science abstracts","volume":"25 1","pages":"407-415"},"PeriodicalIF":0.0,"publicationDate":"2010-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"85166759","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 : 2010-01-01DOI: 10.1787/9789264087156-8-EN
N. Ponomarev-Stepnoy, A. Stolyarevskiy, N. Kodochigov
The concept focused on nuclear power for steam reforming of methane and, later, on hydrogen production from water by high temperature solid oxide electrolysis. The programme arises from the premise that the use of hydrogen could grow world wide by a factor of about sixteen over the next century. Anticipating that the main source of hydrogen will continue to be steam reforming of natural gas during much of that period, by 2025, about a quarter of the world’s production of natural gas would be devoted to hydrogen generation, considering both its use as both the energy source and the source of the raw material. The use of nuclear reactors instead of natural gas as the heat source for steam reforming of methane could reduce the total use of natural gas by almost half.
{"title":"The concept of nuclear hydrogen production based on MHR-T reactor","authors":"N. Ponomarev-Stepnoy, A. Stolyarevskiy, N. Kodochigov","doi":"10.1787/9789264087156-8-EN","DOIUrl":"https://doi.org/10.1787/9789264087156-8-EN","url":null,"abstract":"The concept focused on nuclear power for steam reforming of methane and, later, on hydrogen production from water by high temperature solid oxide electrolysis. The programme arises from the premise that the use of hydrogen could grow world wide by a factor of about sixteen over the next century. Anticipating that the main source of hydrogen will continue to be steam reforming of natural gas during much of that period, by 2025, about a quarter of the world’s production of natural gas would be devoted to hydrogen generation, considering both its use as both the energy source and the source of the raw material. The use of nuclear reactors instead of natural gas as the heat source for steam reforming of methane could reduce the total use of natural gas by almost half.","PeriodicalId":88069,"journal":{"name":"Nuclear science abstracts","volume":"30 17 1","pages":"67-75"},"PeriodicalIF":0.0,"publicationDate":"2010-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"83091763","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 : 2010-01-01DOI: 10.1787/9789264087156-15-EN
Vivekanand Sharma, B. Yildiz
High temperature steam electrolysis is one of the most efficient processes for hydrogen generation from water with no CO2 emissions using electricity and heat from nuclear or concentrated solar plants. Solid Oxide Electrolytic Cells (SOEC) are the proposed technology being researched and developed for this purpose. Over a long period of operation of the cells, various sources for degradation in the cells’ electrochemical performance prevail, and hence the cell resistance increases and the process becomes inefficient. Our research is aimed at identifying the mechanisms for the loss in the electrochemical performance of the cell, particularly of the oxygen electrode, namely the anode.
{"title":"Degradation mechanisms in solid oxide electrolysis anodes","authors":"Vivekanand Sharma, B. Yildiz","doi":"10.1787/9789264087156-15-EN","DOIUrl":"https://doi.org/10.1787/9789264087156-15-EN","url":null,"abstract":"High temperature steam electrolysis is one of the most efficient processes for hydrogen generation from water with no CO2 emissions using electricity and heat from nuclear or concentrated solar plants. Solid Oxide Electrolytic Cells (SOEC) are the proposed technology being researched and developed for this purpose. Over a long period of operation of the cells, various sources for degradation in the cells’ electrochemical performance prevail, and hence the cell resistance increases and the process becomes inefficient. Our research is aimed at identifying the mechanisms for the loss in the electrochemical performance of the cell, particularly of the oxygen electrode, namely the anode.","PeriodicalId":88069,"journal":{"name":"Nuclear science abstracts","volume":"36 1","pages":"139-145"},"PeriodicalIF":0.0,"publicationDate":"2010-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"84720481","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 : 2009-04-01DOI: 10.1787/9789264087156-11-EN
J. O'Brien, C. Stoots, M. McKellar, E. Harvego, K. Condie, G. Housley, J. Herring, J. Hartvigsen
This paper provides a status update on the high-temperature electrolysis (HTE) research and development program at the Idaho National Laboratory (INL), with an overview of recent large-scale system modeling results and the status of the experimental program. System analysis results have been obtained using the commercial code UniSim, augmented with a custom high-temperature electrolyzer module. The process flow diagrams for the system simulations include an advanced nuclear reactor as a source of high-temperature process heat, a power cycle and a coupled steam electrolysis loop. Several reactor types and power cycles have been considered, over a range of reactor coolant outlet temperatures. In terms of experimental research, the INL has recently completed an Integrated Laboratory Scale (ILS) HTE test at the 15 kW level. The initial hydrogen production rate for the ILS test was in excess of 5000 liters per hour. Details of the ILS design and operation will be presented. Current small-scale experimental research is focused on improving the degradation characteristics of the electrolysis cells and stacks. Small-scale testing ranges from single cells to multiple-cell stacks. The INL is currently in the process of testing several state-of-the-art anode-supported cells and is working to broaden its relationship with industry in order to improve the long-term performance of the cells.
{"title":"Status of the INL high-temperature electrolysis research program –experimental and modeling","authors":"J. O'Brien, C. Stoots, M. McKellar, E. Harvego, K. Condie, G. Housley, J. Herring, J. Hartvigsen","doi":"10.1787/9789264087156-11-EN","DOIUrl":"https://doi.org/10.1787/9789264087156-11-EN","url":null,"abstract":"This paper provides a status update on the high-temperature electrolysis (HTE) research and development program at the Idaho National Laboratory (INL), with an overview of recent large-scale system modeling results and the status of the experimental program. System analysis results have been obtained using the commercial code UniSim, augmented with a custom high-temperature electrolyzer module. The process flow diagrams for the system simulations include an advanced nuclear reactor as a source of high-temperature process heat, a power cycle and a coupled steam electrolysis loop. Several reactor types and power cycles have been considered, over a range of reactor coolant outlet temperatures. In terms of experimental research, the INL has recently completed an Integrated Laboratory Scale (ILS) HTE test at the 15 kW level. The initial hydrogen production rate for the ILS test was in excess of 5000 liters per hour. Details of the ILS design and operation will be presented. Current small-scale experimental research is focused on improving the degradation characteristics of the electrolysis cells and stacks. Small-scale testing ranges from single cells to multiple-cell stacks. The INL is currently in the process of testing several state-of-the-art anode-supported cells and is working to broaden its relationship with industry in order to improve the long-term performance of the cells.","PeriodicalId":88069,"journal":{"name":"Nuclear science abstracts","volume":"41 1","pages":"101-117"},"PeriodicalIF":0.0,"publicationDate":"2009-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"81410790","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 : 2009-03-12DOI: 10.1787/9789264087156-47-EN
Richard B. Vilim
Control system studies were performed for the Next Generation Nuclear Plant (NGNP) interfaced to the High Temperature Electrolysis (HTE) plant. Temperature change and associated thermal stresses are important factors in determining plant lifetime. In the NGNP the design objective of a 40 year lifetime for the Intermediate Heat Exchanger (IHX) in particular is seen as a challenge. A control system was designed to minimize temperature changes in the IHX and more generally at all high-temperature locations in the plant for duty-cycle transients. In the NGNP this includes structures at the reactor outlet and at the inlet to the turbine. This problem was approached by identifying those high-level factors that determine temperature rates of change. First are the set of duty cycle transients over which the control engineer has little control but which none-the-less must be addressed. Second is the partitioning of the temperature response into a quasi-static component and a transient component. These two components are largely independent of each other and when addressed as such greater understanding of temperature change mechanisms and how to deal with them is achieved. Third is the manner in which energy and mass flow rates are managed. Generally one aims for a temperature distribution that minimizes spatial non-uniformity of thermal expansion in a component with time. This is can be achieved by maintaining a fixed spatial temperature distribution in a component during transients. A general rule of thumb for heat exchangers is to maintain flow rate proportional to thermal power. Additionally the product of instantaneous flow rate and heat capacity should be maintained the same on both sides of the heat exchanger. Fourth inherent mechanisms for stable behavior should not be compromised by active controllers that can introduce new feedback paths and potentially create under-damped response. Applications of these principles to the development of a plant control strategy for the reference NGNP/HTE plant can be found in the body of this report. The outcome is an integrated plant/control system design. The following conclusions are drawn from the analysis: (1) The plant load schedule can be managed to maintain near-constant hot side temperatures over the load range in both the nuclear and chemical plant. (2) The reactor open-loop response is inherently stable resulting mainly from a large Doppler temperature coefficient compared to the other reactivity temperature feedbacks. (3) The typical controller used to manage reactor power production to maintain reactor outlet temperature at a setpoint introduces a feedback path that tends to destabilize reactor power production in the NGNP. (4) A primary loop flow controller that forces primary flow to track PCU flow rate is effective in minimizing spatial temperature differentials within the IHX. (5) Inventory control in both the primary and PCU system during ramp load change transients is an effective means of main
{"title":"Heat exchanger temperature response for duty-cycle transients in the NGNP/HTE.","authors":"Richard B. Vilim","doi":"10.1787/9789264087156-47-EN","DOIUrl":"https://doi.org/10.1787/9789264087156-47-EN","url":null,"abstract":"Control system studies were performed for the Next Generation Nuclear Plant (NGNP) interfaced to the High Temperature Electrolysis (HTE) plant. Temperature change and associated thermal stresses are important factors in determining plant lifetime. In the NGNP the design objective of a 40 year lifetime for the Intermediate Heat Exchanger (IHX) in particular is seen as a challenge. A control system was designed to minimize temperature changes in the IHX and more generally at all high-temperature locations in the plant for duty-cycle transients. In the NGNP this includes structures at the reactor outlet and at the inlet to the turbine. This problem was approached by identifying those high-level factors that determine temperature rates of change. First are the set of duty cycle transients over which the control engineer has little control but which none-the-less must be addressed. Second is the partitioning of the temperature response into a quasi-static component and a transient component. These two components are largely independent of each other and when addressed as such greater understanding of temperature change mechanisms and how to deal with them is achieved. Third is the manner in which energy and mass flow rates are managed. Generally one aims for a temperature distribution that minimizes spatial non-uniformity of thermal expansion in a component with time. This is can be achieved by maintaining a fixed spatial temperature distribution in a component during transients. A general rule of thumb for heat exchangers is to maintain flow rate proportional to thermal power. Additionally the product of instantaneous flow rate and heat capacity should be maintained the same on both sides of the heat exchanger. Fourth inherent mechanisms for stable behavior should not be compromised by active controllers that can introduce new feedback paths and potentially create under-damped response. Applications of these principles to the development of a plant control strategy for the reference NGNP/HTE plant can be found in the body of this report. The outcome is an integrated plant/control system design. The following conclusions are drawn from the analysis: (1) The plant load schedule can be managed to maintain near-constant hot side temperatures over the load range in both the nuclear and chemical plant. (2) The reactor open-loop response is inherently stable resulting mainly from a large Doppler temperature coefficient compared to the other reactivity temperature feedbacks. (3) The typical controller used to manage reactor power production to maintain reactor outlet temperature at a setpoint introduces a feedback path that tends to destabilize reactor power production in the NGNP. (4) A primary loop flow controller that forces primary flow to track PCU flow rate is effective in minimizing spatial temperature differentials within the IHX. (5) Inventory control in both the primary and PCU system during ramp load change transients is an effective means of main","PeriodicalId":88069,"journal":{"name":"Nuclear science abstracts","volume":"14 1","pages":"417-431"},"PeriodicalIF":0.0,"publicationDate":"2009-03-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"83512936","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 : 2008-01-01DOI: 10.1787/9789264044791-8-EN
H. Abderrahim, M. Tanigaki
The GUINEVERE project is a European project in the framework of FP6 IP-EUROTRANS. The IP-EUROTRANS project aims at addressing the main issues for ADS development in the framework of partitioning and transmutation for nuclear waste volume and radiotoxicity reduction. The GUINEVERE project is carried out in the context of Domain 2 of IP-EUROTRANS, ECATS, devoted to specific experiments for the coupling of an accelerator, a target and a subcritical core. These experiments should provide an answer to the questions of on-line reactivity monitoring, subcriticality determination and operational procedures (loading, start-up, shutdown, etc.) in an ADS by 2009-2010. The GUINEVERE project will make use of the VENUS reactor, serving as a lead fast critical facility, coupled to a continuous beam accelerator. In order to achieve this goal, the VENUS facility has to be adapted and a modified GENEPI-C accelerator has to be designed and constructed. During the years 2007 and 2008, the VENUS facility will be modified in order to allow the experimental programme to start in 2009. The paper describes the main achievements with regard to the modifications for the VENUS facility.
{"title":"SESSION V - ADS Experiments and Test Facilities","authors":"H. Abderrahim, M. Tanigaki","doi":"10.1787/9789264044791-8-EN","DOIUrl":"https://doi.org/10.1787/9789264044791-8-EN","url":null,"abstract":"The GUINEVERE project is a European project in the framework of FP6 IP-EUROTRANS. The IP-EUROTRANS project aims at addressing the main issues for ADS development in the framework of partitioning and transmutation for nuclear waste volume and radiotoxicity reduction. The GUINEVERE project is carried out in the context of Domain 2 of IP-EUROTRANS, ECATS, devoted to specific experiments for the coupling of an accelerator, a target and a subcritical core. These experiments should provide an answer to the questions of on-line reactivity monitoring, subcriticality determination and operational procedures (loading, start-up, shutdown, etc.) in an ADS by 2009-2010. The GUINEVERE project will make use of the VENUS reactor, serving as a lead fast critical facility, coupled to a continuous beam accelerator. In order to achieve this goal, the VENUS facility has to be adapted and a modified GENEPI-C accelerator has to be designed and constructed. During the years 2007 and 2008, the VENUS facility will be modified in order to allow the experimental programme to start in 2009. The paper describes the main achievements with regard to the modifications for the VENUS facility.","PeriodicalId":88069,"journal":{"name":"Nuclear science abstracts","volume":"26 1","pages":"375-444"},"PeriodicalIF":0.0,"publicationDate":"2008-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"91222831","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}
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