A preliminary economic feasibility assessment of nuclear desalination in Madura Island

International Nuclear Information System (INIS)

Kim, S.-H.; Hwang, Y.-D.; Konishi, T.; Hudi Hastowo

2005-01-01

A joint study between KAERI and BATAN, which is entitled 'A preliminary economic feasibility assessment of nuclear desalination in Madura Island', is being conducted under the framework of the Interregional Technical Cooperation Project of IAEA, signed on Oct. 10, 2001 at IAEA. The duration of the project is January 2002 to December 2004. An economic feasibility of nuclear desalination using system-integrated modular advanced reactor (SMART), which will provide Madura Island with electricity and potable water and also support industrialisation and tourism, will be assessed during the project. The scope of this joint study includes the analyses for the short- and long-term energy and water demand as well as the supply plan for Madura Island, evaluation of the site characteristics, environmental impacts and health aspects, technical and economic evaluation of SMART and its desalination system, including the feasibility of its being identified on the Madura Island. KAERI and BATAN are cooperating in conducting a joint study, and IAEA provides technical support and a review of the study products. This paper presents the interim results of the joint study by focussing on the technical and economic aspects of nuclear desalination using SMART in Madura Island. (author)

Study of feasible and sustainable multilateral approach on nuclear fuel cycle

International Nuclear Information System (INIS)

Kuno, Y.; Tazaki, M.; Akiba, M.; Takashima, R.; Izumi, Y.; Tanaka, S.

2013-01-01

Despite the Fukushima accident it is undeniable that nuclear power remains one of the most important methods to handle global growth of economic/energy consumption and issues with greenhouse gases. If the demand for nuclear power increases, the demand for not only the generation of power but also for refining uranium (U), conversion, enrichment, re-conversion, and fuel manufacturing should increase. In addition, concerns for the proliferation of 'Sensitive Nuclear Technologies' (SNT) should also increase. We propose a demand-side approach, where nuclear fuel cycle (NFC) activities would be implemented among multiple states. With this approach, NFC services, in particular those using SNTs, are multilaterally executed and controlled, thereby preventing unnecessary proliferation of SNTs, and enabling safe and appropriate control of nuclear technologies and nuclear materials. This proposal would implement nuclear safety and security at an international level and solve transport issues for nuclear fuels. This proposal is based on 3 types of cooperation for each element of NFC: type A: cooperation for 3S only, services received; Type B: cooperation for 3S, MNA (Multilateral Nuclear Activities) without transfer of ownership to MNA; and Type C cooperation for 3S, MNA holding ownership rights. States involved in the 3 types of activity should be referred to as partner states, host states, and site states respectively. The feasibility of the proposal is discussed for the Asian region

Human reliability data bank: feasibility study

International Nuclear Information System (INIS)

Comer, K.; Miller, D.P.; Donovan, M.

1984-01-01

The US Nuclear Regulatory Commission and Sandia National Laboratories have been developing a plan for a human reliability data bank since August 1981. This research is in response to the data needs of the nuclear power industry's probabilistic risk assessment community. The three phases of the program are to: (A) develop the data bank concept, (B) develop an implementation plan and conduct a feasibility study, and (C) assist a sponsor in implementing the data bank. The program is now in Phase B. This paper describes the methods used in the feasibility study. Decisions to be made in the future regarding full-scale implementation will be based, in part, on the outcome of this study. 3 references, 2 figures

Heat balance calculation and feasibility analysis for initial startup of Fuqing nuclear turbine unit with non-nuclear steam

International Nuclear Information System (INIS)

He Liu; Xiao Bo; Song Yumeng

2014-01-01

Non-nuclear steam run up compared with nuclear steam run up, can verify the design, manufacture, installation quality of the unit, at the same time shorten the follow-up duration of the entire group ready to start debugging time. In this paper, starting from the first law of thermodynamics, Analyzed Heat balance Calculation and Feasibility analysis for Initial startup of Fuqing nuclear Turbine unit with Non-nuclear steam, By the above calculation, to the system requirements and device status on the basis of technical specifications, confirmed the feasibility of Non-nuclear steam running up in theory. After the implementation of the Non-nuclear turn of Fuqing unit, confirmed the results fit with the actual process. In summary, the Initial startup of Fuqing turbine unit with Non-nuclear steam is feasible. (authors)

Feasibility study on application of new concept of environmental assessment to nuclear energy

International Nuclear Information System (INIS)

Lee, Young Eal; Lee, Kun Jai

2000-01-01

The existing environmental assessments of nuclear energy are focused on the two kinds of issues such as prevention of green house gas emission and radiological impact assessment. So, the comparative assessment of the other resources such as fossil fuels has been the main part and this result has been the side of nuclear power as the clean energy resource. However, now is when to develop the methodology that approaches to environmental assessment of energy in terms of the various environmental categories. Life Cycle Assessment (LCA) would be the effective environmental assessment tool, which is able to meet the necessity mentioned above. Also classification of the radiological impact and calculation of the environmental impact from the radioactive substances are indispensable as long as the nuclear energy is considered in the application of LCA for the utilization of energy in the industry. However, direct introduction of LCA to the nuclear energy is difficult more or less due to the absence of the methodology for the radiological impact assessment within the LCA framework. Therefore, this study suggests the new concept of environmental assessment. Also current status of development for the classification factor of radiological impact is introduced and investigates the feasibility of application of it to nuclear power generation system

Feasibility study of computerized presentation of procedures of a nuclear plant

International Nuclear Information System (INIS)

Takagawa, Kenichi; Niwa, Yuji; Urakami, Masahiro

2010-01-01

Introduction of a digital instrumentation control system is in progress in recent nuclear power plants, and an application of Computer Based Procedures (CBP) is being considered. The Institute of Nuclear Safety System, Incorporated has developed a system for a Computerized Presentation of Procedures (CPP) which corresponds to CBP. By fiscal year 2002, all items in the emergency operation procedures of a model plant were made displayable on the CPP. In 2003, the CPP instead of the paper based procedures was used for trial by the operators of a nuclear power plant in an actual training simulator, and feasibility of its practical application was evaluated. Based on the result, we considered subjects which should be taken into account in the future. As a result, improvements of CPP and its navigation system, etc. to enable operations with multi-procedures in parallel were extracted as primary subjects for introduction of CBP in the future as well as practical application of CPP. (author)

Recent progress in the feasibility study for the first nuclear power plant in Indonesia

International Nuclear Information System (INIS)

Adiwardojo

1997-01-01

The energy consumption in Indonesia has been continually increasing since 1970 at an average rate of ∼ 10.6%/year. Specifically, for the island of Java, which consumes ∼ 80% of Indonesia's electricity, the installed capacity by PLN was 6363MW in 1990/91. This has increased by ∼ 17%/year during the past three years. Additional increase in electrical consumption of the Java-Bali system projects the need for the installed capacity to reach 31,845 MW in 2003/04. In anticipation of this major addition of installed capacity, the government of Indonesia is conducting feasibility studies of the nuclear option as a means of filling the projected deficit or gap where other fuel options are likely to reach their limits. This paper describes the scope of the present feasibility study including energy economics and financing, technical and safety aspects, the fuel cycle and waste management, general management, and site and environmental studies. (author). 4 refs, 1 fig., 4 tabs

Recent progress in the feasibility study for the first nuclear power plant in Indonesia

International Nuclear Information System (INIS)

Subki, I.R.; Iskandar, A.; Supadi, S.

1994-01-01

In September 1989 the Indonesian Government decided to perform a Nuclear Power Plant feasibility study, including a comprehensive investigation of Muris site. This presentation reports on the progress to date in the two main components of this study: (a) the non-site studies, covering energy economics, financing, technical and safety aspects, the fuel cycle and waste management as well as general management aspects, and (b) site and environmental studies, covering field investigations, assessment of site selection, site qualification/evaluation, environmental, socio-economic and cultural impacts. The study is carried out under a comprehensive quality assurance programme developed by a consultancy company - NEWJEC Inc., which compiles with IAEA recommendations and was approved by BATAN. A summary of the main results, recommendations and general conclusions is presented. It is estimated that the total investment for the construction of 2 x 900 MWe or 3 x 600 MWe class Nuclear Power Plant units would be around US$7 to US$9 billion. 8 tabs

General discussion of feasibility study

International Nuclear Information System (INIS)

Calori, F.

1976-01-01

Fundamentals, objectives and parameters of feasibility studies in the field of nuclear power project planning are discussed in a general way. Technical and economic problems to be considered are pointed out. In special cases, IAEA offers its aid and support. (UA) [de

Nuclear-power-safety reporting system: feasibility analysis

International Nuclear Information System (INIS)

Finlayson, F.C.; Ims, J.

1983-04-01

The US Nuclear Regulatory Commission (NRC) is evaluating the possibility of instituting a data gathering system for identifying and quantifying the factors that contribute to the occurrence of significant safety problems involving humans in nuclear power plants. This report presents the results of a brief (6 months) study of the feasibility of developing a voluntary, nonpunitive Nuclear Power Safety Reporting System (NPSRS). Reports collected by the system would be used to create a data base for documenting, analyzing and assessing the significance of the incidents. Results of The Aerospace Corporation study are presented in two volumes. This document, Volume I, contains a summary of an assessment of the Aviation Safety Reporting System (ASRS). The FAA-sponsored, NASA-managed ASRS was found to be successful, relatively low in cost, generally acceptable to all facets of the aviation community, and the source of much useful data and valuable reports on human factor problems in the nation's airways. Several significant ASRS features were found to be pertinent and applicable for adoption into a NPSRS

Nuclear power safety reporting system feasibility analysis and concept description

International Nuclear Information System (INIS)

Finlayson, F.C.; Ims, J.R.; Hussman, T.A.

1984-01-01

The Aerospace Corporation is assisting the US Nuclear Regulatory Commission (NRC) in the evaluation of the potential attributes of a voluntary, nonpunitive data gathering system for identifying and quantifying the factors that contribute to the occurrence of significant safety problems involving humans in nuclear power plants. The objectives of the Aerospace Administration (FAA)/National Aeronautics and Space Administration (NASA) Aviation Safety Reporting System (ASRS) in order to determine whether it would be feasible to apply part (or all) of the ASRS concepts for collecting data on human factor related incidents to the nuclear industry; and (2) to identify and define the basic elements and requirements of a Nuclear Power Safety Reporting System (NPSRS), assuming the feasibility of implementing such a system was established

Feasibility of the recent Russian nuclear electric propulsion concept: 2010

International Nuclear Information System (INIS)

Zakirov, Vadim; Pavshook, Vladimir

2011-01-01

Highlights: → The paper focuses on feasibility of the Russian nuclear electric propulsion (NEP) concept. → The Russian NEP concept is based on the past experience and is, therefore, technically feasible. → The big concern is that the program will be cancelled due to non-technical issues. - Abstract: The paper introduces recent Russian nuclear electric propulsion (NEP) concept for space exploration. The concept advantages are listed along with future missions. The current development status for the two main enabling technologies is presented and the feasibility analysis of the up-to-date experience is performed. The main features of NEP concept are discussed. Revision of these features and available technologies demonstrates that the NEP concept is a logical continuation of the previous efforts by the former Soviet Union. Because no breakthrough technologies are needed for NEP development while the existing technologies only need to be adapted to the megawatt (MW) class NEP the development is considered technically feasible, low risk program likely to succeed unless cancelled by the listed non-technical reasons. Successful NEP space vehicle development is going to bring practical space exploration of solar system to the new level as well as require supplementary payload program, supporting monitoring and communication radar networks. Nuclear safety during future NEP missions can be ensured by adherence to the United Nations guidelines in the same way it was done during the Soviet Topaz Nuclear Power System (NPS) missions.

Feasibility of the recent Russian nuclear electric propulsion concept: 2010

Energy Technology Data Exchange (ETDEWEB)

Zakirov, Vadim, E-mail: v.zakirov@mail.tsinghua.edu.c [Room 3121, Yifu Building, School of Aerospace, Tsinghua University, Haidian District, Beijing 100084 (China); Pavshook, Vladimir, E-mail: vap_ki@mail.r [Russian Research Center ' Kurchatov Institute' , Kurchatov Sq. 1, Moscow 123182 (Russian Federation)

2011-05-15

Highlights: The paper focuses on feasibility of the Russian nuclear electric propulsion (NEP) concept. The Russian NEP concept is based on the past experience and is, therefore, technically feasible. The big concern is that the program will be cancelled due to non-technical issues. - Abstract: The paper introduces recent Russian nuclear electric propulsion (NEP) concept for space exploration. The concept advantages are listed along with future missions. The current development status for the two main enabling technologies is presented and the feasibility analysis of the up-to-date experience is performed. The main features of NEP concept are discussed. Revision of these features and available technologies demonstrates that the NEP concept is a logical continuation of the previous efforts by the former Soviet Union. Because no breakthrough technologies are needed for NEP development while the existing technologies only need to be adapted to the megawatt (MW) class NEP the development is considered technically feasible, low risk program likely to succeed unless cancelled by the listed non-technical reasons. Successful NEP space vehicle development is going to bring practical space exploration of solar system to the new level as well as require supplementary payload program, supporting monitoring and communication radar networks. Nuclear safety during future NEP missions can be ensured by adherence to the United Nations guidelines in the same way it was done during the Soviet Topaz Nuclear Power System (NPS) missions.

Feasibility study of a zone approach concept for the nuclear fuel cycle of Argentina

International Nuclear Information System (INIS)

Saavedra, Analia D.; Castro, Laura B.; Mairal, M.L.; Maceiras, Elena; Fernandez Moreno, Sonia; Vicens, Hugo E.; Llacer, Carlos D.; Valentino, Lucia I.

1999-01-01

An important part of the nuclear material inventory in Argentina is placed in the nuclear fuel cycle devoted to nuclear power generation, with a high frequency of transfers of such material amongst the nuclear facilities involved. These facilities mostly handle natural uranium. At present, the safeguards systems for these facilities is based on 'Facility Approach' concept. Therefore, for each one of them an independent safeguards approach is applied. However, there are specific procedures that while maintaining or increasing safeguards effectiveness may reduce the inspection resources required in the field. One of these procedures is the 'Zone Approach', by means of which there is a reduction in the need for verifying inventory changes amongst the involved facilities and provides assurance against borrowing of nuclear material within the zone. This paper describes the features of the facilities included in the study, the present safeguards approach applied to them and a feasibility analysis of a zone approach scheme. The comparison between 'facility specific approach' and a 'zone approach' would allow determining whether a reduction of the inspection effort currently applied to fulfil the quantitative safeguards criteria in force for these facilities is obtained. On the other hand, a result showing a relevant reduction on the inspection effort while maintaining safeguards effectiveness would permit to re-orient these resources for an optimum application of the 'Strengthened Safeguards System'. (author)

In-plant reliability data base for nuclear plant components: a feasibility study on human error information

International Nuclear Information System (INIS)

Borkowski, R.J.; Fragola, J.R.; Schurman, D.L.; Johnson, J.W.

1984-03-01

This report documents the procedure and final results of a feasibility study which examined the usefulness of nuclear plant maintenance work requests in the IPRDS as tools for understanding human error and its influence on component failure and repair. Developed in this study were (1) a set of criteria for judging the quality of a plant maintenance record set for studying human error; (2) a scheme for identifying human errors in the maintenance records; and (3) two taxonomies (engineering-based and psychology-based) for categorizing and coding human error-related events

Technical economic feasibility study for the implementation of a nuclear power plant for the production of electricity in Colombia

International Nuclear Information System (INIS)

Gonzales, David E.; Bolanos, Hernan G.; Mayorga, Manuel A.; Rodriguez, Edwin A.

2013-01-01

A study on the technical and economic feasibility will be used to implement a nuclear power in Colombia to generate electricity. To this will be searched if there are previous studies on this topic and what they concluded. The manner in which power is supplied will be discussed in a national level nowadays, its strengths and weaknesses. It will be investigated the legal norms that exists in the country on nuclear power and renewable energy sources, the standards established at world level, the nuclear accidents and the great examples. Providers will be sought on the world market nuclear equipment which serve to this purpose and the technical characteristics of these equipment will be discussed. The type of fuel used in nuclear reactors, its origin, method of production, specifications, availability and long-term and safe handling and final disposal are considered. safe handling of this technology and policy or international rules that will studied

A feasibility study for a contained pulsed nuclear propulsion concept

International Nuclear Information System (INIS)

Parlos, A.G.; Metzger, J.D.

1993-01-01

A preliminary analysis of a pulsed propulsion concept is performed utilizing the enormously dense energy generated by small nuclear detonations. The concept feasibility is based on the premise that current materials technology has undergone significant breakthroughs, allowing design of pressure vessels capable of containing the blast associated with such detonations. Furthermore, the rapid energy transfer to the propellant, allows generation of high thrust levels for up to 10 ms following the detonation. Preliminary reevaluation of the concept using off-the-shelf materials technology appears to indicate that the contained pulsed nuclear propulsion concept has no major flaws, and it can provide thrust levels resulting in average thrust-to-weight ratios on the order of 2--2.5 over an engine operating cycle. Furthermore, even though the specific impulse is not a good performance indicator for impulsive engines, operating-cycle-averaged specific impulse of approximately 1800 s has been calculated. The engine mass associated with this performance is on the order of 50 Mg. The concept appears attractive for a number of missions planned for the Space Exploration Initiative, however, there are still a number of issues that must be addressed

Feasibility study of full-reactor gas core demonstration test

Science.gov (United States)

Kunze, J. F.; Lofthouse, J. H.; Shaffer, C. J.; Macbeth, P. J.

1973-01-01

Separate studies of nuclear criticality, flow patterns, and thermodynamics for the gas core reactor concept have all given positive indications of its feasibility. However, before serious design for a full scale gas core application can be made, feasibility must be shown for operation with full interaction of the nuclear, thermal, and hydraulic effects. A minimum sized, and hence minimum expense, test arrangement is considered for a full gas core configuration. It is shown that the hydrogen coolant scattering effects dominate the nuclear considerations at elevated temperatures. A cavity diameter of somewhat larger than 4 ft (122 cm) will be needed if temperatures high enough to vaporize uranium are to be achieved.

Feasibility study of technologies to aid in the diagnosis of nuclear plant transients

International Nuclear Information System (INIS)

Bertch, W.J.; Bray, M.A.; Esparza, V.; Fink, R.K.; Shepherd, J.C.; Venhuizen, J.R.

1985-08-01

A technical feasibility study was performed to identify and evaluate the various computerized techniques available to diagnose and identify nuclear power plant transients in support of improving operator response to emergencies. Five categories of methods were investigated: expert system technology, computerized alarm handling, data driven displays, estimation and failure detection, and fault tree/event tree techniques. Literature searches and personal contacts were used to obtain information on specific methods and their applications within these categories. A set of evaluation criteria was established and an Analytic Hierarchy Process evaluation of the methods was performed. An integrated approach for a computerized operator aid, combining the strong features from the various methods, appears to be the most promising. 91 refs., 1 tab

Economic feasibility of heat supply from nuclear power plants in the United States

International Nuclear Information System (INIS)

Roe, K.K.; Oliker, I.

1987-01-01

Nuclear energy is regarded as competitive for urban district heating applications. Hot water heat transoport systems of up to 50 miles are feasible for heat loads over 1500 MWt, and heat load density of over 130 MWt/mi 2 is most suitable for nuclear applications. An incremental approach and a nuclear plant design provision for future heat extraction are recommended. Nuclear district heating technology status is discussed, particularly turbine design. Results of a study for retrofitting a major existing nuclear power plant to cogeneration operation are presented. The study indicates that for transmission distances up to 20 miles it is economical to generate and transport between 600 and 1200 MWt of district heat (author)

Case studies on the feasibility of the transient analysis system STAR in German nuclear power plants

International Nuclear Information System (INIS)

Buettner, W.E.; Felkel, L.; Zapp, A.

1984-01-01

On the basis of distubances which actually have occurred in German nuclear power plants a case-study has been performed to evaluate the feasibility of the computer-based disturbance analysis system STAR. By means of a compact plant simulator the disturbances collected have been remodelled and anlysed, on-line, with the disturbance analysis system STAR. In the last phase of the project experiments have been performed with reactor operators to get their reaction to, and opinion on, computerbased-operator aids. (orig.) [de

Feasibility study on nuclear core design for soluble boron free small modular reactor

Energy Technology Data Exchange (ETDEWEB)

Rabir, Mohamad Hairie, E-mail: m-hairie@nuclearmalaysia.gov.my; Hah, Chang Joo; Ju, Cho Sung [Department of NPP Engineering, KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

2015-04-29

A feasibility study on nuclear core design of soluble boron free (SBF) core for small size (150MWth) small modular reactor (SMR) was investigated. The purpose of this study was to design a once through cycle SMR core, where it can be used to supply electricity to a remote isolated area. PWR fuel assembly design with 17×17 arrangement, with 264 fuel rods per assembly was adopted as the basis design. The computer code CASMO-3/MASTER was used for the search of SBF core and fuel assembly analysis for SMR design. A low critical boron concentration (CBC) below 200 ppm core with 4.7 years once through cycle length was achieved using 57 fuel assemblies having 170 cm of active height. Core reactivity controlled using mainly 512 number of 4 wt% and 960 12 wt% Gd rods.

Heat resistant materials and their feasibility issues for a space nuclear transportation system

International Nuclear Information System (INIS)

Olsen, C.S.

1991-01-01

A number of nuclear propulsion concepts based on solid-core nuclear propulsion are being evaluated for a nuclear propulsion transportation system to support the Space Exploration Initiative (SEI) involving the reestablishment of a manned lunar base and the subsequent exploration of Mars. These systems will require high-temperature materials to meet the operating conditions with appropriate reliability and safety built into these systems through the selection and testing of appropriate materials. The application of materials for nuclear thermal propulsion (NTP) and nuclear electric propulsion (NEP) systems and the feasibility issues identified for their use will be discussed. Some mechanical property measurements have been obtained, and compatibility tests were conducted to help identify feasibility issues. 3 refs., 1 fig., 4 tabs

Feasibility of safe terminal disposal of spent nuclear fuel

International Nuclear Information System (INIS)

Nilsson, B.; Papp, T.

1980-01-01

The results of the KBS study indicate that safe terminal storage of spent nuclear fuel in crystalline rock is feasible with the technology available today and at a safety level that is well within the limitations recommended by the ICRP. This statement is not only based on the fact that the doses calculated in the KBS study were acceptably low, but even more on the freedom to choose the dimensions of the engineered barriers as well as depth of the repository and to some degree the quality of the host rock

Feasibility study of micro-filtration for algae separation in an innovative nuclear effluents decontamination process

International Nuclear Information System (INIS)

Gouvion Saint Cyr, D. de; Wisniewski, C.; Schrive, L.; Farhi, E.; Rivasseau, C.

2014-01-01

Bio-remediation technologies often offer efficiency, cost and environmental impact benefits against physico-chemical technologies. Concerning the remediation of radionuclide-containing water, a few bio-based technologies have been proposed but none is currently operational in highly radioactive environments. A new radio-tolerant micro-alga, isolated from a nuclear facility, possesses properties that offer new decontamination prospects for the nuclear industry or for the clean-up of environmental water. A pilot-scale treatment unit based on this alga is currently under development for the decontamination of radioactive water. It includes separation and/or concentration steps relying on membrane filtration. This work aims at verifying the feasibility of micro-filtration as separation step for the targeted algae separation. Recommendations about the choice of operating conditions limiting and/or controlling the membrane fouling are provided with the objective to enhance the separation efficiency. Lab-scale dead-end filtration tests were implemented and the key factors involved in the separation performances were investigated. Membrane characteristics, biomass composition, and hydrodynamic conditions were considered. Organic membranes provided adequate filtration performance. Membrane fouling was essentially induced by a rapid reversible algae deposit and to a lesser extent by irreversible pore blockage caused by smaller particles and dissolved organic matter. To cancel the reversible fouling, hydrodynamic actions such as stirring and back-flush efficiently prevented algae deposit, allowing higher filtration productivity. This study demonstrates the feasibility of membrane separation for micro-algae harvesting at laboratory-scale and specifies the suitable working conditions. (authors)

Feasibility study of a dedicate nuclear desalination system: Low-pressure inherent heat sink nuclear desalination plant (LIND)

Energy Technology Data Exchange (ETDEWEB)

Kim, Ho Sik; No, Hee Cheon; Jo, Yu Gwan; Wivisono, Andhika Feri; Park, Byung Ha; Choi, Jin Young; Lee, Jeong Ik; Jeong, Yong Hoon; Cho, Nam Zin [Dept. of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

2015-04-15

In this paper, we suggest the conceptual design of a water-cooled reactor system for a low-pressure inherent heat sink nuclear desalination plant (LIND) that applies the safety-related design concepts of high temperature gas-cooled reactors to a water-cooled reactor for inherent and passive safety features. Through a scoping analysis, we found that the current LIND design satisfied several essential thermal-hydraulic and neutronic design requirements. In a thermal-hydraulic analysis using an analytical method based on the Wooton-Epstein correlation, we checked the possibility of safely removing decay heat through the steel containment even if all the active safety systems failed. In a neutronic analysis using the Monte Carlo N-particle transport code, we estimated a cycle length of approximately 6 years under 200 MW{sub th} and 4.5% enrichment. The very long cycle length and simple safety features minimize the burdens from the operation, maintenance, and spent-fuel management, with a positive impact on the economic feasibility. Finally, because a nuclear reactor should not be directly coupled to a desalination system to prevent the leakage of radioactive material into the desalinated water, three types of intermediate systems were studied: a steam producing system, a hot water system, and an organic Rankine cycle system.

Feasibility study of a dedicated nuclear desalination system: Low-pressure Inherent heat sink Nuclear Desalination plant (LIND

Directory of Open Access Journals (Sweden)

Ho Sik Kim

2015-04-01

Full Text Available In this paper, we suggest the conceptual design of a water-cooled reactor system for a low-pressure inherent heat sink nuclear desalination plant (LIND that applies the safety-related design concepts of high temperature gas-cooled reactors to a water-cooled reactor for inherent and passive safety features. Through a scoping analysis, we found that the current LIND design satisfied several essential thermal–hydraulic and neutronic design requirements. In a thermal–hydraulic analysis using an analytical method based on the Wooton–Epstein correlation, we checked the possibility of safely removing decay heat through the steel containment even if all the active safety systems failed. In a neutronic analysis using the Monte Carlo N-particle transport code, we estimated a cycle length of approximately 6 years under 200 MWth and 4.5% enrichment. The very long cycle length and simple safety features minimize the burdens from the operation, maintenance, and spent-fuel management, with a positive impact on the economic feasibility. Finally, because a nuclear reactor should not be directly coupled to a desalination system to prevent the leakage of radioactive material into the desalinated water, three types of intermediate systems were studied: a steam producing system, a hot water system, and an organic Rankine cycle system.

Examination of Economic Feasibility of Nuclear Weapons in the Republic of Korea

Energy Technology Data Exchange (ETDEWEB)

Suh, Young A; Yim, Man Sung [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

2015-05-15

This observation implies that the popular view on nuclear weapons amongst Korean public is in part due to lack of knowledge about overall implications of possessing nuclear weapons. In this regard, pros and cons of nuclear weapons development need to be better characterized and understood by the public to support nuclear nonproliferation culture development. Noting lack of literature on characterizing the economics of nuclear weapons development, this study aims at performing economic feasibility analysis of nuclear weapons development in the ROK. For this purpose, an approach called Index technique based on the US experiences was applied to Korean historical data along with cost-benefit analysis and Multi-Criteria Decision Making Analysis. In this study, the scenario of nuclear weapons development against North Korean nuclear threat was compared with conventional weapons-based defense strategy. The comparison was based on cost benefit analysis and qualitative multi-criteria decision analysis. Results indicate that nuclear weapons development is not a desirable option. However, as this work was a rather simplistic academic exercise, further work is needed to support the outcome of the study. Outcome of these investigations would be useful for communication with the public regarding the need for nuclear weapons for national defense and to develop nuclear nonproliferation culture in the ROK.

Examination of Economic Feasibility of Nuclear Weapons in the Republic of Korea

International Nuclear Information System (INIS)

Suh, Young A; Yim, Man Sung

2015-01-01

This observation implies that the popular view on nuclear weapons amongst Korean public is in part due to lack of knowledge about overall implications of possessing nuclear weapons. In this regard, pros and cons of nuclear weapons development need to be better characterized and understood by the public to support nuclear nonproliferation culture development. Noting lack of literature on characterizing the economics of nuclear weapons development, this study aims at performing economic feasibility analysis of nuclear weapons development in the ROK. For this purpose, an approach called Index technique based on the US experiences was applied to Korean historical data along with cost-benefit analysis and Multi-Criteria Decision Making Analysis. In this study, the scenario of nuclear weapons development against North Korean nuclear threat was compared with conventional weapons-based defense strategy. The comparison was based on cost benefit analysis and qualitative multi-criteria decision analysis. Results indicate that nuclear weapons development is not a desirable option. However, as this work was a rather simplistic academic exercise, further work is needed to support the outcome of the study. Outcome of these investigations would be useful for communication with the public regarding the need for nuclear weapons for national defense and to develop nuclear nonproliferation culture in the ROK

A Feasibility Study of Optimal Nuclear Desalination Process for Industrial Water Supply in Korea

International Nuclear Information System (INIS)

Park, Hyunchul; Han, Kiin

2013-01-01

Seawater Desalination can be an alternative technology for water production based on salt separation from seawater. Seawater desalination can produce freshwater with necessary quality by choosing an appropriate desalination process and posttreatment methods of the product water. The commercial seawater desalination processes which are proven and reliable for large scale freshwater production are MSF and MED for evaporative desalination and RO for membrane desalination. Vapor compression plants based on thermal and mechanical compression are also employed for the small and medium capacity ranges. The aim of this study is to compare the characteristics and cost of each process methods and suggest the most efficient and effective method of desalination for an industrial water supply to the National Industrial Complex nearby Nuclear Power Plant. The costs associated with desalination depend on many factors such as capital, energy, labor, chemicals that are specific to the location, plant capacity, product salinity pre-treatment necessities, and other site-related costs for land, plant and brine disposal. A detailed analysis of each situation is thus required to estimate desalination costs. It could be stated that RO cost is lower than distillation one in energy and environmental terms. The optimal capacity(10,000 m 3 /day) was decided to analyze the estimated water usage in nuclear power plants. And then compared the availability of each process, energy consumption, O and M and economic aspects. In terms of economic feasibility study, RO is the most recommendable process in nuclear power plants in Korea

Feasibility study on the development of proton accelerator

Energy Technology Data Exchange (ETDEWEB)

Chung, Ki Hyung; Bang, Hyung Chan; Cho, Yong Sup [Seoul National University, Seoul (Korea, Republic of); Kim, Young Rak [Church Environment Research Institute, Seoul (Korea, Republic of); Nam Kung, Won; Cho, Moo Hyun [Pohang University of Science and Technology, Pohang (Korea, Republic of); Seo, Tae Suk [Cartolrik University, Seoul (Korea, Republic of); Woo, Hyung Joo [Nature Research Institute, Seoul (Korea, Republic of); Lee, Kyung Soo [Basic Study Research Institute, Seoul (Korea, Republic of); Lee, Hun Joo [Cheju National University, Cheju (Korea, Republic of); Chang, Soon Hong; Cho, Nam Jin [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of); Han, Jeon Kun [Sungkyunkwan University, Seoul (Korea, Republic of)

1996-10-01

A feasibility on the development of a high energy proton accelerator to be used for R and D in the nuclear field of korea was studied. The proposed one is a proton linac with parameters of about 1 GeV, 20 mA which can supply enough neutrons by the spallation reaction to drive a subcritical reactor. It= is expected to solve the intrinsic problem in the nuclear field such as safety, nuclear waste, proliferation and resource. The study was carried out through a multi-institutional cooperation of universities, institute and industry for a national consensus. 5 refs., 8 tabs., 8 figs. (author)

Feasibility of space disposal of radioactive nuclear waste. 2: Technical summary

Science.gov (United States)

1974-01-01

The feasibility of transporting radioactive waste produced in the process of generating electricity in nuclear powerplants into space for ultimate disposal was investigated at the request of the AEC as a NASA in-house effort. The investigation is part of a broad AEC study of methods for long-term storage or disposal of radioactive waste. The results of the study indicate that transporting specific radioactive wastes, particularly the actinides with very long half-lives, into space using the space shuttle/tug as the launch system, appears feasible from the engineering and safety viewpoints. The space transportation costs for ejecting the actinides out of the solar system would represent less than a 5-percent increase in the average consumer's electric bill.

The feasibility of uranium enrichment in Brazil for use in nuclear bombs and the conceptual project of a nuclear explosive

International Nuclear Information System (INIS)

Rosa, L.P.

1990-05-01

This work reports the steps to define a brazilian system of nuclear safeguards under the congress responsibility. It discusses as well the feasibility of uranium enrichment for nuclear weapons, the construction of a nuclear submarine and the conceptual project of a nuclear explosive. (A.C.A.S.)

Feasibility study of electron beam welding of spent nuclear fuel canisters

International Nuclear Information System (INIS)

Sanderson, A.; Szluha, T.F.; Turner, J.L.; Leggatt, R.H.

1983-04-01

A thick walled copper container is presently the prime Swedish alternative for encapsulation of spent nuclear fuel. In order to demonstrate the feasibility of encapsulating high-level nuclear waste in copper containers, a study of electron beam welding of thick copper has been performed. Two copper qualities have been investigated, oxygen free high conductivity (OFHC) copper and phosphorous desoxydized high conductivity copper (PDO). The findings in this study are summarized below. In 100 mm thick copper penetration can be achived at power level of about 75 kW (typically 150 kV x 500 mA) at welding speed of 100 mm/min. The welds in OFHC copper made under these conditions are free from major defects during constant welding conditions. The welds in PDO copper show a microporosity level considerably higher than those in OFHC copper, but no major defects are produced in the welds in PDO copper. In the ending of the weld (ie the fade out) it is still not possible to completely eliminate root and cold-shut defects. A semi-full-scale lid weld has been performed successfully. Automatic ultrasonic C-scan has been shown to be useful in detecting and displaying defects, but some problems still remain with defect sizing. The different speciments of OFHS copper had different attenuation of the ultrasonic signal, forged copper showing a far lower attenuation than hot extruded copper, indicating that attention must be paid in choosing copper that allows accurate ultrasonic testing. Resiudal stresses in the welded zone has been measured and are found to lie in the range -32N/mm 2 to +36N/mm 2 . The peak stress was less than half the assumed value of the proof stress of the fused metal. (authors)

A cask maintenance facility feasibility study

International Nuclear Information System (INIS)

Rennich, M.J.; Medley, L.G.; Attaway, C.R.

1989-01-01

The Oak Ridge National Laboratory (ORNL) is supporting the USDOE Office of Civilian Radioactive Waste Management (OCRWM) in developing a transportation system for spent nuclear fuel (SNF) and defense high level waste (HLW) as a part of the Federal Waste Management System (FWMS). In early 1988, a feasibility study was undertaken to design a stand-alone, green field facility for maintaining the FWMS casks. The feasibility study provided an initial layout facility design, an estimate of the construction cost, and an acquisition schedule for a Cask Maintenance Facility (CMF). The study also helped to define the interfaces between the transportation system and the waste generators, the repository, and a Monitored Retrieveable Storage (MRS) facility. The data, design, and estimated cost resulting from the study have been organized for use in the total transportation system decision-making process. Most importantly, the feasibility study also provides a foundation for continuing design and planning efforts. The feasibility study was based on an assumed stand-alone green field configuration because of the flexibility this design approach provides. A stand-alone facility requires the inclusion with support functions as well as the primary process facilities thus yielding a comprehensive design evaluation and cost estimate. For example, items such as roads, security and waste processing which might be shared with an integrated or collocated facility have been fully costed in the feasibility study. Thus, while the details of the facility design might change, the overall concept used in the study can be applied to other facility configurations as planning for the total FWMS develops

Feasibility study on commercialized fast reactor cycle systems. (1) Current status of the phase-II study

International Nuclear Information System (INIS)

Sagayama, Yutaka

2005-01-01

A feasibility study on commercialized fast reactors including related nuclear fuel cycle systems has been started from Japanese fiscal year 1999 by a Japanese joint project team of Japan Nuclear Cycle Development Institute and the Japan Atomic Power Company. This project aims at elucidating prominent fast reactor cycle systems that will respond to various needs of society in the future, together with economic competitiveness as future electricity supply systems. Challenging technology goals for the fast reactor cycle systems were defined in five targets: safety, economic competitiveness, reduction of environmental burden, efficient utilization of nuclear fuel resources and enhancement of nuclear non-proliferation. As the results of the feasibility study up to now, it is confirmed as the interim results that the combination of sodium-cooled fast reactors with oxide fuels, advanced aqueous reprocessing and simplified pellet fuel fabrication is highly suited to the development targets. The cost would be highly reduced by the adoption of innovative technologies, which feasibility is relatively clear and some R and D issues are now under progress. (author)

Whose Frames Mattered? The Feasibility Study in the Municipality of Tierp 1998-2000

International Nuclear Information System (INIS)

Johansson, Hanna Sofia

2003-01-01

In December 2001 SKB (the Swedish Nuclear Fuel and Waste Management Co) presented a ranking list of the eight feasibility studies carried out in Sweden. The feasibility study in Tierp was cited as showing that potentially good bedrock could be found in the municipality and SKB therefore asked to carry out a site investigation. Tierp is a neighbouring municipality to Oesthammar, a municipality that hosts nuclear power plants, with around 20,000 inhabitants and an area of 1543 km 2 . This paper focuses on why the Municipal Council in Tierp voted 'no' to further investigations even though SKB pointed out the municipality as having potentially good bedrock. In 1998 a feasibility study in Tierp was started. The arguments presented for a feasibility study were: the proximity to Forsmark nuclear power plant in Oesthammar, responsibilities for future generations, and that an investigation of the municipality could be used for other purposes. The main question this paper asks is the following: why did the Municipal Council in Tierp say 'no' to further investigations? This question is of interest since SKB claimed that Tierp had potentially good bedrock. The hypothesis is that the democratic models (representative democracy, discursive democracy or technocracy) present in the feasibility study and the boundary work carried out, i.e. how the boundary between science and politics was drawn, and which actors had access to the discussion on the public agenda, influenced the decision of the Council. The main sources used are interviews and a Swedish governmental investigation report about the feasibility studies. Twelve fairly open interviews with actors from the municipal organization, SKB, local opinion groups and the media were carried out. The questions cover how hey worked with the study, how the municipality organized its work, how they defined the nuclear waste issues and how they tried to communicate their views to other actors

Feasibility studies - Oesthammar, Nykoeping, Oskarshamn, Tierp, Hultsfred and Aelvkarleby. Summary report

International Nuclear Information System (INIS)

2001-06-01

Swedish Nuclear Fuel and Waste Management Company, SKB, has carried out feasibility studies on a municipal scale as a part of the siting programme for the deep repository for spent nuclear fuel. Final reports describing the results of the six feasibility studies in Oesthammar, Nykoeping, Oskarshamn, Tierp, Aelvkarleby and Hultsfred were submitted during the autumn and winter of 2000/2001. With this as a basis, the siting work can now proceed to the next phase - site investigations. In this stage, investigations that include test drilling will be conducted on at least two sites. In December 2000, SKB published the report 'Integrated account of method, site selection and programme prior to the site investigation phase', in which SKB stipulates where they want to conduct site investigations and how they will be carried out. The report is being reviewed by the Swedish Nuclear Power Inspectorate during the first half of 2001. Before the site investigations can be initiated,the go-ahead is required from the national safety authorities, the Government, and concerned municipalities and landowners. SKB projects that the it will be possible to commence the site investigations in 2002. This report comprises an English summary of the final reports from the six feasibility studies. The report summarizes the most important results and conclusions from the different feasibility studies. All six final reports are available in their entirety in Swedish

Feasibility studies - Oesthammar, Nykoeping, Oskarshamn, Tierp, Hultsfred and Aelvkarleby. Summary report

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-06-01

Swedish Nuclear Fuel and Waste Management Company, SKB, has carried out feasibility studies on a municipal scale as a part of the siting programme for the deep repository for spent nuclear fuel. Final reports describing the results of the six feasibility studies in Oesthammar, Nykoeping, Oskarshamn, Tierp, Aelvkarleby and Hultsfred were submitted during the autumn and winter of 2000/2001. With this as a basis, the siting work can now proceed to the next phase - site investigations. In this stage, investigations that include test drilling will be conducted on at least two sites. In December 2000, SKB published the report 'Integrated account of method, site selection and programme prior to the site investigation phase', in which SKB stipulates where they want to conduct site investigations and how they will be carried out. The report is being reviewed by the Swedish Nuclear Power Inspectorate during the first half of 2001. Before the site investigations can be initiated,the go-ahead is required from the national safety authorities, the Government, and concerned municipalities and landowners. SKB projects that the it will be possible to commence the site investigations in 2002. This report comprises an English summary of the final reports from the six feasibility studies. The report summarizes the most important results and conclusions from the different feasibility studies. All six final reports are available in their entirety in Swedish.

The technical feasibility of uranium enrichment for nuclear bomb construction at the parallel nuclear program plant

International Nuclear Information System (INIS)

Rosa, L.P.

1990-01-01

It is discussed the hole of the Parallel Nuclear Program is Brazil and the feasibility of uranium enrichment for nuclear bomb construction. This program involves two research centers, one belonging to the brazilian navy and another to the aeronautics. Some other brazilian institutes like CTA, IPEN, COPESP and CETEX and also taking part in the program. (A.C.A.S.)

A feasibility study on the longer cycle operation of Yonggwang nuclear power plants 3 and 4 (3 rd quarter report)

Energy Technology Data Exchange (ETDEWEB)

Zee Sung Kyun; Song, Jae Woong; Ha, Young Joon; Kim, Kyu Tae [Korea Advanced Institute of Science and Technolgoy, Taejon (Korea, Republic of)

1996-04-01

In this report, described are results of the feasibility study on applying for the 18-month cycle in Korean Standard Nuclear Power Plants (KSNPs). This report contains results of safety and economic evaluations, radiation source analysis, an effect on changing the calibration period for each component of NSSS, and review on the related regulating codes. 12 refs., 34 tabs., 28 figs. (author)

The feasibility of nuclear power development in the Arab world

International Nuclear Information System (INIS)

Boukhars, A.

2009-01-01

In recent years, many Arab countries have manifested an interest in the development of peaceful uses of nuclear technology. This intent, however, was viewed by many commentators through geopolitical and security lens. In contrast with this view, this paper argues for the feasibility and desirability of nuclear power development in the Arab world based on sound economic considerations and economic development needs. The first part of the paper will, therefore, examine the reasons behind the initiatives currently being developed to acquire nuclear energy. The second part will highlight the promise of nuclear power development. The concluding section will illustrate how recognition of the economic motivation for investing in nuclear power generation is important to avoid a misrepresentation of intentions. (Author)

A cask maintenance facility feasibility study

International Nuclear Information System (INIS)

Rennich, M.J.; Medley, L.G.; Attaway, C.R.

1989-01-01

The Oak Ridge National Laboratory (ORNL) is developing a transportation system for spent nuclear fuel (SNF) and defense high level waste (HLW) as a part of the Federal Waste Management System (FWMS). In early 1988, a feasibility study was undertaken to design a stand-alone, ''green field'' facility for maintaining the FWMS casks. The feasibility study provided an initial layout facility design, an estimate of the construction cost, and an acquisition schedule for a Cask Maintenance Facility (CMF). The study also helped to define the interfaces between the transportation system and the waste generators, the repository, and a Monitored Retrievable Storage (MRS) facility. The data, design, and estimated costs resulting from the study have been organized for use in the total transportation system decision-making process. Most importantly, the feasibility study also provides a foundation for continuing design and planning efforts. Fleet servicing facility studies, operational studies from current cask system operators, a definition of the CMF system requirements, and the experience of others in the radioactive waste transportation field were used as a basis for the feasibility study. In addition, several cask handling facilities were visited to observe and discuss cask operations to establish the functions and methods of cask maintenance expected to be used in the facility. Finally, a peer review meeting was held at Oak Ridge, Tennessee in August, 1988, in which the assumptions, design, layout, and functions of the CMF were significantly refined. Attendees included representatives from industry, the repository and transportation operations

Continuous A.E. monitoring of nuclear systems: some feasibility studies now in-progress in France

International Nuclear Information System (INIS)

Roget, J.; Germain, J.L.

1986-01-01

Continuous A.E. monitoring of Nuclear systems can give some unique information about abnormal behaviour (leak appearance...) or crack initiation or propagation. Some feasibility studies have been undertaken in France in this field and this paper presents the results we have got in two cases. The study showed that an A.E. surveillance of pressurized safety valves indicates the appearance or the presence of a leak. Functioning noise is not a problem in this case. Secondly a large study have been undertaken to test the resistance of the pipe inner sleeve to thermal fatigue. An A.E. monitoring showed that it is possible to separate A.E. due to Crack extension from other signals by a location method in spite of high noise level. A.E. seems applicable for continuous monitoring. So, complementary tests are in progress to confirm and improve these results

Idaho Nuclear Technology and Engineering Center Newly Generated Liquid Waste Demonstration Project Feasibility Study

International Nuclear Information System (INIS)

Herbst, A.K.

2000-01-01

A research, development, and demonstration project for the grouting of newly generated liquid waste (NGLW) at the Idaho Nuclear Technology and Engineering Center is considered feasible. NGLW is expected from process equipment waste, decontamination waste, analytical laboratory waste, fuel storage basin waste water, and high-level liquid waste evaporator condensate. The potential grouted waste would be classed as mixed low-level waste, stabilized and immobilized to meet RCRA LDR disposal in a grouting process in the CPP-604 facility, and then transported to the state

Staging and storage facility feasibility study. Final report

International Nuclear Information System (INIS)

Swenson, C.E.

1995-02-01

This study was performed to investigate the feasibility of adapting the design of the HWVP Canister Storage Building (CSB) to meet the needs of the WHC Spent Nuclear Fuel Project for Staging and Storage Facility (SSF), and to develop Rough Order of Magnitude (ROM) cost and schedule estimates

Mortality and career radiation doses for workers at a commercial nuclear power plant: feasibility study

International Nuclear Information System (INIS)

Goldsmith, R.; Boice, J.D. Jr.; Hrubec, Z.; Hurwitz, P.E.; Goff, T.E.; Wilson, J.

1989-01-01

Career radiation doses for 8,961 male workers at the Calvert Cliffs Nuclear Power Plant (CCNPP) were determined for both utility (n = 4,960) and contractor (n = 4,001) employees. Workers were followed from the time of first employment at CCNPP (including plant construction) to the end of 1984 (mean follow-up = 5.4 y). Plant operation began in 1975. The mean duration of employment was 1.9 y at CCNPP and 3.1 y in the nuclear industry. Career radiation doses were determined from dosimetry records kept by the utility company and the U.S. Nuclear Regulatory Commission (NRC). For all exposed workers, the average career dose was 21 mSv and was higher for contractor (30 mSv) than utility (13 mSv) workers. Career doses were also higher among those employed in the nuclear industry for greater than or equal to 15 y (111 mSv) and among workers classified as health physicists (56 mSv). Cumulative doses of greater than or equal to 50 mSv were received by 12% of the workers; the maximum career dose reported was 470 mSv. The availability of social security numbers for practically all employees facilitated record-linkage methods to determine mortality; 161 deaths were identified. On average the workers experienced mortality from all causes that was 15% less than that of the general population of the U.S., probably due to healthier members of the population being selected for employment. Our investigation demonstrates that historical information is available from which career doses could be constructed and that, in principle, it is feasible to conduct epidemiologic studies of nuclear power plant workers in the U.S. Although difficult, the approach taken could prove useful until such time as a comprehensive registry of U.S. radiation workers is established

Future Without Nuclear Energy; Is It Feasible, Is It Sensible?

International Nuclear Information System (INIS)

Knapp, V.; Pevec, D.

2012-01-01

The task of reducing CO 2 emission in order to keep the global temperature increase below 2 0 C requires staggering changes in energy consumption and production. It appears, unfortunately, that before obvious and drastic effects of climate change occur, few governments have the strength to implement the energy strategies called for. However, by the time climate change becomes evident to wide public it may be too late or much more difficult. Energy policy is heavily politicized which creates another obstacle to timely action, as witnessed by backlash against nuclear energy following Fukushima accidents. Post Fukushima arguments for nuclear energy should concentrate on the features which give it a secure place in the 21st century energy strategy, with highest safety standards understood. Its modern relevance comes from the, at present, unique ability, independent on external conditions, to produce large amounts of energy without emission of carbon dioxide. How long will this unique position last cannot be predicted with precision, but from the dynamics of their developments, large scale CCS is unlikely to be available before 2060/65 and nuclear fusion later still. We discuss the feasibility and desirability of the future without nuclear energy. Our recent study (EP 2010) has shown that nuclear energy, even subject to stringent safety and technology constraints, can give substantial contribution to carbon emission reduction until 2065, thus providing time for a large scale introduction of renewable sources, CCS and possibly nuclear fusion. Maximum nuclear strategy limited by uranium resources and with conventional reactor technology without reprocessing we assumed in period 2025-2065, would contribute in 2065 with about 25.2 Gt CO 2 emission reduction, respectively with 39% of the reduction needed to reduce emission from business as usual strategy (WEO 2009) to the level required to limit global temperature increase below 2 0 C. Remaining reduction of 38.4 Gt C0 2 eq

A Giant Step for Developing Countries, Lessons Learned from Feasibility Studies

Energy Technology Data Exchange (ETDEWEB)

Lee, Byoung Youp [Korea Hydro and Nuclear Power, Seoul (Korea, Republic of); Cho, Young Gon [Sanamyung Univ., Seoul (Korea, Republic of)

2014-05-15

According to the IAEA(International Atomic Energy Agency, hereinafter 'IAEA') research, the booming trend of nuclear renaissance among developing countries have initiated to investigate economic feasibility studies regarding future electricity demand and supply for the introduction of nuclear power generation in massive volume. Although the ambitious dream of public servants in the third nations who desperately want to instill nuclear power generation capacity promising generation abundance in their homeland, it is not easy to calculate economic benefits and its related costs where lots of blurred areas could not defined in plain terminology. For this reason, IAEA urges the new entrant countries should prepare carefully and design cautiously not to deter large lump sum nuclear power plant construction project. Nuclear power generation in civil area can be seen as righteous peaceful usage of nuclear energy in appropriate manner, although the advanced technology, capital intensive characteristics would hinder for the developing countries to implement proper scheduled ambitious nuclear power projects in timely course. In particular, the complicated economic feasibility studies are major tasks for poverty struck sovereigns to fulfill their ambitions. Thus further detailed design might be requested in order to relieve international concerns on possible military usage. This article is exploring to gauge multiple aspects of peaceful usage of nuclear energy and its economic benefits which allow power huger nations to achieve sustainable development and make significant advancement.

Feasible research on VLLW disposal in control area of nuclear installation

International Nuclear Information System (INIS)

Kong Jinsong; Guo Weiqun

2013-01-01

Based on the basic requirements on the VLLW landfill disposal specified by the national codes and standards, a on-site disposal of VLLW in the control area of nuclear installation was proposed. A detail analysis of the advantages and disadvantages about the disposal method and the problem to be solved were described. Results showed that the on-site disposal of VLLW in the control area of nuclear installation was feasible in practice. (authors)

Feasibility study of the IE-SASW method for nondestructive evaluation of containment building structures in nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Kim, D.S. E-mail: dskim@kaist.ac.kr; Kim, H.W. E-mail: hwk@kaist.ac.kr; Seo, W.S.; Choi, K.C.; Woo, S.K

2003-02-01

The IE-SASW method, a combination of impact-echo (IE) acoustics with spectral analysis of surface waves (SASW), is proposed as a newly developed nondestructive testing method in concrete structures. This feasibility study examines the IE technique and uses elastic P-wave velocity data as measured from the SASW method on concrete members in nuclear power plant containment structures. It was shown that both the thickness of the concrete specimens used in this study and the depth of the introduced defects (i.e. voids) could be identified by the IE-SASW method. In contrast, the reinforced steel bar itself could not be identified by the IE-SASW method. Additionally, GPR (ground penetrating radar) techniques were used to examine the same specimens in order to establish some level of performance and reliability to compare with the performance of the IE-SASW method. The GPR method provides an objective and reliable image corresponding to the reinforced steel bars. The experimental studies show that it is more feasible to use the IE-SASW method rather than GPR to detect voids that were positioned beneath the steel reinforcing bars in the concrete specimens.

Feasibility of Low Enriched Uranium Fuel for Space Nuclear Propulsion

Energy Technology Data Exchange (ETDEWEB)

Venneri, Paolo; Kim, Yonghee [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

2013-05-15

The purpose of this initial study is to create a baseline with which to perform further analysis and to build a solid understanding of the neutronic characteristics of a solid core for the nuclear thermal rocket. Once consistency with work done at Idaho National Laboratory (INL) is established, this paper will provide a study of other fuel types, such as low and medium-enriched uranium fuels. This paper will examine how the implementation of each fuel type affects the multiplication factor of the reactor, and will then explore different possibilities for alterations needed to accommodate their successful usage. The reactor core analysis was done using the MCNP5 code. While this study has not shown that the SNRE can be easily retrofitted for low-enriched U fuel, it has made a detailed study of the SNRE, and identified the difficulties of the implementation of low-enriched fuels in small nuclear rockets. These difficulties are the need for additional moderation and fuel mass in order to achieve a critical mass. Neither of these is insurmountable. Future work includes finding the best method by which to increase the internal moderation of the reactor balanced with appropriate sizing to prevent neutron leakage. Both of these are currently being studied. This paper will present a study of the Small Nuclear Rocket Engine (SNRE) and the feasibility of using low enriched Uranium (LEU) instead of the traditional high enriched Uranium (HEU) fuels.

Feasibility study on small modular reactors for modern microgrids

Energy Technology Data Exchange (ETDEWEB)

Islam, R.; Gabbar, H.A., E-mail: hossam.gabbar@uoit.ca [Univ. of Ontario Inst. of Technology, Faculty of Energy Systems and Nuclear Science, Oshawa, Ontario (Canada)

2013-07-01

Microgrid is a solution of conventional power grid problem and offer sustainable decentralized power system. Microgrid with modern distributed energy resources (DER) could play an important role to alleviate dependency on the main electricity grid. Distributed energy resource comprises wind turbine, solar photovoltaic, diesel generator, gas engine, micro turbine, fuel cells, etc.Due to the gap between typical loads and supply within microgrid, larger scale energy generation could provide a possible solution to balance power demand and supply. Feasibility study of Small Nuclear Power Plant, such as Small Modular reactor (SMR), within microgrids could be achieved via different cases. To achieve the target, a comprehensive feasibility study is conducted on microgrid with SMR through electricity generation profiles, geographical and environmental assessment, as well as cost analysis using simulation practices and data analysis.Also potency of SMRs is analyzed. Parameters and Key Performance Indicators (KPIs) could be analyzed to achieve feasible solution of microgrids with small modular reactor (SMR) to improve the overall microgrid performance.The study shows that SMR could be a feasible solution if microgrid parameters are selected properly. (author)

Feasibility study on small modular reactors for modern microgrids

International Nuclear Information System (INIS)

Islam, R.; Gabbar, H.A.

2013-01-01

Microgrid is a solution of conventional power grid problem and offer sustainable decentralized power system. Microgrid with modern distributed energy resources (DER) could play an important role to alleviate dependency on the main electricity grid. Distributed energy resource comprises wind turbine, solar photovoltaic, diesel generator, gas engine, micro turbine, fuel cells, etc.Due to the gap between typical loads and supply within microgrid, larger scale energy generation could provide a possible solution to balance power demand and supply. Feasibility study of Small Nuclear Power Plant, such as Small Modular reactor (SMR), within microgrids could be achieved via different cases. To achieve the target, a comprehensive feasibility study is conducted on microgrid with SMR through electricity generation profiles, geographical and environmental assessment, as well as cost analysis using simulation practices and data analysis.Also potency of SMRs is analyzed. Parameters and Key Performance Indicators (KPIs) could be analyzed to achieve feasible solution of microgrids with small modular reactor (SMR) to improve the overall microgrid performance.The study shows that SMR could be a feasible solution if microgrid parameters are selected properly. (author)

Cogeneration feasibility study in the Gulf States Utilities service area

Energy Technology Data Exchange (ETDEWEB)

1979-12-01

Sites in the Gulf States Utilities service are considered for cogeneration feasibility studies. The sources of steam considered for the Orange, Texas and Geismar, Lake Charles, and North Baton Rouge, Louisiana sites include oil, coal, HTGR steamers, consolidated nuclear steam system, atmospheric fluidized-bed coal combustion, and coal gasification. Concepts concerning cogeneration fuel systems were categorized by technical applicability as: current technology (pulverized coal-fired boilers and fuel oil-fired boilers), advanced technology under development (HTGR steamers and the CNSS), and advanced technology for future development (atmospheric fluidized-bed boilers and coal gasification). In addition to providing data on cogeneration plant generally useful in the US, the study determined the technical and economic feasibility of steam and electric power cogeneration using coal and nuclear fuels for localized industrial complexes. Details on site selection, plant descriptions, cost estimates, economic analysis, and plant schedule and implementation. (MCW)

Decommissioning of nuclear facilities. Feasibility, needs and costs

International Nuclear Information System (INIS)

1986-01-01

Reactor decommissioning activities generally are considered to begin after operations have ceased and the fuel has been removed from the reactor, although in some countries the activities may be started while the fuel is still at the reactor site. The three principal alternatives for decommissioning are described. The factors to be considered in selecting the decommissioning strategy, i.e. a stage or a combination of stages that comprise the total decommissioning programme, are reviewed. One presents a discussion of the feasibility of decommissioning techniques available for use on the larger reactors and fuel cycle facilities. The numbers and types of facilities to be decommissioned and the resultant waste volumes generated for disposal will then be projected. Finally, the costs of decommissioning these facilities, the effect of these costs on electricity generating costs, and alternative methods of financing decommissioning are discussed. The discussion of decommissioning draws on various countries' studies and experience in this area. Specific details about current activities and policies in NEA Member Countries are given in the short country specific Annexes. The nuclear facilities that are addressed in this study include reactors, fuel fabrication facilities, reprocessing facilities, associated radioactive waste storage facilities, enrichment facilities and other directly related fuel cycle support facilities. The present study focuses on the technical feasibility, needs, and costs of decommissioning the larger commercial facilities in the OECD member countries that are coming into service up to the year 2000. It is intended to inform the public and to assist in planning for the decommissioning of these facilities

Evaluation of the feasibility, economic impact, and effectiveness of underground nuclear power plants. Final technical report

International Nuclear Information System (INIS)

1978-05-01

Information on underground nuclear power plants is presented concerning underground nuclear power plant concepts; public health impacts; technical feasibility of underground concepts; economic impacts of underground construction; and evaluation of related issues

A study on the feasibility of environmental impacts assessment for Wolsung nuclear 3 and 4 - Ecology, population and socio-economic environment

Energy Technology Data Exchange (ETDEWEB)

Kang, Ho; Lee, Jin Hong; Hong, Seong Soo [Chungnam National Univ., Taejon (Korea, Republic of)] (and others)

1993-09-15

It is necessary to study persistently methodology and all relevant information for environmental impacts assessment, which will make the assessment be more effective. The contents and scope of this project are summarized as follows : review on the feasibility of the overall environmental status surveyed at the vicinity of the proposed nuclear power plants, review on the assessment of the probable impacts, review on the potential of alternatives to minimize the adverse impacts on the surrounding environments.

The Results of Feasibility Study of Co-generation NPP With Innovative VK-300 Simplified Boiling Water Reactor

International Nuclear Information System (INIS)

Kuznetsov, Yury N.

2006-01-01

The co-generation nuclear power plant (CNPP) producing electricity and district heating heat is planned to be constructed in Archangelsk Region of Russia. Following the 'Letter of Intent' signed by Governor of Archangelsk region and by Minister of the Russian Federation for atomic energy the feasibility study of the Project has been done. The NPP will be based on the four co-generation nuclear power units with the Russian VK-300 SBWR. The innovative passive VK-300 reactor facility has been designed on the basis of well-established nuclear technologies, proven major components, the operating experience of the prototype VK-50 reactor in RIAR, Dimitrovgrad, and the experience in designing such reactors as SBWR (GE) and SWR-1000 (Siemens). The CNPP's total power is planned to be 1000 MW(e) and district-heating heat production capacity 1600 Gcal/h. A detailed description of the results of the feasibility study is presented in the report. The results of the feasibility study have shown that the Archangelsk CGNP is feasible in terms of engineering, economics and production. (authors)

The results of feasibility study of co-generation NPP with innovative VK-300 simplified boiling water reactor

International Nuclear Information System (INIS)

Kuznetsov, Yu. N.; Gabaraev, B. A.

2004-01-01

The co-generation nuclear power plant (CNPP) producing electricity and district-heating heat is planned to be constructed in Archangelsk Region of Russia. Following the Letter of Intent signed by Governor of Archangelsk region and by Minister of the Russian Federation for atomic energy the feasibility study of the Project has been done. The NPP will be based on the four co-generation nuclear power units with the Russian VK-300 SBWR. The innovative passive VK-300 reactor facility has been designed on the basis of well-established nuclear technologies, proven major components, the operating experience of the prototype VK-50 reactor in RIAR, Dimitrovgrad, and the experience in designing such reactors as SBWR (GE) and SWR-1000 (Siemens). The CNPP's total power is planned to be 1000 MW(e) and district-heating heat production capacity 1600 Gcal /h. A detailed description of the results of the feasibility study is presented in the report. The results of the feasibility study have shown that the Archangelsk CGNP is feasible in terms of engineering, economics and production.(author)

INCOGEN pre-feasibility study. Nuclear cogeneration

Energy Technology Data Exchange (ETDEWEB)

Van Heek, A.I.; De Haas, J.B.M.; Hogenbirk, A.; Klippel, H.T.; Kuijper, J.C.; Schram, R. [Netherlands Energy Research Foundation ECN, Petten (Netherlands); Hoogenboom, J.E.; Valko, J. [Interfaculty Reactor Institute IRI, Delft (Netherlands); Kanij, J.B.W.; Eendebak, B.T.; De Groot, P.C.; De Kler, R.C.F.; Stempniewicz, M.M. [KEMA, Arnhem (Netherlands); Van Dijk, A.B.; Bredman, B.; Van Essen, D.; Holtz, E.; Op `t Veld, R.; Tjemmes, J.G. [Stork Nucon, Amsterdam (Netherlands); Crommelin, G.A.K.; Crommelin-de Jonge, M.T. [eds.] [ROMAWA, Voorschoten (Netherlands)

1997-09-01

The Netherlands Programme to Intensify Nuclear Competence (PINK, abbreviated in Dutch) supported the technical and economical evaluation of a direct cycle High Temperature Reactor (HTR) installation for combined heat and power generation. This helium cooled, graphite moderated HTR based on the German HTR-M, is named INCOGEN (Inherently safe Nuclear COGENeration). The INCOGEN reference is a 40 MW HTR design by the US company Longmark Power International (LPI). The energy conversion system comprises a single-shaft helium turbine-compressor (2.3-1.0 MPa) directly coupled with a 16.5 MW generator, a recuperator and low-temperature (150C to 40C) heat exchangers (23 MW). Spherical fuel elements (60 mm diameter) will be added little by little, which keeps the core only marginally critical. Void core volume can accommodate added fuel for several years until defuelling. Analyses of failure scenarios (loss of coolant accident or LOCA, loss of flow accident or LOFA, anticipated transient without scram or ATWS) show no excess of maximum acceptable fuel temperature of 1600C. Scoping analyses indicate no severe graphite fires. Transient analyses of the turbine-compressor system indicate adequate control flexibility. Optimization and endurance testing of the helium turbine-compressor is recommended.

Feasibility of waste to Bio-diesel production via Nuclear-Biomass hybrid model. System dynamics analysis

International Nuclear Information System (INIS)

Nam, Hoseok; Kasada, Ryuta; Konishi, Satoshi

2017-01-01

Nuclear-Biomass hybrid system which takes waste biomass from municipal, agricultural area, and forest as feedstock produces Bio-diesel fuel from synthesis gas generated by endothermic pyrolytic gasification using high temperature nuclear heat. Over 900 degree Celsius of exterior thermal heat from nuclear reactors, Very High Temperature Reactor (VHTR) and some other heat sources, bring about waste biomass gasification to produce maximum amount of chemical energy from feedstock. Hydrogen from Biomass gasification or Bio-diesel as the product of Fischer-Tropsch reaction following it provide fuels for transport sector. Nuclear-Biomass hybrid system is a new alternatives to produce more energy generating synergy effects by efficiently utilizing the high temperature heat from nuclear reactor that might be considerably wasted by thermal cycle, and also energy loss from biomass combustion or biochemical processes. System Dynamics approach is taken to analyze low-carbon synthesis fuel, Bio-diesel, production with combination of carbon monoxide and hydrogen from biomass gasification. Feedstock cost considering collection, transportation, storage and facility for biomass gasification impacts the economic feasibility of this model. This paper provides the implication of practical nuclear-biomass hybrid system application with feedstock supply chain through evaluation of economic feasibility. (author)

Feasibility study about Nuclear Center of the National Commission of Nuclear Energy

International Nuclear Information System (INIS)

1984-01-01

This study is mainly about of investments, financing evaluation of the Profitability, RU-2 Reactor and partnership laboratories; work of the RU-2, control systems and security, refrigeration system and treatment of water, irradiation devices and experimental facilities, Building of the reactor, Organization and human resources, Plant of radioisotopes Production, Radiological Protection and Nuclear Security, Location

Depleted uranium concrete container feasibility study

International Nuclear Information System (INIS)

Haelsig, R.T.

1994-09-01

The purpose of this report is to consider the feasibility of using containers constructed of depleted uranium aggregate concrete (DUCRETE) to store and transport radioactive materials. The method for this study was to review the advantages and disadvantages of DUCRETE containers considering design requirements for potential applications. The author found that DUCRETE is a promising material for onsite storage containers, provided DUCRETE vessels can be certified for one-way transport to disposal sites. The author also found that DUCRETE multipurpose spent nuclear fuel storage/transport packages are technically viable, provided altered temperature acceptance limits can be developed for DUCRETE

INTEC High-Level Waste Studies Universal Solvent Extraction Feasibility Study

International Nuclear Information System (INIS)

Banaee, J.; Barnes, C.M.; Battisti, T.; Herrmann, S.; Losinski, S.J.; McBride, S.

2000-01-01

This report summarizes a feasibility study that has been conducted on the Universal Solvent Extraction (UNEX) Process for treatment and disposal of 4.3 million liters of INEEL sodium-bearing waste located at the Idaho Nuclear Technology and Engineering Center. This feasibility study covers two scenarios of treatment. The first, the UNEX Process, partitions the Cs/Sr from the SBW and creates remote-handled LLW and contact-handled TRU waste forms. Phase one of this study, covered in the 30% review documents, dealt with defining the processes and defining the major unit operations. The second phase of the project, contained in the 60% review, expanded on the application of the UNEX processes and included facility requirements and definitions. Two facility options were investigated for the UNEX process, resulting in a 2 x 2 matrix of process/facility scenarios as follows: Option A, UNEX at Greenfield Facility, Option B, Modified UNEX at Greenfield Facility, Option C, UNEX at NWCF, th is document, covers life-cycle costs for all options presented along with results and conclusions determined from the study

Feasibility study for adding a demand failure data collection system to the Nuclear Plant Reliability Data System. Final report

International Nuclear Information System (INIS)

Tashjian, B.M.; Logan, B.W.

1983-07-01

Southwest Research Institute (SwRI) is pleased to submit to Sandia National Laboratories this technical report as fulfillment of Task 5 of the proposal entitled A Feasibility Study for Adding a Duty Cycle Data Collection System to the Nuclear Plant Reliability Data System. The purpose of this report is to summarize the work as delineated in the proposal tasks and to recommend follow-on activities. Technical support for this work was provided by Duke Power Company (Duke), subcontractor to SwRI. The four tasks to be performed in conjunction with the Duty Cycle Data Collection Study (renamed in this report Demand Data Collection) were: define component population and measurable parameters; develop data collection and assessment methodologies; assess the impact on utilities; and assess the impact on NPRDS

A feasibility study for a one-megawatt pulsed spallation source at Los Alamos National Laboratory

International Nuclear Information System (INIS)

Pynn, R.

1994-01-01

Over the past two decades, high-intensity proton accelerators have been designed and developed to support nuclear physics research and defense applications. This technology has now matured to the point where it can support simultaneous and cost-effective exploitation of a number of important areas of both basic and applied science. Examples include neutron scattering, the production of radioisotopes, tests of technologies to transmute nuclear waste, radiation damage studies, nuclear physics, and muon spin research. As part of a larger program involving these and other areas, a team at Los Alamos National Laboratory has undertaken a feasibility study for a 1-MW pulsed spallation neutron source (PSS) based on the use of an 800-MeV proton linac and an accumulator ring. In January 1994, the feasibility study was reviewed by a large, international group of experts in the design of accelerators and neutron spallation targets. This group confirmed the viability of the proposed neutron source. In this paper, I describe the approach Los Alamos has taken to the feasibility study, which has involved a synergistic application of the Laboratory's expertise in nuclear science and technology, computation, and particle-beam technologies. Several examples of problems resolved by the study are described, including chopping of low-energy proton beam, interactions between H - particles and the stripper foil used to produce protons for injection into an accumulator ring, and the inclusion of engineering realities into the design of a neutron production target. These examples are chosen to illustrate the breadth of the expertise that has been brought to bear on the feasibility study and to demonstrate that there are real R ampersand D issues that need to be resolved before a next-generation spoliation source can be built

Feasibility study of component risk ranking for plant maintenance

International Nuclear Information System (INIS)

Ushijima, Koji; Yonebayashi, Kenji; Narumiya, Yoshiyuki; Sakata, Kaoru; Kumano, Tetsuji

1999-01-01

Nuclear power is the base load electricity source in Japan, and reduction of operation and maintenance cost maintaining or improving plant safety is one of the major issues. Recently, Risk Informed Management (RIM) is focused as a solution. In this paper, the outline regarding feasibility study of component risk ranking for plant maintenance for a typical Japanese PWR plant is described. A feasibility study of component risk raking for plant maintenance optimization is performed on check valves and motor-operated valves. Risk ranking is performed in two steps using probabilistic analysis (quantitative method) for risk ranking of components, and deterministic examination (qualitative method) for component review. In this study, plant components are ranked from the viewpoint of plant safety / reliability, and the applicability for maintenance is assessed. As a result, distribution of maintenance resources using risk ranking is considered effective. (author)

Gas core nuclear rocket feasibility project

International Nuclear Information System (INIS)

Howe, S.D.; DeVolder, B.; Thode, L.; Zerkle, D.

1997-09-01

The next giant leap for mankind will be the human exploration of Mars. Almost certainly within the next thirty years, a human crew will brave the isolation, the radiation, and the lack of gravity to walk on and explore the Red planet. However, because the mission distances and duration will be hundreds of times greater than the lunar missions, a human crew will face much greater obstacles and a higher risk than those experienced during the Apollo program. A single solution to many of these obstacles is to dramatically decrease the mission duration by developing a high performance propulsion system. The gas core nuclear rocket (GCNR) has the potential to be such a system. The gas core concept relies on the use of fluid dynamic forces to create and maintain a vortex. The vortex is composed of a fissile material which will achieve criticality and produce high power levels. By radiatively coupling to the surrounding fluids, extremely high temperatures in the propellant and, thus, high specific impulses can be generated. The ship velocities enabled by such performance may allow a 9 month round trip, manned Mars mission to be considered. Alternatively, one might consider slightly longer missions in ships that are heavily shielded against the intense Galactic Cosmic Ray flux to further reduce the radiation dose to the crew. The current status of the research program at the Los Alamos National Laboratory into the gas core nuclear rocket feasibility will be discussed

Planning study and economic feasibility for extended life operation of light water reactor plants

International Nuclear Information System (INIS)

Negin, C.A.; Goudarzi, L.A.; Kenworthy, L.U.; Lapides, M.E.

1980-01-01

The purpose of this planning study was to perform an assessment of the engineering and economic feasibility of extended life operation of present nuclear power plant units and to recommend future programs that may be warranted by the feasibility assessments. This effort concludes, essentially, that there is sufficient economic motivation for refurbishment to warrant more extensive examination for present plants and to identify possible design modifications that would facilitate extended service life in future plants. The costs of replacing the deterioration-prone equipment in a nuclear power plant appear to represent a small portion of the total plant costs, provided downtime is not excessive. A refurbishment and economic analysis is presented

Assessment of the advantages and feasibility of a nuclear rocket

International Nuclear Information System (INIS)

Howe, S.D.

1985-01-01

The feasibility of rebuilding and testing a nuclear thermal rocket (NTR) for the Mars mission has been investigated. Calculations indicate that an NTR would substantially reduce the earth-orbit assembled mass compared to LOX/LH 2 systems. The mass savings were 36% and 65% for the cases of total aerobraking and of total propulsive braking respectively. Consequently, the cost savings for a single mission of using an NTR, if aerobraking is feasible, are probably insufficient to warrant the NTR development. If multiple missions are planned or if propulsive braking is desired at Mars and/or at Earth, then the savings of about $7B will easily pay for the NTR development. Estimates of the cost of rebuilding a NTR were based on the previous NERVA program's budget plus additional costs to develop a flight ready engine. The total cost to build the engine would be between $4 to 5B. The concept of developing a full-power test stand at Johnston Atoll in the Pacific appears very feasible. The added expense of building facilities on the island should be less than $1.4B

Thermal hydraulic feasibility assessment of the spent nuclear fuel project

International Nuclear Information System (INIS)

Heard, F.J.

1996-01-01

A series of analyses have been completed investigating the thermal-hydraulic performance and feasibility of the Spent Nuclear Fuel Project (SNFP) Integrated Process Strategy (IPS). The goal was to develop a series of thermal-hydraulic models that could respond to all process and safety related issues that may arise pertaining to the SNFP, as well as provide a basis for validation of the results. Results show that there is a reasonable envelope for process conditions and requirements that are thermally and hydraulically acceptable

Feasibility Study for Cobalt Bundle Loading to CANDU Reactor Core

International Nuclear Information System (INIS)

Park, Donghwan; Kim, Youngae; Kim, Sungmin

2016-01-01

CANDU units are generally used to produce cobalt-60 at Bruce and Point Lepreau in Canada and Embalse in Argentina. China has started production of cobalt-60 using its CANDU 6 Qinshan Phase III nuclear power plant in 2009. For cobalt-60 production, the reactor’s full complement of stainless steel adjusters is replaced with neutronically equivalent cobalt-59 adjusters, which are essentially invisible to reactor operation. With its very high neutron flux and optimized fuel burn-up, the CANDU has a very high cobalt-60 production rate in a relatively short time. This makes CANDU an excellent vehicle for bulk cobalt-60 production. Several studies have been performed to produce cobalt-60 using adjuster rod at Wolsong nuclear power plant. This study proposed new concept for producing cobalt-60 and performed the feasibility study. Bundle typed cobalt loading concept is proposed and evaluated the feasibility to fuel management without physics and system design change. The requirement to load cobalt bundle to the core was considered and several channels are nominated. The production of cobalt-60 source is very depend on the flux level and burnup directly. But the neutron absorption characteristic of cobalt bundle is too high, so optimizing design study is needed in the future

Feasibility Study for Cobalt Bundle Loading to CANDU Reactor Core

Energy Technology Data Exchange (ETDEWEB)

Park, Donghwan; Kim, Youngae; Kim, Sungmin [KHNP Central Research Institute, Daejeon (Korea, Republic of)

2016-10-15

CANDU units are generally used to produce cobalt-60 at Bruce and Point Lepreau in Canada and Embalse in Argentina. China has started production of cobalt-60 using its CANDU 6 Qinshan Phase III nuclear power plant in 2009. For cobalt-60 production, the reactor’s full complement of stainless steel adjusters is replaced with neutronically equivalent cobalt-59 adjusters, which are essentially invisible to reactor operation. With its very high neutron flux and optimized fuel burn-up, the CANDU has a very high cobalt-60 production rate in a relatively short time. This makes CANDU an excellent vehicle for bulk cobalt-60 production. Several studies have been performed to produce cobalt-60 using adjuster rod at Wolsong nuclear power plant. This study proposed new concept for producing cobalt-60 and performed the feasibility study. Bundle typed cobalt loading concept is proposed and evaluated the feasibility to fuel management without physics and system design change. The requirement to load cobalt bundle to the core was considered and several channels are nominated. The production of cobalt-60 source is very depend on the flux level and burnup directly. But the neutron absorption characteristic of cobalt bundle is too high, so optimizing design study is needed in the future.

Feasibility of Electromagnetic Acoustic Evaluation for Quality Test of a Plate-type Nuclear Fuel

International Nuclear Information System (INIS)

Jung, Hyun Kyu; Lee, Yoon Sang; Cheong, Yong Moo

2010-01-01

Most research and test reactors use the nuclear fuel plates which are consisted of a fuel core in aluminum alloy. Recently KAERI signed a deal with the Jordan Atomic Energy Commission to build the research reactor and have to supply the plate-type nuclear fuels. For the demands of world market, KAERI started the research and development of the plate-type fuel elements and endeavored to achieve a localization of fuel fabrication. For the inspection of plate-type fuel elements to be used in Research Reactors, an immersion pulse-echo ultrasonic technique was applied. This inspection was done with water, so a nuclear fuel was immersed to be prone to corrosion and needed to have time and cost due to an additional process. The sample that will be examined within this paper is a non-ferromagnetic material such as aluminum which has a good acousto-elastic property, for an effective inspection of a bond quality for a nuclear fuel under a manufacturing environment. The purpose of this study is to investigate the feasibility of an EMAT technology for an automated inspection of a nuclear fuel without water

Feasibility study of a fission supressed blanket for a tandem-mirror hybrid reactor

International Nuclear Information System (INIS)

Moir, R.W.; Lee, J.D.; Barr, W.L.

1981-01-01

A study of fission suppressed blankets for the tandem mirror not only showed such blankets to be feasible but also to be safer than fissioning blankets. Such hybrids could produce enough fissile material to support up to 17 light water reactors of the same nuclear power rating. Beryllium was compared to 7 Li for neutron multiplication; both were considered feasible but the blanket with Li produced 20% less fissile fuel per unit of nuclear power in the reactor. The beryllium resource, while possibly being too small for extensive pure fusion application, would be adequate (with carefully planned industrial expansion) for the hybrid because of the large support ratio, and hence few hybrids required. Radiation damage and coatings for beryllium remain issues to be resolved by further study and experimentation. Molten salt reprocessing was compared to aqueous solution reprocessing

Feasible and realiable ab initio atomistic modeling for nuclear waste management

Energy Technology Data Exchange (ETDEWEB)

Beridze, George

2016-07-01

The studies in this PhD dissertation focus on finding a computationally feasible ab initio methodology which would make the reliable first principle atomistic modeling of nuclear materials possible. Here we tested the performance of the different DFT functionals and the DFT-based methods that explicitly account for the electronic correlations, such as the DFT+U approach, for prediction of structural and thermochemical properties of lanthanide- and actinide-bearing materials. In the previous studies, the value of the Hubbard U parameter, required by the DFT+U method, was often guessed or empirically derived. We applied and extensively tested the recently developed ab initio methods such as the constrained local density approximation (cLDA) and the constrained random phase approximation (cRPA), to compute the Hubbard U parameter values from first principles, thus making the DFT+U method a real it ab initio parameter free approach. Our successful benchmarking studies of the parameter-free DFT+U method, for prediction of the structures and the reaction enthalpies of actinide- and lanthanide-bearing molecular compounds and solids indicate, that the linear response method (cLDA) provides a very good, and consistent with the cRPA prediction, estimate of the Hubbard U parameter. In particular, we found that the Hubbard U parameter value, which describes the strength of the on-site Coulomb repulsion between f-electrons, depends strongly on the oxidation state of the f-element, its local bonding environment and crystalline structure of the materials, which has never been considered in such detail before. We have shown, that the applied computational approach substantially, if not dramatically, reduces the error of the predicted reaction enthalpies making the accuracy of the prediction comparable with the uncertainty of the computational unfeasible, higher order methods of quantum chemistry, and experiments. The derived methodology resulted in various, already published

Feasible and realiable ab initio atomistic modeling for nuclear waste management

International Nuclear Information System (INIS)

Beridze, George

2016-01-01

The studies in this PhD dissertation focus on finding a computationally feasible ab initio methodology which would make the reliable first principle atomistic modeling of nuclear materials possible. Here we tested the performance of the different DFT functionals and the DFT-based methods that explicitly account for the electronic correlations, such as the DFT+U approach, for prediction of structural and thermochemical properties of lanthanide- and actinide-bearing materials. In the previous studies, the value of the Hubbard U parameter, required by the DFT+U method, was often guessed or empirically derived. We applied and extensively tested the recently developed ab initio methods such as the constrained local density approximation (cLDA) and the constrained random phase approximation (cRPA), to compute the Hubbard U parameter values from first principles, thus making the DFT+U method a real it ab initio parameter free approach. Our successful benchmarking studies of the parameter-free DFT+U method, for prediction of the structures and the reaction enthalpies of actinide- and lanthanide-bearing molecular compounds and solids indicate, that the linear response method (cLDA) provides a very good, and consistent with the cRPA prediction, estimate of the Hubbard U parameter. In particular, we found that the Hubbard U parameter value, which describes the strength of the on-site Coulomb repulsion between f-electrons, depends strongly on the oxidation state of the f-element, its local bonding environment and crystalline structure of the materials, which has never been considered in such detail before. We have shown, that the applied computational approach substantially, if not dramatically, reduces the error of the predicted reaction enthalpies making the accuracy of the prediction comparable with the uncertainty of the computational unfeasible, higher order methods of quantum chemistry, and experiments. The derived methodology resulted in various, already published

Feasibility studies and technological innovation

DEFF Research Database (Denmark)

Hvelplund, Frede Kloster; Lund, Henrik; Sukkumnoed, Decharut

2004-01-01

The chapter offers a tool to conduct feasibility studies and focuses on how to make feasibility studies in a situation with environmental concerns, in which technological innovation and institutional chnages are among the objectives.......The chapter offers a tool to conduct feasibility studies and focuses on how to make feasibility studies in a situation with environmental concerns, in which technological innovation and institutional chnages are among the objectives....

Feasibility analysis of aggressive cooldown in OPR-1000 nuclear power plants

International Nuclear Information System (INIS)

Kim, Man Cheol; Jerng, Dong Wook

2014-01-01

Highlights: • We examine the feasibility of aggressive cooldown, particularly in OPR-1000 plants. • We review experimental and simulation results, EOPs, and time estimates. • Aggressive cooldown is, in general, expected to be performed successfully. • There is potential for failure to initiate aggressive cooldown in a timely manner. • Investigation on allowing higher cooldown rate in OPR-1000 plants is recommended. - Abstract: Aggressive cooldown is the action taken by main control room (MCR) operators to rapidly cool down and depressurize the reactor coolant system at the maximum allowed cooldown rate during a small break loss of coolant accident (SBLOCA) or a steam generator tube rupture accident with failure of high-pressure safety injection (HPSI) in a pressurized water reactor. We examined the feasibility of aggressive cooldown in OPR-1000 nuclear power plants by establishing success criteria based on experimental results and thermal–hydraulic code simulations, reviewing emergency operating procedures, and estimating the necessary time for MCR operators to initiate aggressive cooldown based on experimental results with licensed nuclear power plant operators. For an SBLOCA with a break size of 0.02 ft 2 combined with total failure of HPSI, we found that aggressive cooldown can generally be performed successfully, but there is potential for failure to initiate aggressive cooldown in a timely manner. We discuss the potential effects of introducing the Ultimate Procedure on reducing the core damage potential. Detailed analysis and further discussion are necessary to reduce uncertainties associated with aggressive cooldown and its positive effect on the safety of nuclear power plants

Feasibility study of fusion breeding blanket concept employing graphite reflector

International Nuclear Information System (INIS)

Cho, Seungyon; Ahn, Mu-Young; Lee, Cheol Woo; Kim, Eung Seon; Park, Yi-Hyun; Lee, Youngmin; Lee, Dong Won

2015-01-01

Highlights: • A Helium-Cooled Ceramic Reflector (HCCR) breeding blanket concept adopts graphite as a reflector material by reducing the amount of beryllium multiplier. • Its feasibility was investigated in view point of the nuclear performance as well as material-related issues. • A nuclear analysis is performed under the fusion reactor condition to address the feasibility of graphite reflector in breeding blanket. • Also, the chemical stability of the graphite is investigated considering the chemical stability under accident conditions. • In conclusion, the adaptation of graphite reflector in breeding blanket is intrinsically safe and plausible under fusion reactor condition. - Abstract: To obtain high tritium breeding performance with limited blanket thickness, most of solid breeder blanket concepts employ a combination of lithium ceramic as a breeder and beryllium as a multiplier. In this case, considering that huge amount of beryllium are needed in fusion power plants, its handling difficulty and cost can be a major factor to be accounted for commercial use. Korea has proposed a Helium-Cooled Ceramic Reflector (HCCR) breeding blanket concept relevant to fusion power plants. Here, graphite is used as a reflector material by reducing the amount of beryllium multiplier. Its feasibility has been investigated in view point of the nuclear performance as well as material-related issues. In this paper, a nuclear analysis is performed under the fusion reactor condition to address the feasibility of graphite reflector in breeding blanket, considering tritium breeding capability and neutron shielding and activation aspects. Also, the chemical stability of the graphite is investigated considering the chemical stability under accident conditions, resulting in that the adaptation of graphite reflector in breeding blanket is intrinsically safe and plausible under fusion reactor condition.

Feasibility study of fusion breeding blanket concept employing graphite reflector

Energy Technology Data Exchange (ETDEWEB)

Cho, Seungyon, E-mail: sycho@nfri.re.kr [National Fusion Research Institute, Daejeon (Korea, Republic of); Ahn, Mu-Young [National Fusion Research Institute, Daejeon (Korea, Republic of); Lee, Cheol Woo; Kim, Eung Seon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Park, Yi-Hyun; Lee, Youngmin [National Fusion Research Institute, Daejeon (Korea, Republic of); Lee, Dong Won [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2015-10-15

Highlights: • A Helium-Cooled Ceramic Reflector (HCCR) breeding blanket concept adopts graphite as a reflector material by reducing the amount of beryllium multiplier. • Its feasibility was investigated in view point of the nuclear performance as well as material-related issues. • A nuclear analysis is performed under the fusion reactor condition to address the feasibility of graphite reflector in breeding blanket. • Also, the chemical stability of the graphite is investigated considering the chemical stability under accident conditions. • In conclusion, the adaptation of graphite reflector in breeding blanket is intrinsically safe and plausible under fusion reactor condition. - Abstract: To obtain high tritium breeding performance with limited blanket thickness, most of solid breeder blanket concepts employ a combination of lithium ceramic as a breeder and beryllium as a multiplier. In this case, considering that huge amount of beryllium are needed in fusion power plants, its handling difficulty and cost can be a major factor to be accounted for commercial use. Korea has proposed a Helium-Cooled Ceramic Reflector (HCCR) breeding blanket concept relevant to fusion power plants. Here, graphite is used as a reflector material by reducing the amount of beryllium multiplier. Its feasibility has been investigated in view point of the nuclear performance as well as material-related issues. In this paper, a nuclear analysis is performed under the fusion reactor condition to address the feasibility of graphite reflector in breeding blanket, considering tritium breeding capability and neutron shielding and activation aspects. Also, the chemical stability of the graphite is investigated considering the chemical stability under accident conditions, resulting in that the adaptation of graphite reflector in breeding blanket is intrinsically safe and plausible under fusion reactor condition.

Feasibility of evacuation

International Nuclear Information System (INIS)

1988-01-01

The main question is whether evacuation of people is feasible in case of accidents with a nuclear power plant. The limiting conditions of this question are extracted from other studies. This study is therefore focused on a postulated accident in a newly built nuclear power plant with an electric capacity of 1000 Megawatt and a source term of one percent. In this particular case an evacuation should take place within the period between the accident and the emission of nuclear materials. Initial focus is on the administrative-organizational aspects of evacuation. Then bottlenecks in the technical implementation of evacuation are determined. An analysis is made for each potential Dutch location (Borssele, Eemshaven, Maasvlakte, Moerdijk and Westelijke Noordoostpolderdijk) of a nuclear power plant. By means of a model the following question is examined: can the population leave the danger area or be evacuated on time, under certain circumstances. It is concluded that preventive evacuation of the population from the planned locations is feasible, but at Moerdijk complications may occur because of the presence of some homes for the elderly and a nursing home. 18 refs.; 7 figs.; 2 tabs

The feasibility study on commercialized fast reactor cycle system

International Nuclear Information System (INIS)

Noda, Hiroshi

2002-01-01

The feasibility study on commercialized Fast Reactor cycle system (FS) has been carried out by a joint team with the participation of all parties concerned in Japan since July, 1999. It aims to clarify various perspectives for commercialized fast reactor cycle system and also suggest development strategies to diverse social needs in the 21 st century. The FS consists of several phases. The phase 1 has progressed as planned and the highly feasible candidate concepts with innovative technologies have been screened out among a wide variety of concepts. During the phase 2, approximately five years after the phase 1, the in-depth design studies and engineering scale tests of key technologies are being conducted to verify and validate the feasibility of screened candidate concepts. At the end of the phase 2, a few promising concepts will be selected with their R and D tasks. The paper describes the results of the phase 1, the activities of the phase 2 and the new concept related to the fast reactor fuel cycle focusing on the reduction in environmental burden, which is one of key factors to sustain the nuclear power generation in the 21 st century

Feasibility study for siting of a deep repository within the Storuman municipality

International Nuclear Information System (INIS)

1995-01-01

It is SKB's task to gather a broad body of information for the siting of a deep repository for Sweden's spent nuclear fuel and other long-lived radioactive waste. The criteria presented by SKB serve as guidelines for the siting studies. Overviews of siting factors are compiled in general siting studies of all or parts of Sweden. Feasibility studies examine the siting prospects in potentially suitable and interested municipalities. SKB plans to carry out feasibility studies in five to ten municipalities in different parts of the country. General studies and feasibility studies are primarily based on existing material. The feasibility study in Storuman is the first to be conducted. It began during the second half of 1993 with the conclusion of an agreement between the municipality and SKB. SKB has been in charge of the execution of the feasibility study. SKB has been responsible for the summary provided in a status report published in June 1994, as well as for the conclusions and evaluations in this final report. Altogether about 30 reports have been published within the framework of the feasibility study. The purpose of the various studies have been to describe, in as much detail as possible, the prospects for siting a deep repository in the municipality of Storuman, and to shed light on the possible positive and negative consequences of such a siting. The feasibility study has led to a discussion within the municipality and the region concerning the siting of a deep repository. In SKB's opinion, this gives all those concerned ample opportunity to become acquainted with the issues and to assert their interests and present their viewpoints at an early stage. 55 refs

Basic research for nuclear energy. y Study on the nuclear materials technology

Energy Technology Data Exchange (ETDEWEB)

Kuk, I H; Lee, H S; Jeong, Y H; Sung, K W; Han, J H; Lee, J T; Lee, H K; Kim, S J; Kang, H S; An, D H; Kim, K R; Park, S D; Han, C H; Jung, M K; Oh, Y J; Kim, K H; Kim, S H; Back, J H; Kim, C H; Lim, K S; Kim, Y Y; Na, J W; Ku, J H; Lee, D H

1996-12-01

A study on the nuclear materials technologies which are necessary to establish the base for alloy development was performed. - The feasibility study on the application of Zircaloy scrap waste for hydrogen storage - The development of metal hydride battery for energy storage system - The establishment of transmission electron microscopy database for nuclear materials - The basic technology for the development of cladding materials for high burnup - The water chemistry technology for secondary system pH control and the photocatalysis technology for decomposition and removal of organics. - Improvement of primary component integrity of PWR by Zinc injection. (author). 175 refs., 58 tabs., 262 figs.

Basic research for nuclear energy. y Study on the nuclear materials technology

International Nuclear Information System (INIS)

Kuk, I. H.; Lee, H. S.; Jeong, Y. H.; Sung, K. W.; Han, J. H.; Lee, J. T.; Lee, H. K.; Kim, S. J.; Kang, H. S.; An, D. H.; Kim, K. R.; Park, S. D.; Han, C. H.; Jung, M. K.; Oh, Y. J.; Kim, K. H.; Kim, S. H.; Back, J. H.; Kim, C. H.; Lim, K. S.; Kim, Y. Y.; Na, J. W.; Ku, J. H.; Lee, D. H.

1996-12-01

A study on the nuclear materials technologies which are necessary to establish the base for alloy development was performed. - The feasibility study on the application of Zircaloy scrap waste for hydrogen storage - The development of metal hydride battery for energy storage system - The establishment of transmission electron microscopy database for nuclear materials - The basic technology for the development of cladding materials for high burnup - The water chemistry technology for secondary system pH control and the photocatalysis technology for decomposition and removal of organics. - Improvement of primary component integrity of PWR by Zinc injection. (author). 175 refs., 58 tabs., 262 figs

Economic feasibility of heat supply from simple and safe nuclear plants

International Nuclear Information System (INIS)

Tian, J.

2001-01-01

Use of nuclear energy as a heating source is greatly challenged by the economic factor since the nuclear heating reactors have relative small size and often the lower plant load factor. However, use of very simple reactor could be a possible way to economically supply heat. A deep pool reactor (DPR) has been designed for this purpose. The DPR is a novel design of pool type reactor for heat only supply. The reactor core is put in a deep pool. By only putting light static water pressure on the core coolant, the DPR will be able to meet the temperature requirements of heat supply for district heating. The feature of simplicity and safety of DPR makes a decrease of investment cost compared to other reactors for heating only purposes. According to the economical assessments, the capital investment to build a DPR plant is much less than that of a pressurized reactor with pressure vessels. For the DPR with 120 or 200 MW output, it can bear the economical comparison with a usual coal-fired heating plant. Some special means taken in DPR design make an increase of the burn-up level of spent fuel and a decrease of fuel cost. The feasibility studies of DPR in some cities in China show that heating cost using nuclear energy is only one third of that by coal and only one tenth of that by nature gas. Therefore, the DPR nuclear heating system provides an economically attractive solution to satisfy the demands of district heating without contributing to increasing greenhouse gas emissions

Technical economic feasibility study for the implementation of a nuclear power plant for the production of electricity in Colombia; Estudio de factibilidad tecnico economica para la implementacion de una central de energia nuclear para la produccion de energia electrica en Colombia

Energy Technology Data Exchange (ETDEWEB)

Gonzales, David E.; Bolanos, Hernan G.; Mayorga, Manuel A.; Rodriguez, Edwin A., E-mail: david_egO@yahoo.es, E-mail: hernanbolaos@yahoo.com.ar, E-mail: alejo_mayorga@yahoo.com, E-mail: edwin.rodriguez@distoyota.com.co [Escuela Colombiana de Carreras Industriales (ECCI), Bogota (Colombia). Grupo de Investigacion GIATME

2013-07-01

A study on the technical and economic feasibility will be used to implement a nuclear power in Colombia to generate electricity. To this will be searched if there are previous studies on this topic and what they concluded. The manner in which power is supplied will be discussed in a national level nowadays, its strengths and weaknesses. It will be investigated the legal norms that exists in the country on nuclear power and renewable energy sources, the standards established at world level, the nuclear accidents and the great examples. Providers will be sought on the world market nuclear equipment which serve to this purpose and the technical characteristics of these equipment will be discussed. The type of fuel used in nuclear reactors, its origin, method of production, specifications, availability and long-term and safe handling and final disposal are considered. safe handling of this technology and policy or international rules that will studied.

Feasibility study for the installation of a nuclear reactor in thermal stimulation processes in heavy oil extraction from Orinoco oil belt

International Nuclear Information System (INIS)

Munoz, A.; Sanchez, R.

1982-01-01

Due to strategic need in the exploitation of heavy and extraheavy oil wells of Orinoco oil belt, technical and economical studies have been carried out to determine an optimal method for oil production and exploitation. So far, studies indicate thermal stimulation is the most adequate technique. Experience shows that stimulation cost is high when traditional methods (boilers) are used. The profit is due to the high price of oil in international market. Due to actual oil price trends, evaluation of nontraditional methods to generate steam in thermal stimulation processes (steam injection) is in order. A nuclear reactor as steam generator was evaluated. It was found economical feasibility and saving in fuel cost between 31.08% and 72.63% depending on oil prices

Feasibility study for siting of a deep repository within the Storuman municipality

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-01-01

It is SKB`s task to gather a broad body of information for the siting of a deep repository for Sweden`s spent nuclear fuel and other long-lived radioactive waste. The criteria presented by SKB serve as guidelines for the siting studies. Overviews of siting factors are compiled in general siting studies of all or parts of Sweden. Feasibility studies examine the siting prospects in potentially suitable and interested municipalities. SKB plans to carry out feasibility studies in five to ten municipalities in different parts of the country. General studies and feasibility studies are primarily based on existing material. The feasibility study in Storuman is the first to be conducted. It began during the second half of 1993 with the conclusion of an agreement between the municipality and SKB. SKB has been in charge of the execution of the feasibility study. SKB has been responsible for the summary provided in a status report published in June 1994, as well as for the conclusions and evaluations in this final report. Altogether about 30 reports have been published within the framework of the feasibility study. The purpose of the various studies have been to describe, in as much detail as possible, the prospects for siting a deep repository in the municipality of Storuman, and to shed light on the possible positive and negative consequences of such a siting. The feasibility study has led to a discussion within the municipality and the region concerning the siting of a deep repository. In SKB`s opinion, this gives all those concerned ample opportunity to become acquainted with the issues and to assert their interests and present their viewpoints at an early stage. 55 refs.

Feasibility study for an alternative PWR-containment. Stage 3

International Nuclear Information System (INIS)

Eibl, J.

1994-08-01

The following report deals with a feasibility study on a lightwater reactor containment which is oriented at the German 1300 MW Convoy Type reactor. It was the aim of this containment development for a future nuclear ractor to restrict all consequences of an extreme reactor failure exclusively to the interior of the containment. Also the decay heat of the relevant core catchers is provided to be removed by passive means. This containment development was a common project with the Nuclear Research Centre at Karlsruhe (KFK). As a consequence of this intention the concept started from upper physical limits, such as a maximum static pressure of 1,5 MPa at 200 , a global and local detonation pressure of 8,4 MPa at an impulse of 5,0 kPas, an upward directed force exerted by the pressure vessel of 300 MN, a horizontal force exerted by the moving pressure vessel onto its environment of 70 MN, a cavern pressure around the core catcher of 3,0 resp., 2,0 MPa and a steam explosion-energy of 300 MJ. Such a contaiment concept is presented and inverstigated with respect to its feasibility, statically and dynamically in all relevant details including earthquake actions. (orig.) [de

Current status of feasibility studies on commercialized fuel cycle system for Fast Breeder Reactor

International Nuclear Information System (INIS)

Ojima, Hisao; Nagaoki, Yoshihiro

2000-01-01

A 'Feasibility Studies on Commercialized Fast Breeder Reactor Cycle System' is underway at the Japan Nuclear Cycle Development Institute (JNC). The study will select the promising concepts with their R and D tasks in order to commercialize the fast breeder reactor (FBR) cycle system. The feasibility studies (F/S) have to present surveyed and screened various relevant technologies, and defined the design requirement of the commercialized fuel cycle system for FBR. The promising technical options are being evaluated and conceptual designs are being examined. At the end of JFY2000, several candidate concepts of the commercialized FBR cycle system will be proposed. (author)

Feasibility of Ericsson type isothermal expansion/compression gas turbine cycle for nuclear energy use

International Nuclear Information System (INIS)

Shimizu, Akihiko

2007-01-01

A gas turbine with potential demand for the next generation nuclear energy use such as HTGR power plants, a gas cooled FBR, a gas cooled nuclear fusion reactor uses helium as working gas and with a closed cycle. Materials constituting a cycle must be set lower than allowable temperature in terms of mechanical strength and radioactivity containment performance and so expansion inlet temperature is remarkably limited. For thermal efficiency improvement, isothermal expansion/isothermal compression Ericsson type gas turbine cycle should be developed using wet surface of an expansion/compressor casing and a duct between stators without depending on an outside heat exchanger performing multistage re-heat/multistage intermediate cooling. Feasibility of an Ericsson cycle in comparison with a Brayton cycle and multi-stage compression/expansion cycle was studied and technologies to be developed were clarified. (author)

Aging/Systems Interaction Study, Component Residual Lifetime Evaluation and Feasibility of Relicensing. Progress report, FY 1985

International Nuclear Information System (INIS)

Close, J.A.; Jacobs, P.T.; Korth, G.E.; Mudlin, J.M.; Server, W.L.; Spaletta, H.W.

1985-10-01

This report documents the work performed on four research tasks in Fiscal Year 1985 (FY-1985) which were part of the Aging/Systems Interaction Study, Component Residual Lifetime Evaluation and Feasibility of Relicensing Project. The technical and management/institutional objectives for the project are described, followed by a description of the results of each task. The work on Task 1 involved identifying and prioritizing new research activities for the Nuclear Regulatory Commission (NRC) Nuclear Plant Aging Research (NPAR) Program. A proposed methodology and plan for aging-system interaction studies was developed in Task 2. The description of Task 3 work comprises a summary of nuclear plant life extension activities in the US, the technical basis associated with the residual life of metallic materials and a proposed plan for research on residual life assessment. Task 4 describes the initial evaluation of selected Standard Review Plan (NUREG-0800) sections to investigate the feasibility of relicensing. 14 refs., 13 figs., 20 tabs

Case study on the feasibility of small and medium nuclear power plants in Egypt

International Nuclear Information System (INIS)

1994-04-01

The IAEA agreed to co-operate with the Arab Republic of Egypt in performing a case study on the feasibility of small and medium power reactors (SMPRs) as a technical assistance project. The major objective of this study is to examine the feasibility of SMPRs to supply a portion of the future electrical energy requirements in the long term power programme of Egypt. The IAEA is grateful to all who provided information and assisted in the drafting and review of the report, in particular to the Advisory Group which performed the study in a co-operative effort. It is hoped that the report will meet the interests of policy makers, managers, engineers and economists in Member States, particularly in developing countries, and that it will provide a useful basis for specific studies to prepare decisions on SMPR projects. Refs, figs and tabs

Feasibility study of plutonium recycling in light water reactors

International Nuclear Information System (INIS)

Tabuchi, Hideoto

1979-01-01

The feasibility of plutonium recycling in light water reactors has been studied by the Agency of Natural Resources and Energy, MITI. As the first step of the feasibility study, it was planned to charge two fuel assemblies, containing uranium-plutonium mixed oxide (MO 2 ), in the core of the Tsuruga nuclear power plant (BWR) for testing. The design of fuel the safety of these fuel and the operating characteristics of these special fuel assemblies were evaluated. The specifications of MO 2 fuel pin and fuel assembly are compared to those of present uranium oxide (UO 2 ) fuel. The weight of fissile plutonium in one MO 2 fuel assembly is 2.22 kg. The characteristics of MO 2 fuel assemblies, such as reactivity, control rod worth and power distribution can be kept similar to UO 2 fuel. The plutonium isotope ratio of the MO 2 fuel is assumed as that obtained in the fuel taken out of the Tokai No. 1 gas cooled reactor. The temperature distribution in the fuel pellets is shown, compared to that of UO 2 fuel. The linear power density is 440 w/cm at the beginning of the fuel life and 360 w/cm after the burn-up of 44,000 Mwd/t. The stress in the cladding tubes of MO 2 fuel is not different from that of UO 2 fuel. The pellet-cladding interaction (PCM1) was analyzed, utilizing the FEM code, FEAST. Concerning the calculation of resonance absorption, the space dependence of thermal neutron spectra and the nuclear behavior of hollow pellets the methods of design calculation were checked up. It was recognized that regarding the nuclear characteristics of MO 2 fuel, no special technical question remains. (Nakai, Y.)

A feasibility assessment of nuclear reactor power system concepts for the NASA Growth Space Station

Science.gov (United States)

Bloomfield, H. S.; Heller, J. A.

1986-01-01

A preliminary feasibility assessment of the integration of reactor power system concepts with a projected growth Space Station architecture was conducted to address a variety of installation, operational, disposition and safety issues. A previous NASA sponsored study, which showed the advantages of Space Station - attached concepts, served as the basis for this study. A study methodology was defined and implemented to assess compatible combinations of reactor power installation concepts, disposal destinations, and propulsion methods. Three installation concepts that met a set of integration criteria were characterized from a configuration and operational viewpoint, with end-of-life disposal mass identified. Disposal destinations that met current aerospace nuclear safety criteria were identified and characterized from an operational and energy requirements viewpoint, with delta-V energy requirement as a key parameter. Chemical propulsion methods that met current and near-term application criteria were identified and payload mass and delta-V capabilities were characterized. These capabilities were matched against concept disposal mass and destination delta-V requirements to provide a feasibility of each combination.

A feasibility assessment of nuclear reactor power system concepts for the NASA growth Space Station

International Nuclear Information System (INIS)

Bloomfield, H.S.; Heller, J.A.

1986-01-01

A preliminary feasibility assessment of the integration of reactor power system concepts with a projected growth space station architecture was conducted to address a variety of installation, operational, disposition and safety issues. A previous NASA sponsored study, which showed the advantages of space station related concepts, served as the basis for this study. A study methodology was defined and implemented to assess compatible combinations of reactor power installation concepts, disposal destinations, and propulsion methods. Three installation concepts that met a set of integration criteria were characterized from a configuration and operational viewpoint, with end-of-life disposal mass identified. Disposal destinations that met current aerospace nuclear safety criteria were identified and characterized from an operational and energy requirements viewpoint, with delta-V energy requirement as a key parameter. Chemical propulsion methods that met current and near-term application criteria were identified and payload mass and delta-V capabilities were characterized. These capabilities were matched against concept disposal mass and destination delta-V requirements to provide a feasibility of each combination

ARAC feasibility study for the NRC Phase I: final report

International Nuclear Information System (INIS)

Rosen, L.C.; Orphan, R.C.

1979-11-01

The feasibility of implementing ARAC (Atmospheric Release Advisory Capability) services in a particular nuclear power plant is examined. The criteria for selecting Rancho Seco are discussed and the physical, meteorological and procedural factors related to the plant are assessed. The potential benefits and limitations of implementing ARAC at Rancho Seco are analyzed. The costs of employing the system at the nuclear power plant are given for alternative plans. A training and familiarization program is outlined

Nuclear energy center site survey: fuel cycle studies

International Nuclear Information System (INIS)

1976-05-01

Background information for the Nuclear Regulatory Commission Nuclear Energy Center Site Survey is presented in the following task areas: economics of integrated vs. dispersed nuclear fuel cycle facilities, plutonium fungibility, fuel cycle industry model, production controls and failure contingencies, environmental impact, waste management, emergency response capability, and feasibility evaluations

Feasibility of quantitative performance measures for evaluating nuclear power plant operators

International Nuclear Information System (INIS)

Carter, R.J.; Connelly, E.M.; Krois, P.A.

1989-01-01

A more valid measure of team performance in nuclear power plants is needed. A study is described which was oriented towards evaluating the feasibility of synthesizing performance measures by deriving measures for crews responding to an off-normal event in a full-scope simulator. The thesis was that performance assessment is based on the subjective judgment of training instructors. The procedure used to synthesize the performance measure consisted of: identification of the factors believed to be important to performance assessment, development of example crew performances and ratings on each by instructors, and derivation of the measure by capturing the instructors' assessment rules. A performance measure was derived which explains nearly all of the variance of the instructors' team performance assessments. There is reason to believe that this method of synthesizing measures can be applied to other events. 7 tabs

Feasibility study for a transportation operations system cask maintenance facility

Energy Technology Data Exchange (ETDEWEB)

Rennich, M.J.; Medley, L.G.; Attaway, C.R.

1991-01-01

The US Department of Energy (DOE), Office of Civilian Radioactive Waste Management (OCRWM) is responsible for the development of a waste management program for the disposition of spent nuclear fuel (SNF) and high-level waste (HLW). The program will include a transportation system for moving the nuclear waste from the sources to a geologic repository for permanent disposal. Specially designed casks will be used to safely transport the waste. The cask systems must be operated within limits imposed by DOE, the Nuclear Regulatory Commission (NRC), and the Department of Transportation (DOT). A dedicated facility for inspecting, testing, and maintaining the cask systems was recommended by the General Accounting Office (in 1979) as the best means of assuring their operational effectiveness and safety, as well as regulatory compliance. In November of 1987, OCRWM requested a feasibility study be made of a Cask Maintenance Facility (CMF) that would perform the required functions. 46 refs., 16 figs., 13 tabs.

Feasibility study for a transportation operations system cask maintenance facility

International Nuclear Information System (INIS)

Rennich, M.J.; Medley, L.G.; Attaway, C.R.

1991-01-01

The US Department of Energy (DOE), Office of Civilian Radioactive Waste Management (OCRWM) is responsible for the development of a waste management program for the disposition of spent nuclear fuel (SNF) and high-level waste (HLW). The program will include a transportation system for moving the nuclear waste from the sources to a geologic repository for permanent disposal. Specially designed casks will be used to safely transport the waste. The cask systems must be operated within limits imposed by DOE, the Nuclear Regulatory Commission (NRC), and the Department of Transportation (DOT). A dedicated facility for inspecting, testing, and maintaining the cask systems was recommended by the General Accounting Office (in 1979) as the best means of assuring their operational effectiveness and safety, as well as regulatory compliance. In November of 1987, OCRWM requested a feasibility study be made of a Cask Maintenance Facility (CMF) that would perform the required functions. 46 refs., 16 figs., 13 tabs

Radiological safety research for nuclear excavation projects - Interoceanic canal studies

Energy Technology Data Exchange (ETDEWEB)

Klement, Jr, A W [U.S. Atomic Energy Commission, Las Vegas, NV (United States)

1969-07-01

The general radiological problems encountered in nuclear cratering and nuclear excavation projects are discussed. Procedures for assessing radiological problems in such projects are outlined. Included in the discussions are source term, meteorology, fallout prediction and ecological factors. Continuing research requirements as well as pre- and post-excavation studies are important considerations. The procedures followed in the current interoceanic canal feasibility studies provide examples of radiological safety problems, current solutions and needed research. (author)

Radiological safety research for nuclear excavation projects - Interoceanic canal studies

International Nuclear Information System (INIS)

Klement, A.W. Jr.

1969-01-01

The general radiological problems encountered in nuclear cratering and nuclear excavation projects are discussed. Procedures for assessing radiological problems in such projects are outlined. Included in the discussions are source term, meteorology, fallout prediction and ecological factors. Continuing research requirements as well as pre- and post-excavation studies are important considerations. The procedures followed in the current interoceanic canal feasibility studies provide examples of radiological safety problems, current solutions and needed research. (author)

Feasibility study on floating nuclear power plant (1). Conceptual design study of FNPP. Contract research

International Nuclear Information System (INIS)

Yabuuchi, Noriaki; Shimazaki, Junya; Ochiai, Masaaki; Takahashi, Masao; Nakazawa, Toshio

2001-02-01

Offshore siting methods for a nuclear power plant are classified into three types as a floating type, a settled type and a land reclamation type. The floating nuclear power plant (FNPP) has a number of advantages, such as seismic isolation, standardization of design and manufacturing, and reduction of construction period. It is, however, required for FNPP to establish the safety standards, which are different from ones for land based nuclear power plant. Investigations for this subject have not been conducted sufficiently. In this report, design study on a concept for FNPP and a review on stability evaluation for the floating platform, which were performed in order to study the safety concept of the FNPP are described. The basic concept of the FNPP are described. The basic concept for FNPP is as follows: The FNPP is sited approximately 1 - 2km off the sea coast on the open sea with water depth of about 20m and it is moored of protected sea by the breakwater, it provide a floating platform for a 1,100MWe class PWR plant. The results of design study show that the floating platform for 1,100MWe class PWR plant of 300m (L) x 80m (W) x 35m (H), and displacement of approximately 300,000 ton can be constructed in a dockyard. This floating platform guarded by the breakwater is found to be stable enough to install the nuclear power plant from the analysis simulating the movement of the platform due to sea wave or wind. (author)

Feasibility study on floating nuclear power plant (1). Conceptual design study of FNPP. Construct research

Energy Technology Data Exchange (ETDEWEB)

Yabuuchi, Noriaki; Shimazaki, Junya; Ochiai, Masaaki [Department of Nuclear Energy System, Tokai Research Establishment, Japan Atomic Energy Research Institute, Tokai, Ibaraki (Japan); Takahashi, Masao [Niigata Engineering Co. Ltd., Tokyo (Japan); Nakazawa, Toshio [Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment; Sato, Kazuo [Ishikawajima-Harima Heavy Industries Co. Ltd., Tokyo (Japan)

2001-02-01

Offshore siting methods for a nuclear power plant are classified into three types as a floating type, a settled type and a land reclamation type. The floating nuclear power plant (FNPP) has a number of advantages, such as seismic isolation, standardization of design and manufacturing, and reduction of construction period. It is, however, required for FNPP to establish the safety standards, which are different from ones for land based nuclear power plant. Investigations for this subject have not been conducted sufficiently. In this report, design study on a concept for FNPP and a review on stability evaluation for the floating platform, which were performed in order to study the safety concept of the FNPP are described. The basic concept of the FNPP are described. The basic concept for FNPP is as follows: The FNPP is sited approximately 1 - 2km off the sea coast on the open sea with water depth of about 20m and it is moored of protected sea by the breakwater, it provide a floating platform for a 1,100MWe class PWR plant. The results of design study show that the floating platform for 1,100MWe class PWR plant of 300m (L) x 80m (W) x 35m (H), and displacement of approximately 300,000 ton can be constructed in a dockyard. This floating platform guarded by the breakwater is found to be stable enough to install the nuclear power plant from the analysis simulating the movement of the platform due to sea wave or wind. (author)

Feasibility analysis of the utilization of moderator heat for agricultural and aquacultural purposes, Bruce nuclear power development

International Nuclear Information System (INIS)

1977-12-01

A study is presented of the feasibility of using moderator reject heat from the Bruce nuclear power development either to heat greenhouses or to aid in a warm water hatchery or aquaculture operation. The study examines heat extraction and delivery plans, reliability of supply, pricing schedules, the Ontario greenhouse industry, site selection criteria, water transmission and distribution, costs, approvals required, and a construction timetable. Total system analysis shows that a greenhouse facility would be viable but the aquaculture/hatchery scheme is more cost-effective. (E.C.B.)

Feasibility Study for the Development of Plutonium Reference Materials for Age Dating in Nuclear Forensics

International Nuclear Information System (INIS)

Sturm, M.; Richter, S.; Aregbe, Y.; Wellum, R.; Altzitzoglou, T.; Verbruggen, A.; Mayer, K.; Prohaska, T.

2010-01-01

Isotopic reference materials certified for the age of nuclear material (uranium, plutonium) are needed in the fields of nuclear forensics and environmental measurements. Therefore a feasibility study for the development of plutonium reference materials for age dating has been started recently at the Institute for Reference Materials and Measurements (EC-JRC-IRMM). The ''age'' of the material is defined as the time that has passed since the last chemical separation of the mother and daughter isotopes (e.g. 241 Pu and 241 Am). Assuming that the separation has been complete and all the daughter isotopes have been removed from the original material during this last separation, the age of the material can be determined by measuring the ratio of daughter and mother radio-nuclides, e.g. 241 Am/ 241 Pu. At a given time after the last separation and depending on the half lives of the radio-nuclides involved, a certain amount of the daughter radionuclide(s) will be present. For the determination of the unknown age of a material different ''clocks'' can be used; ''clocks'' are pairs of mother and daughter radio-nuclides, such as 241 Am/ 241 Pu, 238 Pu/ 234 U, 239 Pu/ 235 U, 240 Pu/ 236 U, and possibly 242 Pu/ 238 U. For the age estimation of a real sample, such as material seized in nuclear forensics investigations or dust samples in environmental measurements, it is advisable to use more than one clock in order to ensure the reliability of the results and to exclude the possibility that the sample under question is a mixture of two or more materials. Consequently, a future reference material certified for separation date should ideally be certified for more than one ''clock'' or several reference materials for different ''clocks'' should be developed. The first step of this study is to verify the known separation dates of different plutonium materials of different ages and isotopic compositions by measuring the mother ( 238 Pu, 239 Pu, 240 Pu, 241 Pu, 242 Pu) and daughter

Feasibility study of the AOSTA experimental campaign

Directory of Open Access Journals (Sweden)

Carta M.

2016-01-01

Full Text Available The reduction of the nuclear waste is one of the most important nuclear issues. The high radiotoxicity of the spent fuel is due to plutonium and some minor actinides (MAs such as neptunium, americium and curium, above all. One way to reduce their hazard is to destroy by fission MAs in appropriate nuclear reactors. To allow the MAs destruction an important effort have been done on the nuclear data due to the poor knowledge in this field. In the framework of one of the NEA Expert Group on Integral Experiments for Minor Actinide Management an analysis of the feasibility of MAs irradiation campaign in the TAPIRO fast research reactor is carried out. This paper provides preliminary results obtained by calculations modelling the irradiation, in different TAPIRO irradiation channels, of some CEA samples coming from the French experimental campaign OSMOSE, loaded with different contents of MAs, in order to access, through particular peak spectrometry, to their capture cross section. On the basis of neutron transport calculation results, obtained by both deterministic and Monte Carlo methods, an estimate of the irradiated samples counting levels from the AOSTA (Activation of OSMOSE Samples in TAPIRO experimental campaign is provided.

Feasibility studies for decommissioning

International Nuclear Information System (INIS)

Hladky, E.

2000-01-01

In this presentation author deals with planning of decommission of the NPPs A1, V1 and V2 Bohunice and Mochovce. It was concluded that: Used model for decommissioning parameters assessment has been suitable for elaboration of initial decommissioning plans (feasibility studies); Basic assessment of main decommissioning parameters and basic comparison of various decommissioning options have been possible; Improvement of the model and corresponding software is desirable and works on software improvement began one year ago; V1-NPP initial decommissioning plan should be actualized, because initial decommissioning plan does not correspond by its content and structure to requirements of Act No. 130/98 and Nuclear Regulatory Authority Degree No. 246/99; Strategy of radioactive wastes treatment and conditioning together with technical provisions at Jaslovske Bohunice site was changed in comparison with the assumptions in 1991-92; Considered V1 NPP decommissioning options are necessary to be re-evaluated in accordance with latest development of knowledge and approaches to NPP decommissioning in the world; Specific unit costs are substantially and differentially changed in comparison with the assumptions in 1991-92; Necessity to take into account technical changes resulted from V1 NPP reconstruction. (author)

Nuclear Energy Center study. Phase II. Site suitability analysis. Final report

International Nuclear Information System (INIS)

Fellows, W.S.; Sharp, J.M.; Benator, B.I.

1978-06-01

A site screening study was conducted to identify a site or sites for detailed, site-specific study as a nuclear energy center. Using technical criteria of water requirements, geotechnical constraints, and projected load center and transmission considerations as well as environmental and institutional considerations, five potential study sites in the State of South Carolina were identified, evaluated against established criteria, and ranked according to their acceptability as potential nuclear energy center study sites. Consideration of what is ''representative'' of a site as well as the ranking score was factored into site recommendations, since the site deemed easiest to license and permit may not be the most desirable site for future study of the technical and institutional feasibility and practicality of a specific site. The sites near Lake Hartwell and the Savannah River Plant (SRP) of the Department of Energy were selected as potential study sites after consideration of the above criteria. Because the Lake Hartwell site offers the opportunity to consider institutional issues which may be more representative of other possible NEC sites, it is recommended that the Lake Hartwell site be studied to establish the feasibility and practicality of the nuclear energy concept on a site-specific basis

Strategic analysis for safeguards systems: a feasibility study. Volume 1. Main report

International Nuclear Information System (INIS)

Seaver, D.A.; Cohen, M.S.; Immerman, W.H.; Crane, F.L.; Goldman, A.J.

1984-12-01

Strategic analysis (game theory) is a formal method for modeling adversary situations that, when solved, yields an optimal strategy that maximizes the expected payoff to the player. As such, it appears to be potentially applicable in the nuclear material accounting context in which there is potential for an adversary attempting to divert special nuclear material. The NRC has previously supported research to develop preliminary strategic analysis models which has been considered to be only partially successful. This study reviewed previous efforts and other game theory research and assessed the feasibility of: (1) applying strategic analysis in a regulatory framework; (2) making strategic analysis understandable by licensees; and (3) assuring that strategic analysis can effectively be enforced. This report includes a discussion of the role of strategic analysis in material control and accounting, and of the mechanisms by which the NRC could implement strategic analysis. A set of feasibility criteria are described including both technical feasibility and organizational/implementation feasibility. Alternative strategic analysis model options are evaluated with respect to these criteria, as is the current material accounting practice. The assessment determined that the development of a payoff function that adequately represented the NRC's (and therefore the public's) values with respect to the consequences of diversion and the actions taken to prevent it is the most serious impediment to implementation. Given the limited role of material accounting in safeguards and the uncertainty regarding the development of a payoff function, the NRC should not proceed with full-scale implementation of strategic analysis. It does, however, have sufficient potential to warrant further development, with first priority going to the development of an appropriate payoff function

Investigation/evaluation of water cooled fast reactor in the feasibility study on commercialized fast reactor cycle systems. Intermediate evaluation of phase-II study

International Nuclear Information System (INIS)

Kotake, Syoji; Nishikawa, Akira

2005-01-01

Feasibility study on commercialized fast reactor cycle systems aims at investigation and evaluation of FBR design requirement's attainability, operation and maintenance, and technical feasibility of the candidate system. Development targets are 1) ensuring safety, 2) economic competitiveness, 3) efficient utilization of resources, 4) reduction of environmental load and 5) enhancement of nuclear non-proliferation. Based on the selection of the promising concepts in the first phase, conceptual design for the plant system has proceeded with the following plant system: a) sodium cooled reactors at large size and medium size module reactors, b) a lead-bismuth cooled medium size reactor, c) a helium gas cooled large size reactor and d) a BWR type large size FBR. Technical development and feasibility has been assessed and the study considers the need of respective key technology development for the confirmation of the feasibility study. (T. Tanaka)

Case study of siting technology for underground nuclear power plant

International Nuclear Information System (INIS)

Hibino, Satoshi; Komada, Hiroya; Honsho, Shizumitsu; Fujiwara, Yoshikazu; Motojima, Mutsumi; Nakagawa, Kameichiro; Nosaki, Takashi

1991-01-01

Underground siting method is one of new feasible siting methods for nuclear power plants. This report presents the results on case studies on underground siting. Two sites of a steeply inclined and plateau like configurations were selected. 'Tunnel type cavern; all underground siting' method was applied for the steeply inclined configuration, and 'shaft type semi-cavern; partial underground siting' method was applied for the plateau like configuration. The following designs were carried out for these two sites as case studies; (1) conceptual designs, (2) geological surveys and rock mechanics tests, (3) stability analysis during cavern excavations, (4) seismic stability analysis of caverns during earthquake, (5) reinforcement designs for caverns, (6) drainage designs. The case studies showed that these two cases were fully feasible, and comparison between two cases revealed that the 'shaft type semi-cavern; partial underground siting' method was more suitable for Japanese islands. As a first step of underground siting, therefore, the authors recommend to construct a nuclear power plant by this method. (author)

Feasibility study for the disposal of low and intermediate level radioactive waste in Cuba

International Nuclear Information System (INIS)

Chales Suarez, G.; Peralta Vital, J.L.; Gil Castillo, R.; Franklin Saburido, R.; Rodriquez Reyes, A.; Castillo Gomez, R.

1998-01-01

The perspective of completing and operating the Juragua Nuclear Power Station and the development of nuclear applications justifies the need to establish an appropriate low and intermediate level radioactive waste disposal system in Cuba. The design of one option which is consonant with the characteristics of this country is presented in the form of a feasibility study. The study discusses the characteristics of the wastes, the design of the repository, the packaging of the radioactive wastes as well as the siting, conditioning and performance assessment in a preliminary stage. International practice and experience have been considered, as well as the recommendations of the International Atomic Energy Agency [1-4] in the preparation of this study. (author)

Study on scenario evaluation methodology for decommissioning nuclear facilities using fuzzy logic

International Nuclear Information System (INIS)

Matsuhashi, Kazuya; Yanagihara, Satoshi

2015-01-01

Since there are many scenarios of the process from start to completion of a decommissioning project, it is important to study scenarios of decommissioning by evaluating such properties as safety, cost, and technology. An optimum scenario with the highest feasibility in accordance with the facility and environmental conditions should be selected on the basis of the results of the study. For analyzing a scenario of decommissioning, we prepared structured work packages by using the work breakdown structures (WBS) method together with qualitative evaluation of the technologies being applied to work packages located at the bottom (the third level) of the WBS. A calculation model was constructed to evaluate the feasibility of a scenario where fuzzy logic is applied to derive a score of technology performance and TOPSIS is applied for getting a feasibility grade of the scenario from technical performance scoring. As a case study, the model was applied to the debris removal scenario of Fukushima Daiichi Nuclear Power Plant to confirm its applicability. Two scenarios, underwater and in-air debris removal cases, were characterized by extracting the work packages with the lowest feasibility and by obtaining total average scores of the scenarios. It is confirmed that the methodology developed is useful for the scenario evaluation of decommissioning nuclear facilities. (author)

Experimental studies of nuclear astrophysics

International Nuclear Information System (INIS)

He Jianjun; Zhou Xiaohong; Zhang Yuhu

2013-01-01

Nuclear astrophysics is an interdisciplinary subject combining micro-scale nuclear physics and macro-scale astrophysics. Its main aims are to understand the origin and evolution of the elements in the universe, the time scale of stellar evolution, the stellar environment and sites, the energy generation of stars from thermonuclear processes and its impact on stellar evolution and the mechanisms driving astrophysical phenomena, and the structure and property of compact stars. This paper presents the significance and current research status of nuclear astrophysics; we introduce some fundamental concepts, the nuclear physics input parameters required by certain astrophysics models, and some widely-used experimental approaches in nuclear astrophysics research. The potential and feasibility of research in this field using China’s current and planned large-scale scientific facilities are analyzed briefly. Finally, the prospects of the establishing a deep underground science and engineering laboratory in China are envisaged. (authors)

Feasibility of risk-informed technology for japanese nuclear power plants

International Nuclear Information System (INIS)

Yoshida, Tomoo; Fujioka, Terutaka; Kirimoto, Yorihiro; Ueda, Nobuyuki; Kinoshita, Izumi; Kashima, Koichi

2000-01-01

Risk-informed technology utilizes Probabilistic Safety Assessment for streamlining the maintenance of nuclear power plants. With this technology, plant components are categorized as either high or low-safety-significant components. The Maintenance requirements focuses on high safety-significant components and are relieved for low safety significant ones. This is expected to reduce plant cost while maintaining safety. We investigated especially risk-informed inservice inspection of piping in U.S. nuclear power plants in the interest of determining its feasibility for Japanese plants. Quantitative and qualitative RI-ISI methods were developed by the ASME/Westinghouse Owners Group and EPRI, respectively. These methods have been incorporated in the ASME Section 11 Code Cases and endorsed by the U.S. Nuclear Regulatory Commission. The quantitative method evaluates component segment risks in terms of pipe failure probability calculated with a probabilistic fracture mechanics(PFM) model and pipe failure impact categorization on core damage frequency(CDF) calculated with PSA. The qualitative method uses pipe failure potential categorization derived from the plant service experiences and pipe failure impact on CDF derived from the PSA insight. The PFM model is applicable only to failures from initial welding defects and stress corrosion cracking, therefore it does not cover such significant failure mechanisms found in nuclear power plants as corrosion or high-cycle fatigue, etc.. Thus, a qualitative failure potential categorization method was developed on the basis of the service experiences of the U.S. nuclear power plants, so that appropriate categorization rules must be developed on the service experiences in Japanese plants. Accordingly, we have devised a software framework with a computer-aided system for the selection of risk significant elements. This system consists of a piping failure database module, a piping failure analysis module, and a piping failure potential

Nuclear Energy Center study. Phase II. Site suitability analysis. Final report

Energy Technology Data Exchange (ETDEWEB)

Fellows, W.S.; Sharp, J.M.; Benator, B.I.

1978-06-01

A site screening study was conducted to identify a site or sites for detailed, site-specific study as a nuclear energy center. Using technical criteria of water requirements, geotechnical constraints, and projected load center and transmission considerations as well as environmental and institutional considerations, five potential study sites in the State of South Carolina were identified, evaluated against established criteria, and ranked according to their acceptability as potential nuclear energy center study sites. Consideration of what is ''representative'' of a site as well as the ranking score was factored into site recommendations, since the site deemed easiest to license and permit may not be the most desirable site for future study of the technical and institutional feasibility and practicality of a specific site. The sites near Lake Hartwell and the Savannah River Plant (SRP) of the Department of Energy were selected as potential study sites after consideration of the above criteria. Because the Lake Hartwell site offers the opportunity to consider institutional issues which may be more representative of other possible NEC sites, it is recommended that the Lake Hartwell site be studied to establish the feasibility and practicality of the nuclear energy concept on a site-specific basis.

Study to evaluate the feasibility of constructing a retrofit containment for the 105-L reactor at the Savannah River Plant

International Nuclear Information System (INIS)

Quinn, R.D.

1989-01-01

This paper presents a summary of a study performed to determine the feasibility of constructing a retrofit containment dome meeting the requirements of the ASME Boiler and Pressure Vessel Code for nuclear containment vessels over the existing Savannah River 105-L reactor. Using existing large dome structures as a guide, design concepts were developed and analyses performed to evaluate the structural feasibility of containment dome structures. Construction schedules and costs were estimated to assess financial feasibility as well. It was concluded that such a retrofit containment dome was structurally feasible and within the capabilities of present day construction technology

Full scale model studies of nuclear power stations for earthquake resistance

International Nuclear Information System (INIS)

Kirillov, A.P.; Ambriashvili, Ju. K.; Kozlov, A.V.

Behaviour of nuclear power plants and its equipments under seismic action is not well understood. In the absence of well established method for aseismic deisgn of nuclear power plants and its equipments, it is necessary to carry out experimental investigations on models, fragments and full scale structures. The present study includes experimental investigations of different scale models and on existing nuclear power stations under impulse and explosion effects simulating seismic loads. The experimental work was aimed to develop on model test procedure for nuclear power station and the evaluation of the possible range of dynamic stresses in structures and pipe lines. The results of full-scale investigations of the nuclear reactor show a good agreement of dynamic characteristics of the model and the prototype. The study confirms the feasibility of simulation of model for nuclear power plants. (auth.)

Fuel assembly assessment from CVD image analysis: A feasibility study

International Nuclear Information System (INIS)

Lindsay, C.S.; Lindblad, T.

1997-05-01

The Swedish Nuclear Inspectorate commissioned a feasibility study of automatic assessment of fuel assemblies from images obtained with the digital Cerenkov viewing device currently in development. The goal is to assist the IAEA inspectors in evaluating the fuel since they typically have only a few seconds to inspect an assembly. We report results here in two main areas: Investigation of basic image processing and recognition techniques needed to enhance the images and find the assembly in the image; Study of the properties of the distributions of light from the assemblies to determine whether they provide unique signatures for different burn-up and cooling times for real fuel or indicate presence of non-fuel. 8 refs, 27 figs

Feasibility studies for alpha waste disposal on geological formations in France

International Nuclear Information System (INIS)

Jaouen, C.; Boulanger, A.

1986-01-01

Since 1977, SGN has been involved in many feasibility studies and consultant works in the fields of HLW storages. Starting as nuclear consultant company in the KBS review of the long term storage of HLW, SGN and GEOSTOCK were entrusted in 1978 by the EEC for the basic design and evaluation of the deep storage into granite rock of HLW, followed by a participation in the thermal sensitivity study of such a storage. The cooperation with GEOSTOCK was first extended in 1981 to a preliminary study of HLW storage conditions in granite for a Japanese company, and then in France for several feasibility studies of HLW and TRU waste geological disposal. Three kinds of scenarios have been forecasted and evaluated in the case of vitrified HLW storage, allowing the thermal power to be decreased and the whole management scheme to be optimized. More recently, SGN participation to French engineering studies has been extended by ANDRA to the TRU waste repository evaluation. All these works for French authorities have been performed in a close connection with several specialized departments in the CEA group, and with the help of geological specialists, under the leadership of ANDRA [fr

Feasibility studies for alpha waste disposal on geological formations in France

International Nuclear Information System (INIS)

Jaouen, C.; Boulanger, A.

1985-01-01

Since 1977, SGN has been involved in many feasibility studies and consultant works in the fields of HLW storages. Starting as nuclear consultant company in the KBS review of the long term storage of HLW, SGN and Geostock were entrusted in 1978 by the EEC for the basic design and evaluation of the deep storage into granite rock of HLW, followed by a participation in the thermal sensitivity study of such a storage. The cooperation with Geostock was first extended in 1981 to a preliminary study of HLW storage conditions in granite for a Japanese company, and then in France for several feasibility studies of HLW and TRU waste geological disposal. Three kinds of scenarios have been forecasted and evaluated in the case of vitrified HLW storage, allowing the thermal power to be decreased and the whole management scheme to be optimized. More recently, SGN participation to French engineering studies has been extended by ANDRA to the TRU waste repository evaluation. All these works for French authorities have been performed in a close connection with several specialized departments in the CEA group, and with the help of geological specialists, under the leadership of ANDRA [fr

Feasibility study of 24-month cycle using enriched Gadolinium as burnable poison for OPR1000

Energy Technology Data Exchange (ETDEWEB)

Moon, Sang-Rae; Shin, Ho-Cheol [KHNP Central Research Institute, Daejeon (Korea, Republic of)

2016-10-15

All of cobalt-60 sources are imported to Korea. CANDU units are generally used to produce cobalt-60 at Bruce and Point Lepreau in Canada and Embalse in Argentina. China has started production of cobalt-60 using its CANDU 6 Qinshan Phase III nuclear power plant in 2009. For cobalt-60 production, the reactor's full complement of stainless steel adjusters is replaced with neutronically equivalent cobalt-59 adjusters, which are essentially invisible to reactor operation. With its very high neutron flux and optimized fuel burn-up, the CANDU has a very high cobalt-60 production rate in a relatively short time. This makes CANDU an excellent vehicle for bulk cobalt-60 production. Several studies have been performed to produce cobalt-60 using adjuster rod at Wolsong nuclear power plant. This study proposed new concept for producing cobalt-60 and performed the feasibility study. Bundle typed cobalt loading concept is proposed and evaluated the feasibility to fuel management without physics and system design change. The requirement to load cobalt bundle to the core was considered and several channels are nominated. The production of cobalt-60 source is very depend on the flux level and burnup directly.

Developing Major Steps for a Feasibility Study for Upgrading I and C Systems in a Large Scale for an Operating Nuclear Power Plant

International Nuclear Information System (INIS)

Suh, Yong Suk; Keum, Jong Yong; Kim, Dong Hoon; Kang, Hyeon Tae; Sung, Chan Ho; Lee, Jae Ki; Cho, Chang Hwan

2009-01-01

According to the IAEA report as of Jan. 2008, 436 nuclear power reactors are in operation over the world and 368 nuclear power reactors exceed their operating ages by 20 years. The average I and C equipment's life span is 20 years comparing with that the average reactor's life time is 40 to 60 years. This means that a reactor must be faced with I and C equipment obsolescence problems once or twice during its operating years. The I and C equipment is replaced with new equipment only when the obsolescence problem occurs in a nuclear power plant. This is called an equipment basis upgrade in this paper. This replacement is such a general practice that occurs only when needed. We can assume that most of I and C equipment of a plant will meet with the obsolescence problem almost same time since it started operating. Although there must be a little time difference in the occurrence of the problems among I and C equipment, the replacement will be required in consecutive years. With this assumption, it is recommendable to upgrade the equipment, which is to meet with the problem at the same time, with new equipment at the same time. This is called a system basis upgrade in this paper. The system-basis replacement can be achieved in a large scale by coupling systems whose functions are related each other and replacing them together with a new upto- date platform. This paper focuses on the large scale upgrade of I and C systems for existing and operating NPPs. While performing a feasibility study for the large scale upgrade for Korea standard nuclear power plants (KSNPs), six major steps are developed for the study. This paper is to present what to perform in each step

Feasibility Study of Hydrogen Production at Existing Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Stephen Schey

2009-07-01

Cooperative Agreement DE-FC07-06ID14788 was executed between the U.S. Department of Energy, Electric Transportation Applications, and Idaho National Laboratory to investigate the economics of producing hydrogen by electrolysis using electricity generated by nuclear power. The work under this agreement is divided into the following four tasks: Task 1 – Produce Data and Analyses Task 2 – Economic Analysis of Large-Scale Alkaline Electrolysis Task 3 – Commercial-Scale Hydrogen Production Task 4 – Disseminate Data and Analyses. Reports exist on the prospect that utility companies may benefit from having the option to produce electricity or produce hydrogen, depending on market conditions for both. This study advances that discussion in the affirmative by providing data and suggesting further areas of study. While some reports have identified issues related to licensing hydrogen plants with nuclear plants, this study provides more specifics and could be a resource guide for further study and clarifications. At the same time, this report identifies other area of risks and uncertainties associated with hydrogen production on this scale. Suggestions for further study in some of these topics, including water availability, are included in the report. The goals and objectives of the original project description have been met. Lack of industry design for proton exchange membrane electrolysis hydrogen production facilities of this magnitude was a roadblock for a significant period. However, recent design breakthroughs have made costing this facility much more accurate. In fact, the new design information on proton exchange membrane electrolyzers scaled to the 1 kg of hydrogen per second electrolyzer reduced the model costs from $500 to $100 million. Task 1 was delayed when the original electrolyzer failed at the end of its economic life. However, additional valuable information was obtained when the new electrolyzer was installed. Products developed during this study

Material Identification Technology (MIT) concept technical feasibility study

International Nuclear Information System (INIS)

Jones, J.L.; Harker, Y.D.; Yoon, W.Y.; Johnson, L.O.

1993-09-01

The Idaho National Engineering Laboratory (INEL) has initiated the design and development of a novel pulsed accelerator-based, active interrogation concept. The proposed concept, referred to as the Material Identification Technology (MIT), enables rapid (between accelerator pulses), non-destructive, elemental composition analysis of both nuclear and non-nuclear materials. Applications of this technique include material monitoring in support of counter-proliferation activities, such as export controls (at domestic and international inspection locations), SNM controls, nuclear weapon dismantlement, and chemical weapon verification. Material Identification Technology combines a pulsed, X-ray source (an electron accelerator) and a gamma detection system. The accelerator must maximize neutron production (pulse width, beam current, beam energy, and repetition rate) and minimize photon dose to the object. Current available accelerator technology can meet these requirements. The detection system must include detectors which provide adequate gamma energy resolution capability, rapid recovery after the initial X-ray interrogation pulse, and multiple single gamma event detection between accelerator pulses. Further research is required to develop the detection system. This report provides the initial feasibility assessment of the MIT concept

Sault Tribe Wind Energy Feasibility Study

Energy Technology Data Exchange (ETDEWEB)

Toni Osterhout; Global Energy Concepts

2005-07-31

The Sault Tribe conducted a feasibility study on tribal lands in the Upper Peninsula of Michigan to determine the technical and economic feasibility of both small and large-scale wind power development on tribal lands. The study included a wind resource assessment, transmission system analysis, engineering and regulatory analyzes and assessments.

Status of feasibility study for various technical options of FBR systems

International Nuclear Information System (INIS)

Kani, Yoshio

2000-01-01

JNC (Japan Nuclear Cycle Development Institute) has started a new research project of feasibility studies (F/S) for a wide variety option of fast breeder reactor (FBR) and related fuel cycle in order to develop an economically competitive FBR cycle system fro commercialization. JNC and the electric untilities in Japan have established a new organization in JNC to perform the F/S since July 1, 1999. The organization has undertaken feasibility studies (F/S) in order to determine promising FBR cycle concepts and define necessary RandD tasks. The long-term targets of commercialized FBR cycle system are set as ensuring safety, economic competitiveness relative to future LWRs, efficient utilization of resources, reduction in environmental burden, and enhancement of nuclear non-proliferation. This paper describes the progress of design studies for a wide variety of technical options of FBR plants in the framework of the F/S. We make efforts towards considering all key issues so as not to fail to notice the best concept in a commercialized stage. In the study of technical options, the identified coolant types are sodium, heavy metal (lead and lead-bismuth), gas (carbon dioxide and helium ) and water (boiling water, pressurized water and supercritical water). The classified types of fuel are mixed oxide, nitride and metal. Design studies of small size modular plant concepts are also performed. We study many reactor concepts in combination with a coolant type and a fuel type, understand characteristics of each reactor concept based on our experience and an extensive survey of literature, and make a draft design of each reactor concept for rough estimation of construction costs. We also check how far the concept accomplishes each index (safety, economy, resource utilization, etc.) of design requirements, and will select several promising reactor concepts. (author)

Economic feasibility study of regional centers for nuclear fuel reprocessing in the developing countries

International Nuclear Information System (INIS)

Bakeshloo, A.A.

1977-01-01

The fuel cycle costs for the following three different economic alternatives were studied: (1) Reprocessing in an industrialized country (such as the U.S.); (2) Reprocessing in the individual developing country; (3) Reprocessing in a regional center. The nuclear fuel cycle cost for the ''Throw-away'' fuel cycle was evaluated. Among the six regions which were considered in this study, region one (South America including Mexico) was selected for the economic analysis of the nuclear fuel cycle for the above three alternatives. For evaluation of the cases where the fuel is reprocessed in a regional center or in an individual developing country, a unit reprocessing cost equation was developed. An economic evaluation was developed to estimate the least expensive method for transporting radioactive nuclear material by either leased or purchased shipping casks. The necessary equations were also developed for estimating plutonium transportation and the safeguard costs. On the basis of nuclear material and services requirements and unit costs for each component, the levelized nuclear fuel cycle costs for each alternative were estimated. Finally, by a comparison of cost, among these three alternatives plus the ''Throw-away'' case,it was found that it is not at all economical to build individual reprocessing plants inside the developing countries in region one. However, it also was found that the economic advantage of a regional center with respect to the first alternative is less than a 4% difference between their total fuel cycle costs. It is concluded that there is no great economic advantage in any developing countries to seek to process their fuel in one of the advanced countries. Construction of regional reprocessing centers is an economically viable concept

Assessment of the advantages and feasibility of a nuclear rocket for a manned Mars mission

International Nuclear Information System (INIS)

Howe, S.D.

1986-01-01

The feasibility of rebuilding and testing a nuclear thermal rocket (NTR) for the Mars mission was investigted. Calculations indicate that an NTR would substantially reduce the Earth-orbit assemble mass compared to LOX/LH 2 systems. The mass savings were 36 and 65% for the cases of total aerobraking and of total propulsive braking respectively. Consequently, the cost savings for a single mission of using an NTR, if aerobraking is feasible, are probably insufficient to warrant the NTR development. If multiple missions are planned or if propulsive braking is desired at Mars and/or at Earth, then the savings of about $7 billion will easily pay for the NTR. Estimates of the cost of rebuilding a NTR were based on the previous NERVA program's budget plus additional costs to develop a flight ready engine. The total cost to build the engine would be between $4 to 5 billion. The concept of developing a full-power test stand at Johnston Atoll in the Pacific appears very feasible. The added expense of building facilities on the island should be less than $1.4 billion

Feasibility Study on the Development of Index that Shows Social and Cultural Acceptance of Nuclear Power

Energy Technology Data Exchange (ETDEWEB)

Cho, SeongKyung [Bangmok College of General Education at Myongji Univ., Yongin (Korea, Republic of); Choi, Seungho; Yoon, Hana; Song, Jiyeon [Domo Brodeur, Seoul (Korea, Republic of)

2015-05-15

In this context, it is necessary to manage and develop an index that can measure the level of public acceptance by establishing the terms of social/cultural public acceptance of nuclear power in a practical manner and by identifying influential factors of public acceptance. Developing an index itself is not intended to increase the public acceptance of nuclear power. This study intends to contribute to determining energy policy acceptable to the public by estimating the level of potential social conflicts related to nuclear power policies with eligible evaluation criteria on social/cultural acceptance and by reducing relevant social costs. Key conclusions and proposal of this research are as follows. First, the influential factors of acceptance are reliability of nuclear safety, risk perception of nuclear power and beneficial perception of nuclear power. Among them, reliability of nuclear safety appears to have the most influence. In addition, benefit perception of nuclear power at the social level is significantly higher than that at the individual level. However, in relation to risk perception, a gap between experts and the public is found as nuclear industry premises that accident does not occur while the public premises that accident may occur.

Feasibility Study on the Development of Index that Shows Social and Cultural Acceptance of Nuclear Power

International Nuclear Information System (INIS)

Cho, SeongKyung; Choi, Seungho; Yoon, Hana; Song, Jiyeon

2015-01-01

In this context, it is necessary to manage and develop an index that can measure the level of public acceptance by establishing the terms of social/cultural public acceptance of nuclear power in a practical manner and by identifying influential factors of public acceptance. Developing an index itself is not intended to increase the public acceptance of nuclear power. This study intends to contribute to determining energy policy acceptable to the public by estimating the level of potential social conflicts related to nuclear power policies with eligible evaluation criteria on social/cultural acceptance and by reducing relevant social costs. Key conclusions and proposal of this research are as follows. First, the influential factors of acceptance are reliability of nuclear safety, risk perception of nuclear power and beneficial perception of nuclear power. Among them, reliability of nuclear safety appears to have the most influence. In addition, benefit perception of nuclear power at the social level is significantly higher than that at the individual level. However, in relation to risk perception, a gap between experts and the public is found as nuclear industry premises that accident does not occur while the public premises that accident may occur

Feasibility study on floating nuclear power plant (2). Safety design study of FNPP. Contract research

Energy Technology Data Exchange (ETDEWEB)

Yabuuchi, Noriaki; Shimazaki, Junya; Ochiai, Masaaki [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Takahashi, Masao [Niigata Engineering Co. Ltd., Tokyo (Japan); Nakazawa, Toshio [Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment; Sato, Kazuo [Ishikawajima-Harima Heavy Industries Co. Ltd., Tokyo (Japan)

2001-02-01

In the previous report of 'Conceptual Design Study of FNPP (Floating Nuclear Power Plant)', a design study on a concept for FNPP, which is sited off the sea coast on the open sea with water depth of 20m and it is moored on protected sea by the breakwater was conducted and the floating platform guarded by the breakwater was found to be stable enough to install the nuclear power plant from analysis simulating the movement of the platform due to sea wave or wind. In this report, studies on a basic safety design concept of the FNPP, setting natural phenomena for design condition, required safety functions and a review on dynamic analysis of the large floating structure are presented. The studies revealed that the stability of the floating platform is an essential issue for the FNPP soundness, and the design base natural phenomena such as S1 and S2-class storm including S1 and S2-class earthquake should be considered in evaluation of the stability of the floating platform, and it is one of key technical subjects how to set the magnitude of these storm in application of design evaluation on each FNPP case. (J.P.N.)

Nuclear Energy Center Site Survey, 1975. Part III. Technical considerations

International Nuclear Information System (INIS)

1976-01-01

Studies of the technical feasibility of nuclear energy centers (NECs) and the comparison between NEC technical feasibility and that of nuclear facilities on dispersed sites are reviewed. The conclusions related to technical feasibility of NEC are summarized. Technical feasibility was found to rest mainly on five major issues: heat dissipation, transmission, facility construction, radiological impact, and environmental impact. Although general conclusions can be reached in these five areas, it is recognized that they are interdependent, and detailed site-by-site analysis will be necessary. Some general conclusions on technical feasibility of NECs are presented, then detailed conclusions derived from the technical evaluation of NECs compared to dispersed site facilities are presented. The findings of this study on each of the five major feasibility issues are then discussed in sequence. The study concludes that nuclear energy centers, as defined herein, are technically feasible

Prospects of nuclear desalination in Morocco

International Nuclear Information System (INIS)

Tabet, M.

2005-01-01

In the last few years, Morocco has faced a continuous series of dry seasons, which has put a great stress on its limited water resources. Hence, for some time now Morocco has been considering desalinating seawater to supply fresh water to some areas. In the early 1980's, due to limited energy resources, Morocco was obliged to consider other alternatives to meet its energy demands. A feasibility study for the introduction of a nuclear power plant into the national electrical grid was launched. Even though the study showed that the commercially proven, large size reactors could not be integrated into the grid due to their limited capacity, the national electrical utility continues to pursue its efforts to introduce nuclear energy into the country. Presently, the feasibility study is being updated and a bid invitation specification is being prepared with the help of the IAEA experts. In response to the increasing need for energy and water, Morocco and some North African countries participated in the IAEA regional project on the feasibility study on using nuclear energy for seawater desalination. Subsequently, Morocco carried out a feasibility study for the construction of a demonstration plant for seawater desalination using a 10 MW Nuclear Heating Reactor with China and IAEA. As part of its interest in nuclear energy, Morocco is setting up the nuclear infrastructure that could help in the implementation of the nuclear power programme. The construction of a nuclear research centre which is to be commissioned in a couple of years, and the establishment of the nuclear safety authority and the radiation protection authority are part of the programme. (author)

Studies on environment safety and application of advanced reactor for inland nuclear power plants

International Nuclear Information System (INIS)

Wei, L.; Jie, L.

2014-01-01

To study environment safety assessment of inland nuclear power plants (NPPs), the impact of environment safety under the normal operation was researched and the environment risk of serious accidents was analyzed. Moreover, the requirements and relevant provisions of site selection between international nuclear power plant and China's are comparatively studied. The conclusion was that the environment safety assessment of inland and coastal nuclear power plant have no essential difference; the advanced reactor can meet with high criteria of environment safety of inland nuclear power plants. In this way, China is safe and feasible to develop inland nuclear power plant. China's inland nuclear power plants will be as big market for advanced reactor. (author)

A study on the feasibility and a possible form of local residents participation in nuclear safety regulation

International Nuclear Information System (INIS)

Lee, Sang Hoon; Son, Moon Kyu; Kim, Seong Sook

2003-02-01

It is expected that the results of this study will help policy makers in the government and nuclear industry enhance the confidence of local residents and citizens in the safety of nuclear energy. It is also believed that the citizen confidence on the nuclear energy will help them implement nuclear policies more efficiently and more safely. Considering that the newly sworn-in government is to involve citizens in wide variety of policy areas, this study fits with the policy directions of the new government. Most importantly, desirable citizen participation in public decision-making is to contribute to the enhancement of the working democracy

A study on the feasibility and a possible form of local residents participation in nuclear safety regulation

Energy Technology Data Exchange (ETDEWEB)

Lee, Sang Hoon; Son, Moon Kyu [Korea Association for Nuclear Technology, Taejon (Korea, Republic of); Kim, Seong Sook [Shila Univ., Busan (Korea, Republic of)

2003-02-15

It is expected that the results of this study will help policy makers in the government and nuclear industry enhance the confidence of local residents and citizens in the safety of nuclear energy. It is also believed that the citizen confidence on the nuclear energy will help them implement nuclear policies more efficiently and more safely. Considering that the newly sworn-in government is to involve citizens in wide variety of policy areas, this study fits with the policy directions of the new government. Most importantly, desirable citizen participation in public decision-making is to contribute to the enhancement of the working democracy.

Ultrasonic decontamination of nuclear fuel. Feasibility study

International Nuclear Information System (INIS)

Berg, A.; Libal, A.; Norbaeck, J.; Wegemar, B.

1995-05-01

Ultrasonic decontamination of nuclear fuel is an expeditious way to reduce radiation exposures resulting in a minimal volume of waste. The fuel assemblies are set up in the fuel preparation machine one at a time and treated without prior disassemblage. By decontaminating 20% of the BWR fuel assemblies annually, there is a potential to reduce the collective dose by approximately 40-50%. Including also improved reactivity of the fuel, this amounts to an economic benefit of about 4 MSEK per reactor and year. The costs for performing the decontamination can be economically justified if the plants do not plan for short outages each year. The decontamination method could also be used for the purpose of removing tramp Uranium following a fuel failure or minor core accident. An additional benefit is removal of loosely adherent crud. The waste produced will be handled in a closed filtering circuit. The method is suggested to be verified in a test on discharged burnt-up fuel at site. The next step will be to develop the method further in order to be able to remove also tenacious crud. 12 refs, 4 tabs

Thermal hydraulic feasibility assessment for the Spent Nuclear Fuel Project

International Nuclear Information System (INIS)

Heard, F.J.; Cramer, E.R.; Beaver, T.R.; Thurgood, M.J.

1996-01-01

A series of scoping analyses have been completed investigating the thermal-hydraulic performance and feasibility of the Spent Nuclear Fuel Project (SNFP) Integrated Process Strategy (IPS). The SNFP was established to develop engineered solutions for the expedited removal, stabilization, and storage of spent nuclear fuel from the K Basins at the U.S. Department of Energy's Hanford Site in Richland, Washington. The subject efforts focused on independently investigating, quantifying, and establishing the governing heat production and removal mechanisms for each of the IPS operations and configurations, obtaining preliminary results for comparison with and verification of other analyses, and providing technology-based recommendations for consideration and incorporation into the design bases for the SNFP. The goal was to develop a series fo thermal-hydraulic models that could respond to all process and safety-related issues that may arise pertaining to the SNFP. A series of sensitivity analyses were also performed to help identify those parameters that have the greatest impact on energy transfer and hence, temperature control. It is anticipated that the subject thermal-hydraulic models will form the basis for a series of advanced and more detailed models that will more accurately reflect the thermal performance of the IPS and alleviate the necessity for some of the more conservative assumptions and oversimplifications, as well as form the basis for the final process and safety analyses

100-BC-1 Operable Unit focused feasibility study

International Nuclear Information System (INIS)

Day, R.E.

1994-01-01

The standard Comprehensive Environmental Response, Compensation, and Liability Act feasibility study includes development and screening of alternatives (Phases 1 and 2) and the detailed analysis of alternatives (Phase 3). This focused feasibility study constitutes the Phase 3 portion of the feasibility study process for the remedial alternatives initially developed and screened in the 100 Area Feasibility Study Phases 1 and 2 (DOE-RL 1993a). The focused feasibility study process is conducted in two stages, a Process Document (DOE-RL 1994a) and an operable unit-specific focused feasibility study document, such as this one. The focused feasibility study process is performed by implementing a ''plug-in'' style approach; as defined in greater detail in the Process Document, which is a companion to this document. The objective of this focused feasibility study is to provide decision makers with sufficient information to allow appropriate and timely selection of interim remedial measures for candidate waste sites associated with the 100-BC-1 Operable Unit which is located in the north-central part of the Hanford Site. The interim remedial measure candidate waste sites are determined in the Limited Field Investigation (DOE-RL 1993b). Site profiles are developed for each of these waste sites. The site profiles are used in the application of the plug-in approach. The waste site either plugs into the analysis of the alternatives for the group, or deviations from the developed group alternatives are described and documented

Preliminary economic feasibility study of MIP (Medical Isotopes Producer)

International Nuclear Information System (INIS)

Mon, G. H.; O, S. Y.

2004-01-01

Preliminary economic feasibility study of MIP (Medical Isotopes Producer), which is used liquid nuclear fuel to produce medical isotopes of Mo-99 and Sr-89, was performed. To do this, this study was estimated the IRR(Internal Rate of Return) and PBP(Pay-back Period) about optimistic and pessimistic cases for market penetration of Asia and U.S.A. isotope markets. And sensitivity analysis is also performed about capital cost and price of Mo-99 and Sr-89. According to the results, IRR was between 14.9% and 24.3%, and PBP was between 4.8 years and 7.8 years. These suggest that MIP has economic merits. MIP can produce other medical isotopes such as Sr-90, I-131, Xe-133, Cs-137. So, it is necessary to do cost-benefit analysis considering production of these other isotopes

Results of and prospects for studies on molten salt nuclear reactors

International Nuclear Information System (INIS)

Hery, M.; Lecocq, A.

1983-04-01

This paper reviews the various studies performed in France by the EDF and CEA teams in the field of molten salt nuclear reactors. These studies include graphite moderating systems, feasibility of a 625 MWth core, lead cooling, structural materials, salts tritium diffusion and corrosion. The experience gained allows eventual development prospects of this system to appraised [fr

Bin Set 1 Calcine Retrieval Feasibility Study

International Nuclear Information System (INIS)

Adams, R.D.; Berry, S.M.; Galloway, K.J.; Langenwalter, T.A.; Lopez, D.A.; Noakes, C.M.; Peterson, H.K.; Pope, M.I.; Turk, R.J.

1999-01-01

At the Department of Energy's Idaho Nuclear Technology and Engineering Center, as an interim waste management measure, both mixed high-level liquid waste and sodium bearing waste have been solidified by a calculation process and are stored in the Calcine Solids Storage Facilities. This calcined product will eventually be treated to allow final disposal in a national geologic repository. The Calcine Solids Storage Facilities comprise seven ''bit sets.'' Bin Set 1, the first to be constructed, was completed in 1959, and has been in service since 1963. It is the only bin set that does not meet current safe-shutdown earthquake seismic criteria. In addition, it is the only bin set that lacks built-in features to aid in calcine retrieval. One option to alleviate the seismic compliance issue is to transport the calcine from Bin Set 1 to another bin set which has the required capacity and which is seismically qualified. This report studies the feasibility of retrieving the calcine from Bi n Set 1 and transporting it into Bin Set 6 which is located approximately 650 feet away. Because Bin Set 1 was not designed for calcine retrieval, and because of the high radiation levels and potential contamination spread from the calcined material, this is a challenging engineering task. This report presents preconceptual design studies for remotely-operated, low-density, pneumatic vacuum retrieval and transport systems and equipment that are based on past work performed by the Raytheon Engineers and Constructors architectural engineering firm. The designs presented are considered feasible; however, future development work will be needed in several areas during the subsequent conceptual design phase

Bin Set 1 Calcine Retrieval Feasibility Study

Energy Technology Data Exchange (ETDEWEB)

R. D. Adams; S. M. Berry; K. J. Galloway; T. A. Langenwalter; D. A. Lopez; C. M. Noakes; H. K. Peterson; M. I. Pope; R. J. Turk

1999-10-01

At the Department of Energy's Idaho Nuclear Technology and Engineering Center, as an interim waste management measure, both mixed high-level liquid waste and sodium bearing waste have been solidified by a calculation process and are stored in the Calcine Solids Storage Facilities. This calcined product will eventually be treated to allow final disposal in a national geologic repository. The Calcine Solids Storage Facilities comprise seven ''bit sets.'' Bin Set 1, the first to be constructed, was completed in 1959, and has been in service since 1963. It is the only bin set that does not meet current safe-shutdown earthquake seismic criteria. In addition, it is the only bin set that lacks built-in features to aid in calcine retrieval. One option to alleviate the seismic compliance issue is to transport the calcine from Bin Set 1 to another bin set which has the required capacity and which is seismically qualified. This report studies the feasibility of retrieving the calcine from Bi n Set 1 and transporting it into Bin Set 6 which is located approximately 650 feet away. Because Bin Set 1 was not designed for calcine retrieval, and because of the high radiation levels and potential contamination spread from the calcined material, this is a challenging engineering task. This report presents preconceptual design studies for remotely-operated, low-density, pneumatic vacuum retrieval and transport systems and equipment that are based on past work performed by the Raytheon Engineers and Constructors architectural engineering firm. The designs presented are considered feasible; however, future development work will be needed in several areas during the subsequent conceptual design phase.

Feasibility of a joint nuclear project

International Nuclear Information System (INIS)

Leung, C.T.

1980-01-01

To meet the growing power demand in the late eighties, the People's Republic of China will cooperate with Hong Kong to develop nuclear power. In this paper, the energy policy of China and her nuclear capabilities are reviewed, and some of the foreseeable problems of the China and Hong Kong joint nuclear project are discussed. (author)

Mescalero Apache Tribe Monitored Retrievable Storage (MRS). Phase 1 feasibility study report

Energy Technology Data Exchange (ETDEWEB)

Peso, F.

1992-03-13

The Nuclear Waste Policy Act of 1982, as amended, authorizes the siting, construction and operation of a Monitored Retrievable Storage (MRS) facility. The MRS is intended to be used for the temporary storage of spent nuclear fuel from the nation`s nuclear power plants beginning as early as 1998. Pursuant to the Nuclear Waste Policy Act, the Office of the Nuclear Waste Negotiator was created. On October 7, 1991, the Nuclear Waste Negotiator invited the governors of states and the Presidents of Indian tribes to apply for government grants in order to conduct a study to assess under what conditions, if any, they might consider hosting an MRS facility. Pursuant to this invitation, on October 11, 1991 the Mescalero Apache Indian Tribe of Mescalero, NM applied for a grant to conduct a phased, preliminary study of the safety, technical, political, environmental, social and economic feasibility of hosting an MRS. The preliminary study included: (1) An investigative education process to facilitate the Tribe`s comprehensive understanding of the safety, environmental, technical, social, political, and economic aspects of hosting an MRS, and; (2) The development of an extensive program that is enabling the Tribe, in collaboration with the Negotiator, to reach an informed and carefully researched decision regarding the conditions, (if any), under which further pursuit of the MRS would be considered. The Phase 1 grant application enabled the Tribe to begin the initial activities necessary to determine whether further consideration is warranted for hosting the MRS facility. The Tribe intends to pursue continued study of the MRS in order to meet the following objectives: (1) Continuing the education process towards a comprehensive understanding of the safety, environmental, technical, social and economic aspects of the MRS; (2) Conducting an effective public participation and information program; (3) Participating in MRS meetings.

A feasibility study for the development of an SCWR in Korea

International Nuclear Information System (INIS)

Hong, Sung-Yull; Kim, Yong-Bae; Bae, Seong-Man; Lee, Kwangho; Kim, Junhyung; Bae, Yoon-Yeong

2008-01-01

Korea is participating in international collaboration activities since the selection of supercritical water-cooled reactor (SCWR) as one of the viable candidates for Generation IV reactor systems in 2002. The SCWR has been selected by Generation IV International Forum (GIF) since it is a very feasible candidate reactor system for a large-scale electricity production in commercially viable manner. However, the level of Korean participation is still limited to several key areas and the decision-making on whether going into full-scale research is yet to be made. In three circumstances it has been decided to launch a feasibility study in March 2007 to assess the domestic capability and resources as well as economics for development of an SCWR and to identify the required research areas. This paper introduces the project named 'A feasibility study for the development of an SCWR in Korea', which is sponsored by MEST (Ministry of Education, Science and Technology) in Korea. The main purpose of this study is to provide a basis for establishing a government policy in consideration of the unique domestic environment for SCWR development. This study includes three different areas of evaluation aspect, i.e., policy and environment, technology and safety, and economics. In policy and environment aspects, the needs of SCWR development is evaluated in terms of future electricity demand, reactor type strategy, fuel cycle policy, and available infrastructure in Korea, etc. In technology and safety aspects, evaluation is performed to identify the most optimum way of SCWR R and D strategy and several fundamental studies including heat transfer, code developments, and materials are performed in parallel. Finally, in economic aspect, the economic feasibility of SCWR development is assessed in comparison with the Korean nuclear power plants OPR1000 and APR1400 and other comparable overseas reactors. This study will be finished by 2010 and the results of the assessment will become a

Feasibility analysis of the Primary Loop of Pool-Type Natural Circulating Nuclear Reactor Dedicated to Seawater Desalination

Energy Technology Data Exchange (ETDEWEB)

Jeong, Woonho; Jeong, Yong Hoon [KAIST, Daejeon (Korea, Republic of)

2016-05-15

In this study, the feasibility of natural circulation was evaluated for the reference plant AHR400 (Advanced Heating Reactor 400MWth). AHR400 is a pool-type desalination-dedicated nuclear reactor. As a consequence, AHR400 has low operating pressure and temperature which provides large safety margin. Removal of the reactor coolant pump from the AHR400 will enforce integrity of the reactor vessel and passive safety feature. Therefore, the study also tried to find out optimized primary loop design to achieve total natural circulation of the coolant. Natural circulation capacity of the primary loop of the desalination dedicated nuclear reactor AHR400 was evaluated. It was concluded that to remove RCP from the AHR400 and operates the reactor only by natural circulation of the coolant is impossible. Decreased core power as half make removal of RCP possible with 15m central height difference between the core and IHXs. Furthermore, validation and modification of pressure loss coefficients by small-scaled natural circulation experiment at a pool-type reactor would provide more accurate results.

A study on the planning for the research and development of nuclear energy

International Nuclear Information System (INIS)

Noh, Byong Chull; Won, B. C.; Bang, J. K.; Jung, Y. H.; Kim, M. R.; Cho, C. Y.; Lee, H. S.; Kim, J. U.; Yeo, J. W.; Hong, Y. P.; Kim, I. C.; Rha, K. H.; Yoon, Y. S.; Park, J. H.; Ko, Y. S.; Kim, S. S.; Kang, W. J.; Lee, Y. H.; Shim, H. W.

1997-01-01

This study has performed aiming to provide the government with the basic input to establish 'the comprehensive promotion plan for utilization, research and development of nuclear energy' and 'the mid- and long-term nuclear research and development program', thus the government set it up as a national plan after endorsement of Atomic Energy Commission. Next, the feasibility study of the proton accelerators construction which is expected to use for nuclear research and development and industry. And a systematic and integrated research and development management system for the large-scale projects has been studied considering the inherent uncertainty and high risk of research and development. (author). 24 tabs., 6 figs

Feasibility study for the development of a Dose Calibrator with a well ionization chamber

International Nuclear Information System (INIS)

Arista Romeu, E. J.

2015-01-01

Dose calibrators are intended for the metrological assurance of medical diagnostic studies in which radiopharmaceuticals are used. It is the final link in the national system of standards to ensure quality control and the radiation safety of the dose administered to patients while using these nuclear techniques. The wide utilization of radiopharmaceuticals in our country in several modules of nuclear medicine and other laboratories where radio-isotopic preparations are used, as well as the existence of the National Center of Isotopes to produce them determine the necessity of national production of dose calibration equipment. In this paper, it is presented the result of a feasibility study to develop a dose calibrator with a well-type ionization chamber for nuclear medicine services of the National Health System with gamma camera. It is specifically intended to contribute to monitor and control the activity of the prepared samples to be administered to patients under studies with gamma cameras to ensure compliance with the current requirements of quality and radiation safety. (Author)

The feasibility study: a health economics perspective

Directory of Open Access Journals (Sweden)

Brenda Gannon

2017-02-01

Full Text Available The remit of research funding bodies is to prioritise funding for research that is of relevance and of high quality. This in turn will aim to raise the quality of healthcare and benefit to patients. Researchers are faced with increasing demands and expectations from the public purse and patients. The emphasis is to improve the quality of their research, with the ultimate aim of improving population health. While guidelines on feasibility study methods concentrate heavily on trials, there appears less guidance on application of health economics within feasibility studies, yet these are a less costly way to determine first of all if a full randomised controlled trial (RCT is feasible. A feasibility study assesses if the study can be done in a small RCT type study. Since by definition, a feasibility study does not evaluate the outcome, researchers often omit the health economics aspects but do however include statistical analysis. This leaves a gap in interpretation for policy makers and potential funders. It also means that any resulting publication does not include relevant information and therefore comparison across studies in terms of difficulty in collecting cost data is not possible. The main aim of this commentary therefore, is to demonstrate a suggested health economics analysis within a feasibility study and to recommend to researchers to include these aspects from the conception of their intervention. This paper proposes a number of points, with rationale for each point, to indicate the health economics data and the potential benefits required for coherent interpretation of the feasibility of future economic evaluations in a full trial. Economic evaluation is necessary if implementation into standard care is anticipated. Therefore, collection and summary analysis of relevant data is good practice at each point of the intervention development. Current guidelines for economic evaluation, for example, The Medical Research Guidelines in the

Study on modular technology based on the reference nuclear power plant

International Nuclear Information System (INIS)

Lu Qinwu; Zhao Shuyu; Li Yi; Han Xiaoping; Chai Weidong; Zhang Shuxia

2014-01-01

As an important technology for shortening the construction period and reducing the cost of nuclear power project, modular technology has become one of the development orientations of the third generation nuclear power plant. Taking CPR1000 nuclear power reactor as reference plant and drawing on advanced foreign technology of modularization, the overall concept design has been completed with the help of the self-developed 3D modular design system. On this basis, a typical detailed design work has been carried out so as to verify the feasibility of technology. Besides, an analysis on implementation of modular technology has been made from two aspects (procurement and construction), and the feasibility of research results in actual project has been evaluated. It provides references for the promotion of self-reliant modular technology in nuclear power project in China. (authors)

Final report. Conceptual studies nuclear energy center Lake Hartwell, S.C., Phase III

International Nuclear Information System (INIS)

1981-01-01

This document summarizes a conceptual study on the feasibility and practicality of developing a nuclear energy center (NEC) at a specific site in the SSEB region. The site selected for this conceptual study is at Lake Hartwell, South Carolina. The conceptual NEC at Lake Hartwell consists of twelve nuclear electric generating units, arranged on the site in four clusters of three units each, known as triads. The nominal distance between triads was selected as 2-1/2 miles. Each unit was assumed to be a 1250 MW(e). The total electric output of 15,000 MWe would be transmitted to five major utilities in South Carolina, North Carolina, and Georgia. The basic finding was that the concept of a NEC on the Lake Hartwell site is feasible, but further analysis of institutional issues and possible legislation would be required

Integrating Nuclear Energy to Oilfield Operations - Two Case Studies

International Nuclear Information System (INIS)

Robertson, Eric P.; Nelson, Lee O.; McKellar, Michael G.; Gandrik, Anastasia M.; Patterson, Mike W.

2011-01-01

Fossil fuel resources that require large energy inputs for extraction, such as the Canadian oil sands and the Green River oil shale resource in the western USA, could benefit from the use of nuclear power instead of power generated by natural gas combustion. This paper discusses the technical and economic aspects of integrating nuclear energy with oil sands operations and the development of oil shale resources. A high temperature gas reactor (HTGR) that produces heat in the form of high pressure steam (no electricity production) was selected as the nuclear power source for both fossil fuel resources. Both cases were based on 50,000 bbl/day output. The oil sands case was a steam-assisted, gravity-drainage (SAGD) operation located in the Canadian oil sands belt. The oil shale development was an in-situ oil shale retorting operation located in western Colorado, USA. The technical feasibility of the integrating nuclear power was assessed. The economic feasibility of each case was evaluated using a discounted cash flow, rate of return analysis. Integrating an HTGR to both the SAGD oil sands operation and the oil shale development was found to be technically feasible for both cases. In the oil sands case, integrating an HTGR eliminated natural gas combustion and associated CO2 emissions, although there were still some emissions associated with imported electrical power. In the in situ oil shale case, integrating an HTGR reduced CO2 emissions by 88% and increased natural gas production by 100%. Economic viabilities of both nuclear integrated cases were poorer than the non-nuclear-integrated cases when CO2 emissions were not taxed. However, taxing the CO2 emissions had a significant effect on the economics of the non-nuclear base cases, bringing them in line with the economics of the nuclear-integrated cases. As we move toward limiting CO2 emissions, integrating non-CO2-emitting energy sources to the development of energy-intense fossil fuel resources is becoming

Feasibility Study on the Development of 2-channel Embedded Infrared Fiber-optic Sensor for Thermometry of Secondary Water System in Nuclear Power Plant

International Nuclear Information System (INIS)

Yoo, W. J.; Jang, K. W.; Seo, J. K.; Moon, J.; Han, K. T.; Lee, B.; Park, B. G.

2011-01-01

Any warm object by measuring the emitted infrared (IR) radiation. The radiometers using infrared optical fibers are based on the relationship between the temperature of a heat source and the quality and the quantity of an IR radiation. To measure physical properties including a temperature, optical fiber-based sensor has many advantages, such as small size, low cost, high resolution, remote sensing and immunity to electromagnetic radiation over conventional electrical sensors. In this study, we carried out the feasibility study on the development of an embedded IR fiber-optic sensor for thermometry of the secondary water system in a nuclear power plant. The 2-channel embedded fiberoptic temperature sensor was fabricated using two identical IR optical fibers for accurate thermometry without complicated calibration processes. To decide accurate temperature of the water, we measured the difference between the IR radiations emitted from the two temperature sensing probes according to the temperature variation of the water

Feasibility Study of Non-Destructive Techniques to Measure Corrosion in SAVY Containers

Energy Technology Data Exchange (ETDEWEB)

Davenport, Matthew Nicholas [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2016-07-15

Stainless Steel SAVY containers are used to transport and store nuclear material. They are prone to interior corrosion in the presence of certain chemicals and a low-oxygen environment. SAVY containers also have relatively thin walls to reduce their weight, making their structural integrity more vulnerable to the effects of corrosion. A nondestructive evaluation system that finds and monitors corrosion within containers in use would improve safety conditions and preclude hazards. Non-destructive testing can determine whether oxidation or corrosion is occurring inside the SAVY containers, and there are a variety of non-destructive testing methods that may be viable. The feasibility study described will objectively decide which method best fits the requirements of the facility and the problem. To improve efficiency, the containers cannot be opened during the non-destructive examination. The chosen technique should also be user-friendly and relatively quick to apply. It must also meet facility requirements regarding wireless technology and maintenance. A feasibility study is an objective search for a new technology or product to solve a particular problem. First, the design, technical, and facility feasibility requirements are chosen and ranked in order of importance. Then each technology considered is given a score based upon a standard ranking system. The technology with the highest total score is deemed the best fit for a certain application.

Renewable Energy Feasibility Study Final Report

Energy Technology Data Exchange (ETDEWEB)

Rooney, Tim [Antares Group Inc.

2013-10-30

The Gila River Indian Community (GRIC or the Community) contracted the ANTARES Group, Inc. (“ANTARES”) to assess the feasibility of solar photovoltaic (PV) installations. A solar energy project could provide a number of benefits to the Community in terms of potential future energy savings, increased employment, environmental benefits from renewable energy generation and usage, and increased energy self-sufficiency. The study addresses a number of facets of a solar project’s overall feasibility, including: Technical appropriateness; Solar resource characteristics and expected system performance; Levelized cost of electricity (LCOE) economic assessment. The Gila River Indian Community (GRIC or the Community) contracted the ANTARES Group, Inc. (“ANTARES”) to prepare a biomass resource assessment study and evaluate the feasibility of a bioenergy project on Community land. A biomass project could provide a number of benefits to the Community in terms of increased employment, environmental benefits from renewable energy generation and usage, and increased energy self-sufficiency. The study addresses a number of facets of a biomass project’s overall feasibility, including: Resource analysis and costs; Identification of potential bioenergy projects; Technical and economic (levelized cost of energy) modeling for selected project configuration.

A Study on Dismantling of Westinghouse Type Nuclear Reactor

International Nuclear Information System (INIS)

Jeong, Woo-Tae; Lee, Sang-Guk

2014-01-01

KHNP started a research project this year to develop a methodology to dismantle nuclear reactors and internals. In this paper, we reviewed 3D design model of the reactor and suggested feasible cutting scheme.. Using 3-D CAD model of Westinghouse type nuclear reactor and its internals, we reviewed possible options for disposal. Among various options of dismantling the nuclear reactor, plasma cutting was selected to be the best feasible and economical method. The upper internals could be segmented by using a band saw. It is relatively fast, and easily maintained. For cutting the lower internals, plasma torch was chosen to be the best efficient tool. Disassembling the baffle and the former plate by removing the baffle former bolts was also recommended for minimizing storage volume. When using plasma torch for cutting the reactor vessel and its internal, installation of a ventilation system for preventing pollution of atmosphere was recommended. For minimizing radiation exposure during the cutting operation, remotely controlled robotic tool was recommended to be used

Pinellas Plant feasibility study. Final report

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-09-01

The Pinellas Plant was built in 1956 to manufacture neutron generators, a principal component in nuclear weapons. In September 1990, the Department of Health and Rehabilitative Services (HRS) entered into an agreement with DOE to independently examine environmental monitoring data from the plant and health data from Pinellas County to determine if an epidemiological study is technically feasible to measure possible off-site health effects from ionizing radiation. Through normal plant operations, some radioactive materials have been released to the environment. Eighty percent of the total plant releases of 107,707 curies occurred in the early years of plant operation (1957--1960). The primary materials released were tritium gas, tritium oxide and krypton-85. Environmental monitoring for radioactive releases from the plant has been done regularly since 1975. The US Public Health Service Centers for Disease Control and Prevention (CDC), in assisting HRS, has determined that sufficient radiological data exist by which a dose reconstruction can be done. A dose reconstruction can provide an estimate of how much radiological exposure someone living in the vicinity of the Pinellas Plant may have suffered from environmental releases.

Pinellas Plant feasibility study. Final report

International Nuclear Information System (INIS)

1994-09-01

The Pinellas Plant was built in 1956 to manufacture neutron generators, a principal component in nuclear weapons. In September 1990, the Department of Health and Rehabilitative Services (HRS) entered into an agreement with DOE to independently examine environmental monitoring data from the plant and health data from Pinellas County to determine if an epidemiological study is technically feasible to measure possible off-site health effects from ionizing radiation. Through normal plant operations, some radioactive materials have been released to the environment. Eighty percent of the total plant releases of 107,707 curies occurred in the early years of plant operation (1957--1960). The primary materials released were tritium gas, tritium oxide and krypton-85. Environmental monitoring for radioactive releases from the plant has been done regularly since 1975. The US Public Health Service Centers for Disease Control and Prevention (CDC), in assisting HRS, has determined that sufficient radiological data exist by which a dose reconstruction can be done. A dose reconstruction can provide an estimate of how much radiological exposure someone living in the vicinity of the Pinellas Plant may have suffered from environmental releases

SNRIU nuclear installation modifications

International Nuclear Information System (INIS)

Goroshanskyi, Andrii

2013-01-01

Design stages of Nuclear Instalations (NI): NI design is performed in three stages: • Feasibility study: - Feasibility study is developed on the basis of the customer task for production facilities and linear facilities engineering and transport infrastructure that require detailed study of relevant decisions and identify options for and feasibility of construction. • Design: - The design is developed on the basis of design task, initial data and approved the previous stage under three-stage design. • Detailed documentation

Study of a conceptual nuclear energy center at Green River, Utah: regional considerations

International Nuclear Information System (INIS)

1982-01-01

This document constitutes one segment of a feasibility study investigating the ramifications of constructing a nuclear energy center in an arid and remote Western region. This phase of the study discusses regional considerations involved in nuclear energy center development at Green River, Utah. Regional support for NEC development is assessed. In addition, possible regulatory constraints to NEC development are identified and analyzed. Possible resource allocation shortages resulting from NEC development are also considered. A comparison with a similar study on NEC development in the Southeastern United States is also included

Nuclear Power Plant Lifetime Management Study (I)

Energy Technology Data Exchange (ETDEWEB)

Hong, Sung Yull; Jeong, Ill Seok; Jang, Chang Heui; Song, Taek Ho; Song, Woo Young [Korea Electric Power Research Institute, Taejon (Korea, Republic of); Jin, Tae Eun [Korea Power Engineering Company Consulting and Architecture Engineers, (Korea, Republic of); Kim, Woo Chul [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1997-12-31

As the operation-year of nuclear power plant increases and finding sites for new nuclear power plant becomes harder, a comprehensive and systematic nuclear plant lifetime management(PLIM) program including life extension has to be established for stable and safe supply of electricity. A feasibility study was conducted to systematically evaluate technical, economic and regulatory aspect of plant lifetime managements and plant life extension for Kori-1 nuclear power plant. For technical evaluation of nuclear power plant, 13 major components were selected for lifetime evaluation by screening system. structure, and components(SSCs) of the plant. It was found that except reactor pressure vessel, which needs detailed integrity analysis, and low pressure turbine, which is scheduled to be replaced, 11 out of 13 major components have sufficient service life, for more than 40 years. Because domestic rules and regulations related to license renewal has not yet been written, review on the regulatory aspect of life extensions was conducted using US NRC rules and regulations. A cooperative effort with nuclear regulatory body is needed for early completion of license renewal rules and regulations. For economic evaluation of plant lifetime extension, a computer program was developed and used. It was found that 10 to 20 year of extension operation of Kori-1 nuclear power plant was proved. Based on the results, next phase of plant lifetime management program for detailed lifetime evaluation and presenting detailed implementation schedule for plant refurbishment for lifetime extension should be followed. (author). 74 refs., figs.

Nuclear Power Plant Lifetime Management Study (I)

Energy Technology Data Exchange (ETDEWEB)

Hong, Sung Yull; Jeong, Ill Seok; Jang, Chang Heui; Song, Taek Ho; Song, Woo Young [Korea Electric Power Research Institute, Taejon (Korea, Republic of); Jin, Tae Eun [Korea Power Engineering Company Consulting and Architecture Engineers, (Korea, Republic of); Kim, Woo Chul [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1996-12-31

As the operation-year of nuclear power plant increases and finding sites for new nuclear power plant becomes harder, a comprehensive and systematic nuclear plant lifetime management(PLIM) program including life extension has to be established for stable and safe supply of electricity. A feasibility study was conducted to systematically evaluate technical, economic and regulatory aspect of plant lifetime managements and plant life extension for Kori-1 nuclear power plant. For technical evaluation of nuclear power plant, 13 major components were selected for lifetime evaluation by screening system. structure, and components(SSCs) of the plant. It was found that except reactor pressure vessel, which needs detailed integrity analysis, and low pressure turbine, which is scheduled to be replaced, 11 out of 13 major components have sufficient service life, for more than 40 years. Because domestic rules and regulations related to license renewal has not yet been written, review on the regulatory aspect of life extensions was conducted using US NRC rules and regulations. A cooperative effort with nuclear regulatory body is needed for early completion of license renewal rules and regulations. For economic evaluation of plant lifetime extension, a computer program was developed and used. It was found that 10 to 20 year of extension operation of Kori-1 nuclear power plant was proved. Based on the results, next phase of plant lifetime management program for detailed lifetime evaluation and presenting detailed implementation schedule for plant refurbishment for lifetime extension should be followed. (author). 74 refs., figs.

Feasibility and Competitiveness of the Further Nuclear Energy Production in Lithuania

International Nuclear Information System (INIS)

Gylys, S.; Ziedelis, S.; Klevas, V.

2006-01-01

The newest results gained during analysis of perspectives and technical - economical conditions of nuclear energy usage continuation in Lithuania are presented. After the compulsory premature closure of Ignalina NPP the negative power balance and the shortage of power generating capacity can emerge in the energy sector of Lithuania. This problem can arise already in 2010. Depending on rate of growth of economy the extent of shortage of power generating capacity can range from -50 MW to -583 MW with evident trend for further growing. The positive power balance could be restored if new nuclear power plant (NPP) or new combined cycle gas turbine power plants (CCGT PP) are erected. Feasibility and competitiveness of the new NPP and CCGT PP are compared, analysed and evaluated. Analysis is performed taking into account volume of investments for construction, level of discount rate, forecast of changes of the price of primary energy sources, possible loading level of a new power plant. At the case of low plant loading level (7000 hours per year) the electricity production costs are almost the same for NPP and for CCGT PP. However, increasing the plant's loading level up to 8000 hours per year changes the ratio of electricity production costs to positive for NPP. Comparison of expenses for fuel and total expenses shows unchallenged priority of NPP against CCGT PP. Estimating the forthcoming inevitable growth of price for natural gas, economic advantage of nuclear energy production seems to be obvious. The future energy balance for Baltic states, NORDEL countries, Germany and Russia is also analysed. Deficit of electricity is foreseen in Baltic states and NORDEL countries already after 2007, in Russia - after 2010. Even Central and South European countries (especially those, which are planning to cancel usage of nuclear energy) are forecasting shortage of electricity in 2015 - 2020 years. Such situation in European energy market could be treated as additional argument for

Feasibility study on the guided wave technique for condenser tube in NPP

International Nuclear Information System (INIS)

Choi, Sung Nam; Kim, Young Ho; Kim, Hyung Nam; Yoo, Hyun Joo; Hwang, W. G.

2004-01-01

The condenser tube is examined by the eddy current test (ECT) method to identify the integrity of the nuclear power plant. Because ECT probe is moved through the tube inside to identify flaws, the ECT probe should be exchanged periodically due to the wear of probe surface in order to remove the noise form the ECT signal. Moreover, it is impossible to examine the tube by ECT method because the ECT probe can not move through the inside due to the deformation such as dent. Recently, the theory of guided wave was established and the equipment applying the theory has been actively developed so as to overcome the limitation of ECT method for the tube inspection of heater exchanger in nuclear power plant. The object of this study is to know the feasibility of applying the guided wave technique to condenser tube in NPP

The use of a social network analysis technique to investigate the characteristics of crew communications in nuclear power plants-A feasibility study

International Nuclear Information System (INIS)

Park, Jinkyun

2011-01-01

Effective and reliable communications are very important in securing the safety of human-involved large process control systems because human operators have to accomplish their tasks in cooperative ways. This means that it is very important to understand the characteristics of crew communications, which can provide useful insights for preventing inappropriate communications. Unfortunately, in the nuclear industry, a systematic framework that can be used to identify the characteristics of crew communications seems to be rare. For this reason, the applicability of the social network analysis (SNA) technique to identifying the characteristics of crew communications was investigated in this study. To this end, the communication data of operating crews working in the main control room (MCR) of nuclear power plants (NPPs) were collected under two kinds of simulated off-normal conditions. Then the communication characteristics of MCR operating crews, which can be represented by the associated SNA metrics, were compared with communication characteristics that are already known from existing studies. As a result, it was found that SNA metrics could be meaningful for explaining the communication characteristics of MCR operating crews. Accordingly, it is expected that the SNA technique can be used as one of the serviceable tools to investigate the characteristics of crew communications in NPPs. - Highlights: → Communications are very important for the safety of complicated socio-technical systems. → A systematic framework to identify communication characteristics seems to be rare. → The feasibility of the social network analysis (SNA) technique was investigated. → It is expected that SNA metrics is meaningful for explaining communication characteristics.

Feasibility study on the business of collection and storage of waste from small producer of radioactive waste

International Nuclear Information System (INIS)

Ishiguro, Hideharu; Hayashi, Masaru; Senda, Masaki

2008-01-01

Radioactive Waste Management and Nuclear Facility Decommissioning Technology Center (RANDEC) has investigated the feasibility study on the business of collection and storage of many kinds of low level radioactive waste in radioactive facilities. This works include the total volume of waste, conceptual design of storage facility and cost estimation of construction and operation of this business. This paper describes the some points of the results of this study. (author)

A Study on Strategy Establishment for Foreign Market Penetrating of Nuclear Technology Venture Business

Energy Technology Data Exchange (ETDEWEB)

Song, Ki Dong; Kim, S. S.; Choi, Y. D.; Park, C. S.; Bae, C. I.; Chung, J. M.; Roe, S. P

2007-05-15

The objective of this study is to suggest feasible strategy for foreign market penetration of nuclear venture technology business. Especially, this study focuses on the technology and product export to the Frankfurt-Hoechst Industrial Park in Germany. This study analyzed the operating system of German Industrial Park, especially the Frankfurt-Hoechst Industrial Park. This study also analyzed the current status of Industrial Science Parks in Northern European countries such as Finland, Sweden, and England. Then, this study suggested the strategy for nuclear technology venture business to penetrate German export market effectively.

A Study on Strategy Establishment for Foreign Market Penetrating of Nuclear Technology Venture Business

International Nuclear Information System (INIS)

Song, Ki Dong; Kim, S. S.; Choi, Y. D.; Park, C. S.; Bae, C. I.; Chung, J. M.; Roe, S. P.

2007-05-01

The objective of this study is to suggest feasible strategy for foreign market penetration of nuclear venture technology business. Especially, this study focuses on the technology and product export to the Frankfurt-Hoechst Industrial Park in Germany. This study analyzed the operating system of German Industrial Park, especially the Frankfurt-Hoechst Industrial Park. This study also analyzed the current status of Industrial Science Parks in Northern European countries such as Finland, Sweden, and England. Then, this study suggested the strategy for nuclear technology venture business to penetrate German export market effectively

Feasibility analysis of constant TRU feeding in waste transmutation system using accelerator-driven subcritical system

Energy Technology Data Exchange (ETDEWEB)

Lee, Kun Jai; Cho, Nam Zin; Jo, Chang Keun; Park, Chang Je; Kim, Do Sam; Park, Jeong Hwan [Korea Advanced Institute of Science and Technology, Taejon (Korea)

1999-03-01

It is probable that the issue of nuclear spent fuel and high-level waste can have negative impact on the future expansion of nuclear power programs. Accelerator-driven nuclear waste transmutation with constant composition TRU feeding which satisfies non-proliferation condition will help establish the long-range nuclear waste disposal strategy. In this study, current status of accelerator-driven transmutation of waste technology, and feasibility analysis of constant composition TRU feeding system were investigated. We ascertained that solid system using constant composition TRU is feasible with the the capability of transmutation. (author). 13 refs., 53 figs., 20 tabs.

Results of FY 2002 of feasibility study on commercialized fast reactor cycle systems. Phase 2

International Nuclear Information System (INIS)

2003-06-01

Japan Nuclear Cycle Development Institute (JNC) and Japan Atomic Power Company (JAPC, that is the representative of the electric utilities in Japan) established a new organization to develop a commercialized fast reactor (FR) cycle system on July 1, 1999 and feasibility study (F/S) was undertaken in order to determine the promising concepts and to define the necessary R and D tasks. During Phase 1 (JFY 1999 and 2000), a number of candidate concepts were screened from various options, featuring innovative technologies. In the F/S, the options were evaluated and conceptual designs were examined considering the attainable perspectives for following: 1) ensuring safety, 2) economic competitiveness to future LWRs, 3) efficient utilization of resources, 4) reduction of environmental burden and 5) enhancement of nuclear non-proliferation. The F/S should also guide the necessary R and D to commercialize FR cycle system. To begin with the study of feasible candidate concepts screened in Phase I, Phase 2 started in the plan for five years in 2001. This aims at clarifying several feasible candidate concepts and deciding the research plan after Phase 3 as taking into consideration the innovative technology. As for this plan, an interim report will be carried out in 2003 as one pause and the prospect to clarify the feasible candidates will be expected. Furthermore, after the completion of this research and investigation program, research and development activities will be carried out under a rolling plan in which reviews will be carried out approximately every five years. The objective of these R and D activities is to make a proposal regarding highly attractive and competitive FR cycle system technology that assures safety by 2015. This report summarizes the results of F/S of Phase 2 in 2002. In 2002, the second year of Phase 2, the study was advanced along with the plan which was evaluated by the committee for the Evaluation. Then, in the study of FR system and fuel cycle

Advanced nuclear systems. Review study

International Nuclear Information System (INIS)

Liebert, Wolfgang; Glaser, Alexander; Pistner, Christoph; Baehr, Roland; Hahn, Lothar

1999-04-01

. On the basis of the detailed analysis it is shown: a decisive qualitative progress in these latter fields can rather not be expected for the nuclear systems which would be realizable in the nearer future (5-15 years), while the longer-termed development projects (like fusion or accelerator driven systems) reach out fundamental improvements, however of which cannot be said, whether they are actually going to be realizable. A fundamental question is, how the level of scientific knowledge in the field of advanced nuclear systems can be assessed in regard to comprehensive technology assessment studies. An enduring evaluation of some of these aspects, like operational safety and economy, only becomes possible when corresponding nuclear systems have already been realized and sufficient operational experience has been acquired. This means, that the current level of scientific knowledge is not sufficient to come to a supportable conclusion. First attempts are being made in the present study to identify those knowledge gaps relevant for assessment. A significant extension of the examination pattern appears to be indicated for subsequent more comprehensive technology assessment studies on advanced nuclear systems. We therefore suggest an extended set of criteria, which is supposed to be suitable at first for the detailed examination, then for assessment and finally for the shaping of the various feasible scientific-technical options, where applicable. A basis for more detailed studies on advanced nuclear systems is created thereby

Washoe Tribe Alternative Energy Feasibility Study Final Report

Energy Technology Data Exchange (ETDEWEB)

Johnson, Jennifer [Washoe Tribe of NV and CA

2014-10-01

The Washoe Tribe of Nevada and California was awarded funding to complete the Washoe Tribe Alternative Energy Feasibility Study project. The main goal of the project was to complete an alternative energy feasibility study. This study was completed to evaluate “the potential for development of a variety of renewable energy projects and to conduct an alternative energy feasibility study that determines which alternative energy resources have the greatest economic opportunity for the Tribe, while respecting cultural and environmental values” (Baker-Tilly, 2014). The study concluded that distributed generation solar projects are the best option for renewable energy development and asset ownership for the Washoe Tribe. Concentrating solar projects, utility scale wind projects, geothermal, and biomass resource projects were also evaluated during the study and it was determined that these alternatives would not be feasible at this time.

Do feasibility studies contribute to, or avoid, waste in research?

Science.gov (United States)

Morgan, Ben; Hejdenberg, Jennie; Hinrichs-Krapels, Saba; Armstrong, David

2018-01-01

In the context of avoiding research waste, the conduct of a feasibility study before a clinical trial should reduce the risk that further resources will be committed to a trial that is likely to 'fail'. However, there is little evidence indicating whether feasibility studies add to or reduce waste in research. Feasibility studies funded by the National Institute for Health Research's (NIHR) Research for Patient Benefit (RfPB) programme were examined to determine how many had published their findings, how many had applied for further funding for a full trial and the timeframe in which both of these occurred. A total of 120 feasibility studies which had closed by May 2016 were identified and each Principal Investigator (PI) was sent a questionnaire of which 89 responses were received and deemed suitable for analysis. Based on self reported answers from the PIs a total of 57 feasibility studies were judged as feasible, 20 were judged not feasible and for 12 it was judged as uncertain whether a full trial was feasible. The RfPB programme had spent approximately £19.5m on the 89 feasibility studies of which 16 further studies had been subsequently funded to a total of £16.8m. The 20 feasibility studies which were judged as not feasible potentially saved up to approximately £20m of further research funding which would likely to have not completed successfully. The average RfPB feasibility study took 31 months (range 18 to 48) to complete and cost £219,048 (range £72,031 to £326,830) and the average full trial funded from an RfPB feasibility study took 42 months (range 26 to 55) to complete and cost £1,163,996 (range £321,403 to £2,099,813). The average timeframe of feasibility study and full trial was 72 months (range 56 to 91), however in addition to this time an average of 10 months (range -7 to 29) was taken between the end of the feasibility study and the application for the full trial, and a further average of 18 months (range 13 to 28) between the

Preliminary feasibility study of the heat - pipe ENHS reactor

International Nuclear Information System (INIS)

Fratoni, M.; Kim, L.; Mattafirri, S.; Petroski, R.; Greenspan, E.

2007-01-01

This preliminary study assesses the feasibility of designing an Encapsulated Nuclear Heat Source (ENHS) reactor [1] to have a solid core from which heat is removed by liquid-metal heat pipes (HP). Like the SAFE space nuclear reactor core [2], the HP-ENHS core is comprised of fuel rods and HPs embedded in a solid structure arranged in a hexagonal lattice in a 3:1 ratio. The HPs extend beyond the core length and transfer heat to a secondary coolant that flows by natural circulation. The HP-ENHS reactor is designed to preserve many features of the ENHS reactor including 20-year operation without refueling, very small excess reactivity throughout life, natural circulation cooling, walk-away passive safety, and robust proliferation resistance. The target power level and specific power of the HP-ENHS reactor are those of the reference ENHS reactor [1]. Compared to previous ENHS reactor designs utilizing a lead or lead-bismuth alloy natural circulation cooling system, the HP-ENHS reactor offers a number of possible advantageous features including: (1) significantly enhanced decay heat removal capability; (2) no positive void reactivity coefficients; (3) no direct contact between the fuel clad and coolant, hence, relatively lower wet corrosion of the clad; (4) a core that is more robust for transportation; (5) higher temperature potentially offering higher efficiency and hydrogen production capability. The study focuses on four areas: material compatibility analysis, HP performance analysis, neutronic analysis and thermal-hydraulic analysis. Of four high-temperature structural materials evaluated, Mo TZM alloy is the preferred choice; its upper estimated feasible operating temperature is 1350 K. HP performance is evaluated as a function of working fluid type, operating temperature, wick design and HP diameter and length. Sodium is the preferred working fluid and the HP working temperature is 1300 K. The neutronic analysis found that it is possible to achieve criticality

A study of critical paths for feasibility studies of mining projects

International Nuclear Information System (INIS)

Sayadi, R.

2002-01-01

This work develops a model for design and realisation of profitability's and feasibility studies of a mining project. The model provides the structure of various necessary procedures to establish the feasibility studies and presents a logical system of task sequencing and information circulating between tasks. The specifications of mining projects, particularly their duration, complexity and high costs, necessitate design and realisation of feasibility study bases on the sufficient understanding of task behaviour and the critical path method view. For this purpose, critical paths with the highest frequency of occurrence were studied through several simulations. In addition, the critical tasks and sub tasks with the most probability were identified. The model introduced in this paper can serve as a perfect tool in feasibility study of a mining project. It can also be used as a basis of future development of mining software

White Earth Biomass/Biogas Feasibility Study

Energy Technology Data Exchange (ETDEWEB)

Triplett, Michael

2015-03-12

The White Earth Nation examined the feasibility of cost savings and fossil energy reduction through the installation of biogas/biomass boiler at the tribal casino. The study rejected biogas options due to availability and site constraints, but found a favorable environment for technical and financial feasibility of installing a 5 MMBtu hot water boiler system to offset 60-70 percent of current fuel oil and propane usage.

Establishment of nuclear data system - Feasibility study for neutron-beam= facility at pohang accelerator laboratory

Energy Technology Data Exchange (ETDEWEB)

Nam Kung, Won; Koh, In Soo; Cho, Moo Hyun; Kim, Kui Nyun; Kwang, Hung Sik; Park, Sung Joo [Pohang Accelerator Laboratory, Pohang (Korea, Republic of)

1996-12-01

Nuclear data which have been produced by a few developed countries in the= past are essential elements to many disciplines, especially to nuclear engineering. As we promote our nuclear industry further to the level of advanced countries, we also have to establish the Nuclear Data System to produce and evaluate nuclear data independently. We have studied the possibility to build a neutron-beam facility utilizing accelerator facilities, technologies and man powers at pohang Accelerator Laboratory. We found specific parameters for the PAL 100-MeV electron linac based on the existing klystron, modulator, accelerating tubes and other facilities in the PAL; the beam energy is 60-100 MeV, the beam current for the short pulse (10 ns) is 2 A and for the long pulse is 500 mA and the pulse repetition rate is 60 Hz. We propose a neutron-beam facility using PAL 100-MeV electron linac where we can use a Ta-target for the neutron generation and three different time-of-flight beam lines (10 m, 20 m, and 100 m). One may find that the proposed neutron-beam facility is comparable with other operating neutron facilities in the world. We conclude that the proposed neutron-beam facility utilizing the existing accelerator facility in the PAL would be an excellent facility for neutron data production in combination with the ` Hanaro` facility in KAERI. 8 refs., 11 tabs., 12 figs. (author)

Feasibility study on use of virtual collaborator for remote NPP control

International Nuclear Information System (INIS)

Kim, Jong Hyun; Lee, Seung Jun; Seong, Poong Hyun

2001-01-01

In this paper, we study the feasibility of Virtual Collaborator for Remote NPP Control as long-term research theme. And we present similar and related researches that are fulfilled at I and C laboratory in nuclear department of KAIST. Yoshikawa's laboratory, Kyoto University in Japan, is developing 'virtual collaborator', agent robot, which realized in virtual reality. Virtual Collaborator is a new type of human-machine interface which works as 'intelligent interface agent' to help machine operators manipulating large scale machine system such as power plant. The Virtual Collaborator is a sort of 'virtual robot' which behaves as if an intelligent agent robot in virtual space, who can communicate naturally with human like humans do with each other

A Study on Cost Allocation in Nuclear Power Coupled with Desalination

International Nuclear Information System (INIS)

Lee, ManKi; Kim, SeungSu; Moon, KeeHwan; Lim, ChaeYoung

2004-01-01

As for a single-purpose desalination plant, there is no particular difficulty in computing the unit cost of the water, which is obtained by dividing the annual total costs by the output of fresh water. When it comes to a dual-purpose plant, cost allocation is needed between the two products. No cost allocation is needed in some cases where two alternatives producing the same water and electricity output are to be compared. In these cases, the consideration of the total cost is then sufficient. This study assumes MED (Multi-Effect Distillation) technology is adopted when nuclear power is coupled with desalination. The total production cost of the two commodities in dual-purpose plant can easily be obtained by using costing methods, if the necessary raw data are available. However, it is not easy to calculate a separate cost for each product, because high-pressure steam plant costs cannot be allocated to one or the other without adopting arbitrary methods. Investigation on power credit method is carried out focusing on the cost allocation of combined benefits due to dual production, electricity and water. The illustrative calculation is taken from Preliminary Economic Feasibility Study of Nuclear Desalination in Madura Island, Indonesia. The study is being performed by BATAN (National Nuclear Energy Agency), KAERI (Korean Atomic Energy Research Institute) and under support of the IAEA (International Atomic Energy Agency) started in the year 2002 in order to perform a preliminary economic feasibility in providing the Madurese with sufficient power and potable water for the public and to support industrialization and tourism in Madura Region. The SMART reactor coupled with MED is considered to be an option to produce electricity and potable water. This study indicates that the correct recognition of combined benefits attributable to dual production is important in carrying out economics of desalination coupled with nuclear power. (authors)

Background studies in support of a feasibility assessment on the use of copper-base materials for nuclear waste packages in a repository in tuff

International Nuclear Information System (INIS)

Van Konynenburg, R.A.; Kundig, K.J.A.; Lyman, W.S.; Prager, M.; Meyers, J.R.; Servi, I.S.

1990-06-01

This report combines six work units performed in FY'85--86 by the Copper Development Association and the International Copper Research Association under contract with the University of California. The work includes literature surveys and state-of-the-art summaries on several considerations influencing the feasibility of the use of copper-base materials for fabricating high-level nuclear waste packages for the proposed repository in tuff rock at Yucca Mountain, Nevada. The general conclusion from this work was that copper-base materials are viable candidates for inclusion in the materials selection process for this application. 55 refs., 48 figs., 22 tabs

Background studies in support of a feasibility assessment on the use of copper-base materials for nuclear waste packages in a repository in tuff

Energy Technology Data Exchange (ETDEWEB)

Van Konynenburg, R.A. [Lawrence Livermore National Lab., CA (USA); Kundig, K.J.A.; Lyman, W.S.; Prager, M.; Meyers, J.R.; Servi, I.S. [CDA/INCRA Joint Advisory Group, Greenwich, CT (USA)

1990-06-01

This report combines six work units performed in FY`85--86 by the Copper Development Association and the International Copper Research Association under contract with the University of California. The work includes literature surveys and state-of-the-art summaries on several considerations influencing the feasibility of the use of copper-base materials for fabricating high-level nuclear waste packages for the proposed repository in tuff rock at Yucca Mountain, Nevada. The general conclusion from this work was that copper-base materials are viable candidates for inclusion in the materials selection process for this application. 55 refs., 48 figs., 22 tabs.

A feasibility study on worksite visualization system using augmented reality for Fugen NPP

International Nuclear Information System (INIS)

Izumi, Masanori; Shimoda, Hiroshi; Ishii, Hirotake

2010-01-01

Fugen Nuclear Power Plant, Advanced Thermal Reactor, was permanently shut down in March 2003 and it is at the decommissioning stage. Decommissioning Engineering Support System, DEXUS, has been developed to help planning of the optimal dismantling process and for carrying out the dismantling work safely and efficiently. Worksite Visualization System (WVS), as part of Dismantling Work Support System of DEXUS, has been developed to support the field workers to deal with the information on the dismantling facilities comprehensibly and intuitively. In this article, outline of the dismantling process of Fugen is first introduced, then a feasibility study on WVS is described. (author)

Planning for nuclear power in the Philippines

International Nuclear Information System (INIS)

Ibe, L.D.

1976-01-01

This article traces the events that led to nuclear power introduction in the Philippines starting from: the creation of National Science and Development Board and Philippine Atomic Energy Commission in 1958 under R.A. 2067; recruitment of young engineers, chemists and other scientists and their training here and abroad for the different specialized fields of nuclear energy; the creation of an inter-organizational Ad-Hoc Committee on Nuclear Power Study; initiation of a UNDP-IAEA supported Pre-Investment Study on Power Including Nuclear Power in Luzon in early 1964; enactment of R.A. 5207, the Philippine Nuclear Liability Act in 1968; second feasibility study in 1971; siting study by PAEC, NPC and MERALCO engineers; technical and economic study; organizational and financial study; and investment report. Upon receipt of the results of the feasibility studies on 31 July 1973, the President of the Philippines decided on the immediate implementation of the first nuclear plant project by the National Power Corporation (NPC). Licensing and regulation as well as manpower training with the aid of regional or international training agencies will be undertaken by PAEC

Nuclear waste disposal in space

Science.gov (United States)

Burns, R. E.; Causey, W. E.; Galloway, W. E.; Nelson, R. W.

1978-01-01

Work on nuclear waste disposal in space conducted by the George C. Marshall Space Flight Center, National Aeronautics and Space Administration, and contractors are reported. From the aggregate studies, it is concluded that space disposal of nuclear waste is technically feasible.

Feasibility study for the United Nuclear Corporation Disposal Site at the Oak Ridge Y-12 plant, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1991-02-01

In July 1990, the US Environmental Protection Agency (EPA) directed the Department of Energy Oak Ridge Operations to comply with Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) requirements for the remediation of the United Nuclear Corporation (UNC) Disposal Site located at the Y-12 Plant, Oak Ridge, Tennessee. EPA, Waste Management Branch, had approved a closure plan in December 1989 for the UNC Disposal Site. This feasibility study (FS) is a fully satisfy the National Oil and Hazardous Substances Contingency Plan (NCP) requirements for support of the selection of a remedial response for closure of the UNC Disposal Site. For two years the UNC Disposal Site accepted and disposed of waste from the decommissioning of a UNC uranium recovery facility in Wood River Junction, Rhode Island. Between June 1982 and November 1984, the UNC Disposal Site received 11,000 55-gal drums of sludge fixed in cement, 18,000 drums of contaminated soil, and 288 wooden boxes of contaminated building and process demolition materials. The FS assembles a wide range of remedial technologies so the most appropriate actions could be selected to remediate potential contamination to below MCLs and/or to below the maximum level of acceptable risk. Technologies were evaluated based on technical effectiveness, ease of implementation, and costs. Applicable technologies were then selected for alternative development. 33 refs., 9 figs., 27 tabs

Gasohol: economic feasibility study. Final report

Energy Technology Data Exchange (ETDEWEB)

David, M. L.; Hammaker, G. S.; Buzenberg, R. J.; Wagner, J. P.

1978-07-01

This report was prepared by Development Planning and Research Associates, Inc. under a contract with the Energy Research and Development Center of the University of Nebraska in cooperation with the Agricultural Products Industrial Utilization Committee and the State of Nebraska. Funding for this study was provided to the Energy Research and Development Center by the U.S. Department of Energy and the Old West Regional Commission. The primary objective of the study was to: determine the fiscal and market conditions under which the production of gasohol would be profitable for private producers. For purposes of this study, gasohol is a motor fuel consisting of 10 percent agriculturally-derived anhydrous ethanol and 90 percent unleaded gasoline. The study assumes that gasohol can be a fuel substitute for gasoline; indeed, the cost of gasoline will significantly influence that for gasohol. Gasoline prices are determined by factors external to ethanol; thus, the economic feasibility study of gasohol is in large part an economic feasibility study of fuel-grade ethanol production. More specifically, the study examined the following: the technical aspects of distributing, marketing, and using gasohol; the costs of the distribution and marketing of ethanol and gasohol; the energy balance of ethanol production; the cost of producing ethanol; the factors influencing ehtanol plant size and location; and the conditions that would make ethanol economicaly feasible for private producers.

Economic Analysis of Nuclear Energy

International Nuclear Information System (INIS)

Lee, Han Myung; Lee, M. K.; Moon, K. H.; Kim, S. S.; Lim, C. Y.; Song, K. D.; Oh, K. B.

2002-12-01

This study deals with current energy issues, environmental aspects of energy, project feasibility evaluation, and activities of international organizations. Current energy issues including activities related with UNFCCC, sustainable development, and global concern on energy issues were surveyed with focusing on nuclear related activities. Environmental aspects of energy includes various topics such as, inter- industrial analysis of nuclear sector, the role of nuclear power in mitigating GHG emission, carbon capture and sequestration technology, hydrogen production by using nuclear energy, Life Cycle Analysis as a method of evaluating environmental impacts of a technology, and spent fuel management in the case of introducing fast reactor and/or accelerator driven system. Project feasibility evaluation includes nuclear desalination using SMART reactor, and introduction of COMFAR computer model, developed by UNIDO to carry out feasibility analysis in terms of business attitude. Activities of international organizations includes energy planning activities of IAEA and OECD/NEA, introduction of the activities of FNCA, one of the cooperation mechanism among Asian countries. In addition, MESSAGE computer model was also introduced. The model is being developed by IAEA to effectively handle liberalization of electricity market combined with environmental constraints

Advanced nuclear systems. Review study; Fortgeschrittene Nuklearsysteme. Review Study

Energy Technology Data Exchange (ETDEWEB)

Liebert, Wolfgang; Glaser, Alexander; Pistner, Christoph [Interdisziplinaere Arbeitsgruppe Naturwissenschaft, Technik und Sicherheit (IANUS), Darmstadt University of Technology, Hochschulstrasse 10, D-64289 Darmstadt (Germany); Baehr, Roland; Hahn, Lothar [Institute for applied ecology (Oeko-Institut), Elisabethenstrasse 55-57, D-64283 Darmstadt (Germany)

1999-04-01

. On the basis of the detailed analysis it is shown: a decisive qualitative progress in these latter fields can rather not be expected for the nuclear systems which would be realizable in the nearer future (5-15 years), while the longer-termed development projects (like fusion or accelerator driven systems) reach out fundamental improvements, however of which cannot be said, whether they are actually going to be realizable. A fundamental question is, how the level of scientific knowledge in the field of advanced nuclear systems can be assessed in regard to comprehensive technology assessment studies. An enduring evaluation of some of these aspects, like operational safety and economy, only becomes possible when corresponding nuclear systems have already been realized and sufficient operational experience has been acquired. This means, that the current level of scientific knowledge is not sufficient to come to a supportable conclusion. First attempts are being made in the present study to identify those knowledge gaps relevant for assessment. A significant extension of the examination pattern appears to be indicated for subsequent more comprehensive technology assessment studies on advanced nuclear systems. We therefore suggest an extended set of criteria, which is supposed to be suitable at first for the detailed examination, then for assessment and finally for the shaping of the various feasible scientific-technical options, where applicable. A basis for more detailed studies on advanced nuclear systems is created thereby.

Feasibility and Pilot Studies in Palliative Care Research: A Systematic Review.

Science.gov (United States)

Jones, Terry A; Olds, Timothy S; Currow, David C; Williams, Marie T

2017-07-01

Feasibility and pilot study designs are common in palliative care research. Finding standard guidelines on the structure and reporting of these study types is difficult. In feasibility and pilot studies in palliative care research, to determine 1) how commonly a priori feasibility are criteria reported and whether results are subsequently reported against these criteria? and 2) how commonly are participants' views on acceptability of burden of the study protocol assessed? Four databases (OVID Medline, EMBASE, CINAHL, and PubMed via caresearch.com.au.) were searched. Search terms included palliative care, terminal care, advance care planning, hospice, pilot, feasibility, with a publication date between January 1, 2012 and December 31, 2013. Articles were selected and appraised by two independent reviewers. Fifty-six feasibility and/or pilot studies were included in this review. Only three studies had clear a priori criteria to measure success. Sixteen studies reported participant acceptability or burden with measures. Forty-eight studies concluded feasibility. The terms "feasibility" and "pilot" are used synonymously in palliative care research when describing studies that test for feasibility. Few studies in palliative care research outline clear criteria for success. The assessment of participant acceptability and burden is uncommon. A gold standard for feasibility study design in palliative care research that includes both clear criteria for success and testing of the study protocol for participant acceptability and burden is needed. Such a standard would assist with consistency in the design, conduct and reporting of feasibility and pilot studies. Copyright © 2017 American Academy of Hospice and Palliative Medicine. Published by Elsevier Inc. All rights reserved.

MONJU experimental data analysis and its feasibility evaluation to build up the standard data base for large FBR nuclear core design

International Nuclear Information System (INIS)

Sugino, K.; Iwai, T.

2006-01-01

MONJU experimental data analysis was performed by using the detailed calculation scheme for fast reactor cores developed in Japan. Subsequently, feasibility of the MONJU integral data was evaluated by the cross-section adjustment technique for the use of FBR nuclear core design. It is concluded that the MONJU integral data is quite valuable for building up the standard data base for large FBR nuclear core design. In addition, it is found that the application of the updated data base has a possibility to considerably improve the prediction accuracy of neutronic parameters for MONJU. (authors)

Feasibility study for core protection calculator development

International Nuclear Information System (INIS)

In, W. K.; Han, J. B.

2003-06-01

This project confirmed the development feasibility of new digital core protection system and established development plan for ITOPS that can replace the CPC system. The development plan and implementation strategy for ITOPS proposed in this project will be useful to successfully develop advanced digital core protection system for the CPC replacement in KSNP plants. YGN units 3 and 4 are expected to replace the CPC system within next ten years and the other KSNP plants are followed. The localization model for advanced digital core protection system, ITOPS, is judged to upgrade the Common Q CPC system in both system configuration and algorithm performance and can reduce the cost for supply and maintenance. Hence, ITOPS is expected to be installed in new Korea nuclear power plants and also useful to export the associated technology in the future

Nuclear waste information made accessible: A case study

International Nuclear Information System (INIS)

Willis, Y.A.; Morris, W.R.

1987-01-01

The Nuclear Industry has made great technical strides toward the safe and efficient management of nuclear waste but public acceptance and cooperation lag far behind. The challenge is to better inform the public of the technical options available to safely manage the various types of nuclear wastes. Westinghouse responded to this challenge by creating the Nuclear Waste Management Outreach Program with the goal to make nuclear waste information accessible as well as available. The Outreach Program is an objective informational seminar series comprises of modules which may be adopted to various audiences. The seminars deal with radioactive wastes and the legislative and regulatory framework within which the Industry must function. The Outreach Program provides a forum to present relevant information, encourage an interchange of ideas and experiences, elicit feedback, and it provides for field site visits where feasible and appropriate. The program has been well received by the participants including technologists, government officials, educators, and the general public

Study of heterogeneous nuclear reactor lattice properties in multizone systems

International Nuclear Information System (INIS)

Raisic, N.M.

1964-12-01

Described analysis of substitution experiments and its comparison with the classic procedures showed that it could be successfully applied for processing the experimental results. This method shows some advantages and some deficiencies compared to classic methods. Precision of the method is considered sufficient for design of nuclear facilities. Routine standards used in design of nuclear facilities demand following precision of nuclear parameters: about 5% during feasibility study and design of heavy water facility with natural uranium; 2 - 3% in the phase of parameters optimisation and preparing the main project; 1% during optimization of operation. Accuracy of core parameters obtained by analysis of substitution experiments show that they could be successfully used in the phase of reactor parameters optimisation. It is possible to increase the precision of critical parameters and thus apply the proposed method for analysis of reactor parameters needed in the phase of operation optimization

Feasibility Study on The Modulization of Structure and System Facility for Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Kim, K.S. [Korea Electric Power Research Institute, Taejon (Korea)

2002-07-01

This final report is a results of Study on applicable to SC(Steel Concrete) structure for NPPS and experimentation of SC wall-Support joint carried out by KEPRI from 2001.7.1 to 2000.3.27. The major objectives is to study on application of SC structure and behavior of SC wall-support joint. This result is applicable to plan a main project for ''Development of Modular Construction System in the Nuclear Power Plant''. (author). 45 refs., 19 figs., 23 tabs.

Design study of advanced nuclear fuel recycle system. Conceptual study of recycle system using molten salt

International Nuclear Information System (INIS)

Kakehi, I.; Shirai, N.; Hatano, M.; Kajitani, M.; Yonezawa, S.; Kawai, T.; Kawamura, F.; Tobe, K.; Takahashi, K.

1996-12-01

For the purpose of developing the future nuclear fuel recycle system, the design study of the advanced nuclear fuel recycle system is being conducted. This report describes intermediate accomplishments in the conceptual system study of the advanced nuclear fuel recycle system. Fundamental concepts of this system is the recycle system using molten salt which intend to break through the conventional concepts of purex and pellet fuel system. Contents of studies in this period are as follows, 1)feasibility study of the process by Cd-cathode for nitride fuel, 2)application study for the molten salt of low melting point (AlCl3+organic salt), 3)research for decladding (advantage of decladding by heat treatment), 4)behavior of FPs in electrorefining (behavior of iodine and volatile FP chlorides, FPs behavior in chlorination), 5)criticality analysis in electrorefiner, 6)drawing of off-gas flow diagram, 7)drawing of process machinery concept (cathode processor, vibration packing), 8)evaluation for the amounts of the high level radioactive wastes, 9)quality of the recycle fuels (FPs contamination of recycle fuel), 10)conceptual study of in-cell handling system, 11)meaning of the advanced nuclear fuel recycle system. The conceptual system study will be completed in describing concepts of the system and discussing issues for the developments. (author)

Feasibility study on the acquisition of licensee event data

International Nuclear Information System (INIS)

Kato, W.Y.; Hall, R.E.; Teichmann, T.; Taylor, J.; Luckas, W.J. Jr.; Saha, P.; Samanta, P.; Fragola, J.

1983-01-01

Objective of the study was to assess the feasibility of modifying the LER reporting system as proposed by NRC-AEOD, and/or developing an alternative plan that would in addition collect information about significant events amenable to statistical analysis, such as multi-case, multi-variate analysis. The study indicated that the LERs constitute reports from a large variety of events which have in most cases many different plant parameters, both measured and currently not measured, to characterize the event. In order to determine event-specific plant parameters required for statistical and deterministic analysis, a data matrix approach was used to identify those parameters which are currently being recorded, those which could be measured and recorded, and those which are required for certain types of events involving thermal-hydraulics and neutronics as illustrative of events requiring in-depth analysis. Also included in the study was a review of INPO's Nuclear Plant Reliability Data System; NASA's Problem Reporting and Corrective Action (PRACA) program; Electricite de France's KIT system, an automatic computer-based reactor parameter monitoring and recording system; and the regulatory relationship between the FAA and the commercial airline industry

Preliminary feasibility study on storage of radioactive wastes in Columbia River basalts. Volume I

International Nuclear Information System (INIS)

1976-11-01

Geologic, hydrologic, heat transfer and rock-waste compatibility studies conducted by the Atlantic Richfield Hanford Company to evaluate the feasibility of storing nuclear wastes in caverns mined out into the Columbia River basalts are discussed. The succession of Columbia River Plateau flood basalts was sampled at various outcrops and in core holes and the samples were analyzed to develop a stratigraphic correlation of the various basalt units and sedimentary interbeds. Hydrologic tests were made in one bore hole to assess the degree of isolation in the various deep aquifers separated by thick basalt accumulations. Earthquake and tectonic studies were conducted to assess the tectonic stability of the Columbia River Plateau. Studies were made to evaluate the extent of heat dissipation from stored radioactive wastes. Geochemical studies were aimed at evaluating the compatibility between the radioactive wastes and the basalt host rocks. Data obtained to-date have allowed development of a hydrostratigraphic framework for the Columbia River Plateau and a preliminary understanding of the deep aquifer systems. Finally, the compilation of this information has served as a basis for planning the studies necessary to define the effectiveness of the Columbia River basalts for permanently isolating nuclear wastes from the biosphere

Technological studies on uranium refining at nuclear materials authority, Egypt

International Nuclear Information System (INIS)

Mohammed, H.S.

1997-01-01

In 1992 nuclear materials authority (NMA) took a decision to establish yellow cake refining. Unit so as to study refining of El-Atshan yellow cake which recently produced by ion-exchange pilot plant, production sector. The research studies followed the conventional refining rout to produce nuclear grade UO 3 . This implies investigations on some common solvents to refine the cake viz. tri alkyl phosphates, tri alkyl phosphine oxides, dialkyl phosphoric acid as well as high-molecular weight long-chain tertiary amines. Moreover, non-conventional refining process has also been presented depending on the selectivity of uranyl ion to be dissolved by carbonate and to be precipitated by hydrogen peroxide. Most of the proposed processes were found feasible to refine El-Atshan yellow cake. however, the non- conventional refining process appears to be the most promising, owing to its superior performance and economy

Geohydrological studies for nuclear waste isolation at the Hanford Reservation. Volume I. Executive summary

International Nuclear Information System (INIS)

Apps, J.; Doe, T.; Doty, B.

1979-08-01

A study of the hydrology of the Pasco Basin near Richland, Washington, was initiated during FY 1978 as part of a long-term study on the feasibility of nuclear waste disposal in the Columbia River Basalt underlying the Hanford Reservation. This report summarizes the hydrology field program, Pasco Basin modeling, and groundwater chemistry program. Hanford well logs are also reviewed

Technical design aspects of Feasibility Study-II

International Nuclear Information System (INIS)

Zisman, Michael S.

2001-01-01

Feasibility Study-II examined a high-performance Neutrino Factory providing 1 x 10 20 neutrinos per year aimed at a long-baseline detector. The Study was sponsored jointly by BNL and the Neutrino Factory and Muon Collider Collaboration ration (MC) and is based on a 1 MW proton driver operating at 24 GeV, i.e., an upgraded version of the AGS accelerator. Compared with the earlier FNAL-sponsored study (Feasibility Study-I), there is a sixfold improvement in performance. Here we describe details of the implementation of Study-II concepts and discuss their efficacy. Alternative approaches that will be pursued in follow-on R and D activities are also described briefly

Technology transfer on long-term radioactive waste management - a feasible option for small nuclear programmes?

International Nuclear Information System (INIS)

Mele, I.; Mathieson, J.

2007-01-01

The EU project CATT - Co-operation and technology transfer on long-term radioactive waste management for Member States with small nuclear programmes investigated the feasibility of countries with small nuclear programmes implementing long-term radioactive waste management solutions within their national borders, through collaboration on technology transfer with those countries with advanced disposal concepts. The main project objective was to analyse the existing capabilities of technology owning Member States and the corresponding requirements of potential technology acquiring Member States and, based on the findings, to develop a number of possible collaboration models and scenarios that could be used in a technology transfer scheme. The project CATT was performed as a specific support action under the EU sixth framework programme and it brought together waste management organisations from six EU Member States: UK, Bulgaria, Germany, Lithuania, Slovenia and Sweden. In addition, the EC Joint Research Centre from the Netherlands also participated as a full partner. The paper summarises the analyses performed and the results obtained within the project. (author)

Feasibility study for CPR1000 incore measurement instrumentation educed from the reactor pressure vessel upper head

International Nuclear Information System (INIS)

Guang Jianwei; Liu Qian; Li Wenhong; Duan Yuangang

2010-01-01

The article discusses about the feasibility of in-core measurement instrumentation educed from the reactor pressure vessel (RPV) upper head. Incore instrumentation educed from the reactor pressure vessel upper head is one of advanced technology in the third generation nuclear power plant. This technology can reduce the manufacture problem of RPV; decrease the manufacture time effectively. Furthermore, this technology can get rid of the trouble for loss of water caused by many penetrations in the RPV bottom head, can increase security of nuclear power plant. By the description of structure analysis, comparison, maturity for four type incore instrumentation detectors, the incore instrumentation can be educed from RPV upper head, which can increase reactor's security, reduce the manufacture time, decrease group dose in refueling period. The core design ability can be enhanced through this study. (authors)

Conceptual Thermal Treatment Technologies Feasibility Study

International Nuclear Information System (INIS)

Suer, A.

1996-01-01

This report presents a conceptual Thermal Treatment Technologies Feasibility Study (FS) for the Savannah River Site (SRS) focusing exclusively on thermal treatment technologies for contaminated soil, sediment, or sludge remediation projects

Nuclear power plants - active environment protection|

International Nuclear Information System (INIS)

Aegerter, I.

1987-01-01

The Federal Commission, which is studying energy scenarios, will doubtlessly come to the conclusion that a withdrawal from nuclear energy is technically and economically feasible. Feasibility alone however is no justification for action. Have the questions been asked correctly by the parliamentarians? Are the real problems being bypassed? Is the demand for a withdrawal from nuclear energy soundly based? Is it not oversimplified? Many people are afraid of nuclear energy because they do not understand it. It is necessary that specialists formulate their ideas so that the layman can easily understand them. The broad public can be educated to lose their fear of nuclear power plants which they compare with the nuclear bombs. They can also be educated to lose their fear of radioactivity. The public should also realize that the CO 2 problem is actual and very serious, and that nuclear energy can in fact help to alleviate this particular problem. 7 refs., 2 figs., 1 tab

Feasibility study on large pool-type LMFBR

International Nuclear Information System (INIS)

1984-01-01

A feasibility study has been conducted from 1981 FY to 1983 FY, in order to evaluate the feasibility of a large pool-type LMFBR under the Japanese seismic design condition and safety design condition, etc. This study was aimed to establish an original reactor structure concept which meets those design conditions especially required in Japan. In the first year, preceding design concepts had been reviewed and several concepts were originated to be suitable to Japan. For typical two of them being selected by preliminary analysis, test programs were planned. In the second year, more than twenty tests with basic models had been conducted under severe conditions, concurrently analytical approaches were promoted. In the last year, larger model tests were conducted and analytical methods have been verified concerning hydrodynamic effects on structure vibration, thermo-hydraulic behaviours in reactor plena and so on. Finally the reactor structure concepts for a large pool-type LMFBR have been acknowledged to be feasible in Japan. (author)

Dual-gated cardiac PET-clinical feasibility study

Energy Technology Data Exchange (ETDEWEB)

Teraes, Mika; Kokki, Tommi; Noponen, Tommi; Hoppela, Erika; Sipilae, Hannu T.; Knuuti, Juhani [Turku PET Centre, PO BOX 52, Turku (Finland); Durand-Schaefer, Nicolas [General Electric Medical Systems, Buc (France); Pietilae, Mikko [Turku University Hospital, Department of Internal Medicine, Turku (Finland); Kiss, Jan [Turku University Hospital, Department of Surgery, Turku (Finland)

2010-03-15

Both respiratory and cardiac motions reduce image quality in myocardial imaging. For accurate imaging of small structures such as vulnerable coronary plaques, simultaneous cardiac and respiratory gating is warranted. This study tests the feasibility of a recently developed robust method for cardiac-respiratory gating. List-mode data with triggers from respiratory and cardiac cycles are rearranged into dual-gated segments and reconstructed with standard algorithms of a commercial PET/CT scanner. Cardiac gates were defined as three fixed phases and one variable diastolic phase. Chest motion was measured with a respiratory gating device and post-processed to determine gates. Preservation of quantification in dual-gated images was tested with an IEC whole-body phantom. Minipig and human studies were performed to evaluate the feasibility of the method. In minipig studies, a coronary catheter with radioactive tip was guided in coronary artery for in vivo and ex vivo acquisitions. Dual gating in humans with suspected cardiac disorders was performed using 18-F-FDG as a tracer. The method was found feasible for in vivo imaging and the radioactive catheter tip was better resolved in gated images. In human studies, the dual gating was found feasible and easy for clinical routine. Maximal movement of myocardial surface in cranio-caudal direction was over 20 mm. The shape of myocardium was clearly different between the gates and papillary muscles become more visible in diastolic images. The first clinical experiences using robust cardiac-respiratory dual gating are encouraging. Further testing in larger clinical populations using tracers designed especially for plaque imaging is warranted. (orig.)

Dual-gated cardiac PET-clinical feasibility study

International Nuclear Information System (INIS)

Teraes, Mika; Kokki, Tommi; Noponen, Tommi; Hoppela, Erika; Sipilae, Hannu T.; Knuuti, Juhani; Durand-Schaefer, Nicolas; Pietilae, Mikko; Kiss, Jan

2010-01-01

Both respiratory and cardiac motions reduce image quality in myocardial imaging. For accurate imaging of small structures such as vulnerable coronary plaques, simultaneous cardiac and respiratory gating is warranted. This study tests the feasibility of a recently developed robust method for cardiac-respiratory gating. List-mode data with triggers from respiratory and cardiac cycles are rearranged into dual-gated segments and reconstructed with standard algorithms of a commercial PET/CT scanner. Cardiac gates were defined as three fixed phases and one variable diastolic phase. Chest motion was measured with a respiratory gating device and post-processed to determine gates. Preservation of quantification in dual-gated images was tested with an IEC whole-body phantom. Minipig and human studies were performed to evaluate the feasibility of the method. In minipig studies, a coronary catheter with radioactive tip was guided in coronary artery for in vivo and ex vivo acquisitions. Dual gating in humans with suspected cardiac disorders was performed using 18-F-FDG as a tracer. The method was found feasible for in vivo imaging and the radioactive catheter tip was better resolved in gated images. In human studies, the dual gating was found feasible and easy for clinical routine. Maximal movement of myocardial surface in cranio-caudal direction was over 20 mm. The shape of myocardium was clearly different between the gates and papillary muscles become more visible in diastolic images. The first clinical experiences using robust cardiac-respiratory dual gating are encouraging. Further testing in larger clinical populations using tracers designed especially for plaque imaging is warranted. (orig.)

Feasibility Study: New Knowledge Demands in Turbulent Business World

Science.gov (United States)

Sprice, Renate; Kirikova, Marite

Feasibility study is one of the early activities in information systems (IS) development when important decisions regarding choice among several possible systems development alternatives are to be made. In times of relatively stable business environment and waterfall model as a systems development approach, the role and methods of feasibility study where quite clear (Kendall and Kendall 1995). However, new software development methods and the necessity to develop more rapidly new IS or their parts may. challenge the possibility to evaluate project feasibility in the early stages of IS development.

Feasibility study of the application of biotechnology to nuclear waste treatment

International Nuclear Information System (INIS)

Ashley, N.V.; Pope, N.R.; Roach, D.J.W.

1987-12-01

A number of biotechnology areas applicable to the removal of radionuclides from industrial nuclear effluents were considered, namely: use of Biopolymers; Biosorption using biomass; microbial leaching and solubilisation of metal ions. The potential of biomagnetic separation technology, genetic engineering and monoclonal antibody technology was also examined. It appeared that the most appropriate technologies to develop for radionuclide removal in the short term were based on biosorptions of radionuclides by biomass and modified and unmodified biopolymers. (author)

Feasibility study of power reactor fuel elements factory development: I. Economical aspects

International Nuclear Information System (INIS)

Marwoto; Ratih-Langenati, R.R.; Susanti, P.

1996-01-01

For determining the feasibility study on manufacturing nuclear fuel element from economical aspect point of view, it necessary to fix its capacity which it was found from fuel element reloading requirement for nuclear power plat (PLTN). NEWJEC report which use as a base in this study that is possibly of a complex of NPP as big as 7200 MW in Muria region. If the capacity factor is 80 %, the reload requirement is therefore become from 120 to 142 tons uranium every year. So, its considered to fix the nominal capacity of a fabric for nuclear fuel element manufacturing as much as 200 tons-U per year with economical lifetimes of 20 years. NEWJEC data show, for manufacturing capacity of 200 tons-U per year with, plant have a fixed capital investment of US$ 43.9 million. With working capital as much as 15 % correspond to fixed capital investment (FCI); 10 % of interest rate; US$ 17 million of fixed cost; US$ 106.2/kg-U of variable production cost, its calculated that break even point/BEP is 50 % for price of nuclear fuel is US$ 350/kg-U without uranium cost. On this economic condition, it was found that the return on investment/ROI is 20.2 %; the internal rate of return/IRR is 11.2 % and the benefit cost ration/BCR is 1.22. For all of above, it was assumed that such nuclear fuel element manufacturing service will be operate in the year of 2012. Some of NEWJEC data have been revised, there were the value of FCI; cost of salary; the value in percent of working capital/WC; the cost of non-uranium materials and the price of product service are US$ 68 million; US$ 4.1 million; 30 %; US$ 100/kg-U and US$ 370/kg-U respectively, where the new data appear as higher than old date from NEWJEC, excluding the cost of salary. For all new economical data in the latest, we found that 45 %; 16.73 %; 11.8 % and 1.25 for BEB; IRR and BCR respectively

Solid state nuclear magnetic resonance studies of prion peptides and proteins

Energy Technology Data Exchange (ETDEWEB)

Heller, Jonathan [Univ. of California, Berkeley, CA (United States)

1997-08-01

High-resolution structural studies using x-ray diffraction and solution nuclear magnetic resonance (NMR) are not feasible for proteins of low volubility and high tendency to aggregate. Solid state NMR (SSNMR) is in principle capable of providing structural information in such systems, however to do this efficiently and accurately, further SSNMR tools must be developed This dissertation describes the development of three new methods and their application to a biological system of interest, the priori protein (PrP).

COLD-SAT feasibility study safety analysis

Science.gov (United States)

Mchenry, Steven T.; Yost, James M.

1991-01-01

The Cryogenic On-orbit Liquid Depot-Storage, Acquisition, and Transfer (COLD-SAT) satellite presents some unique safety issues. The feasibility study conducted at NASA-Lewis desired a systems safety program that would be involved from the initial design in order to eliminate and/or control the inherent hazards. Because of this, a hazards analysis method was needed that: (1) identified issues that needed to be addressed for a feasibility assessment; and (2) identified all potential hazards that would need to be controlled and/or eliminated during the detailed design phases. The developed analysis method is presented as well as the results generated for the COLD-SAT system.

Feasibility study of networks. Progress report, July 15, 1975--July 14, 1976

International Nuclear Information System (INIS)

Campbell, E.J.; Kannel, M.; Saffran, K.

1976-01-01

The Laboratory for Nuclear Science has continued its study into the feasibility of networks, changing the focus of the investigation from the possible ways of collaborating with the MIT Information Processing Center in implementing a connection to the ARPA net to a wider consideration of the implications of computer resource sharing via networks. This report describes experiments performed on the ARPA net in collaboration with the Lawrence Berkeley Laboratory and experiments in more conventional forms of remote job entry to that site and others in ERDA. It discusses the use of the Multics mail as set up for ERDA, comparing it to other mail systems. Plans for future experiments in the ARPA net and for investigation of networks other than the ARPA net are proposed. The conclusion was reached that resource sharing via networks is both feasible and desirable provided certain interface problems are solved. Recommendations are made for more investigation into the human factors involved in network use, methods of providing consulting help to users, and determination of the most cost effective use of remote resource sharing. For the Laboratory for Nuclear Science, it is concluded that access to other ERDA computers via networks will meet some of our computing needs now and more in the future. However, remote resource sharing can be used only to supplement the on site computer, not replace it. At the present time, the best method of accessing the ARPA net for our users is via the MIT Multics System. However, as a permanent solution, a mini-host located in our computer center may provide more capability. In the next year, we plan to work out methods of attacking the problems of interfacing to the ARPA net and to use it in a limited manner for actual production work

Feasibility study of networks. Progress report, July 15, 1975--July 14, 1976

Energy Technology Data Exchange (ETDEWEB)

Campbell, E.J.; Kannel, M.; Saffran, K.

1976-04-30

The Laboratory for Nuclear Science has continued its study into the feasibility of networks, changing the focus of the investigation from the possible ways of collaborating with the MIT Information Processing Center in implementing a connection to the ARPA net to a wider consideration of the implications of computer resource sharing via networks. This report describes experiments performed on the ARPA net in collaboration with the Lawrence Berkeley Laboratory and experiments in more conventional forms of remote job entry to that site and others in ERDA. It discusses the use of the Multics mail as set up for ERDA, comparing it to other mail systems. Plans for future experiments in the ARPA net and for investigation of networks other than the ARPA net are proposed. The conclusion was reached that resource sharing via networks is both feasible and desirable provided certain interface problems are solved. Recommendations are made for more investigation into the human factors involved in network use, methods of providing consulting help to users, and determination of the most cost effective use of remote resource sharing. For the Laboratory for Nuclear Science, it is concluded that access to other ERDA computers via networks will meet some of our computing needs now and more in the future. However, remote resource sharing can be used only to supplement the on site computer, not replace it. At the present time, the best method of accessing the ARPA net for our users is via the MIT Multics System. However, as a permanent solution, a mini-host located in our computer center may provide more capability. In the next year, we plan to work out methods of attacking the problems of interfacing to the ARPA net and to use it in a limited manner for actual production work.

Self-sustaining nuclear pumped laser-fusion reactor experiment

International Nuclear Information System (INIS)

Boody, F.P.; Choi, C.K.; Miley, G.H.

1977-01-01

The features of a neutron feedback nuclear pumped (NFNP) laser-fusion reactor equipment were studied with the intention of establishing the feasibility of the concept. The NFNP laser-fusion concept is compared schematically to electrically pumped laser fusion. The study showed that, once a method of energy storage has been demonstrated, a self-sustaining fusion-fission hybrid reactor with a ''blanket multiplication'' of two would be feasible using nuclear pumped Xe F* excimer lasers having efficiencies of 1 to 2 percent and D-D-T pellets with gains of 50 to 100

An investigation into the technical feasibility of cyclotron production of technetium-99m

International Nuclear Information System (INIS)

Egan, G.F.; Lagunas-Solar, M.C.

1994-01-01

The role of technetium-99m in nuclear medicine is well established with 80 per cent to 90 per cent of all nuclear medicine studies utilising this isotope. Technetium-99m is currently produced from nuclear reactors via production of the parent radionuclide molybdenum-99. The reactor production of 99m Tc has both significant financial and environmental costs, with unresolved problems in the areas of radioactive waste disposal and reactor decommissioning. Recent scientific publications have indicated that medical quality 99m Tc may be produced using cyclotrons without having the associated problems of waste disposal and decommissioning. Further scientific research is now required to demonstrate the feasibility of this cyclotron production technique. A collaboration between the Cyclotron and PET Centre, Austin Hospital, the National Medical Cyclotron, ANSTO, Sydney, and the Crocker Nuclear Laboratory, University of California, Davis, USA has been proposed. The general objective of the proposed collaboration is to acquire additional scientific data to evaluate the 99m Tc cyclotron production method and to determine the feasibility of cyclotron technology for Australian nuclear medicine. 16 refs., 2 tabs

An investigation of the feasibility of building a harbor on the West coast of South America using explosive power of nuclear weapons, a preliminary report

Energy Technology Data Exchange (ETDEWEB)

Zodtner, H. H.

1971-12-31

There is an interest in discovering the various peace time uses of nuclear explosives. One of the proposals is the building of harbors. There are several ports along the west coast of South America where lighterage is necessary. This implies a need for expanded harbor facilities. The problem is to find a good location for creating a harbor, and the feasibility of accomplishing this with the use of nuclear force. Feasibility includes blast effects, radiation hazards, the number of weapons needed, and economic considerations. Economic considerations include the cost of treating a harbor of sufficient depth and area, the building of harbor facilities, and the estimated savings and advantages of the new harbor. Several meetings were held with naval personnel of the Military Liaison group at UCRL to discuss the general problems of harbors. Thirty-three different ports were given a preliminary investigation.

Feasibility study of medical isotope production at Sandia National Laboratories

International Nuclear Information System (INIS)

Massey, C.D.; Miller, D.L.; Carson, S.D.

1995-12-01

In late 1994, Sandia National Laboratories in Albuquerque, New Mexico, (SNL/NM), was instructed by the Department of Energy (DOE) Isotope Production and Distribution Program (IPDP) to examine the feasibility of producing medically useful radioisotopes using the Annular Core Research Reactor (ACRR) and the Hot Cell Facility (HCF). Los Alamos National Laboratory (LANL) would be expected to supply the targets to be irradiated in the ACRR. The intent of DOE would be to provide a capability to satisfy the North American health care system demand for 99 Mo, the parent of 99m Tc, in the event of an interruption in the current Canadian supply. 99m Tc is used in 70 to 80% of all nuclear medicine procedures in the US. The goal of the SNL/NM study effort is to determine the physical plant capability, infrastructure, and staffing necessary to meet the North American need for 99 Mo and to identify and examine all issues with potential for environmental impact

Delegated Democracy. The Siting of Swedish Nuclear Waste

Energy Technology Data Exchange (ETDEWEB)

Johansson, Hanna Sofia (Stockholm Univ., SCORE, SE-106 91 Stockholm (Sweden))

2009-12-15

This paper aims to characterise Swedish democracy in connection with the disposal of Swedish nuclear waste. To this end, an analysis is performed to discern which democratic ideals that can be found within the nuclear waste issue. The study analyses various actors' views on democracy and expertise as well as their definitions of the nuclear waste issue, and discusses this from the perspective of democracy theory. Which definitions that become influential has democratic implications. In addition, various actors' possible attempts to help or hinder other actors from gaining influence over the nuclear waste issue in the four municipalities are studied. In connection with the case studies the aim of the paper can be narrowed to comprise the following questions: Which democratic ideals can be found within SKB's siting process during the feasibility studies and in the consultation process during the site investigations? Which democratic ideals were influential during the feasibility studies and in the consultation process?

Delegated Democracy. The Siting of Swedish Nuclear Waste

International Nuclear Information System (INIS)

Johansson, Hanna Sofia

2009-12-01

This paper aims to characterise Swedish democracy in connection with the disposal of Swedish nuclear waste. To this end, an analysis is performed to discern which democratic ideals that can be found within the nuclear waste issue. The study analyses various actors' views on democracy and expertise as well as their definitions of the nuclear waste issue, and discusses this from the perspective of democracy theory. Which definitions that become influential has democratic implications. In addition, various actors' possible attempts to help or hinder other actors from gaining influence over the nuclear waste issue in the four municipalities are studied. In connection with the case studies the aim of the paper can be narrowed to comprise the following questions: Which democratic ideals can be found within SKB's siting process during the feasibility studies and in the consultation process during the site investigations? Which democratic ideals were influential during the feasibility studies and in the consultation process?

The environmental energy sector programme. Poland: Feasibility study

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-07-01

The Danish Ministry of Energy has granted financial aid to the preparation of a feasibility study necessary for the procurement of a financial solution to the modernisation of the combined heat and power plant in the city of Zielona Gora.The overall objectives of the Feasibility Study are to: establish new efficient power capacity in the south-west region of Poland, increase the energy efficiency, reduce the impact on the environment, utilise the local natural gas available which cannot be used in the national gas grid and reduce the costs of energy supply.The specific objective of this feasibility study is to obtain the best possible financing of the erection of a new CPH plant in Zielona Gora. The plant shall be designed to utilise the local resources of natural gas and to supply heat to the district heating grid in accordance with long-term planning strategies. (EHS)

An assessment of the feasibility of indefinite containment of Canadian nuclear fuel wastes

International Nuclear Information System (INIS)

Shoesmith, D.W.; King, F.; Ikeda, B.M.

1995-05-01

This report presents an analysis of the expected corrosion behaviour of nuclear fuel waste containers in a conceptual Canadian disposal vault. The container materials considered are dilute Ti alloys (Grades-2, -12 and -16) and oxygen-free copper. The corrosive conditions within the disposal vault change with time as the initially trapped oxygen is consumed and as the heat and γ-radiation produced by the waste decays. This evolution of the vault environment is broadly classified into an early, warm and oxidizing period followed by a period of long-term, stable, cool and non-oxidizing conditions. The corrosion behaviour of both types of material during these two periods is discussed, and various models that have been developed to predict the lifetimes of the containers are presented. The conclusion is that indefinite containment of the waste is feasible with both copper and titanium alloys under Canadian disposal conditions. (author). refs., tabs., figs

Investigation of the potential of wind energy applications in the Sct. Petersburg region. Pre-feasibility study report. Phase 1

International Nuclear Information System (INIS)

1995-11-01

It was proposed to initiate an investigation and, if found to be viable, a feasibility study of the possibilities for partly substituting and supplementing the existing nuclear and fossil fuel based energy supply of the St. Petersburg region with environmentally benign wind energy. The feasibility study is expected to lead to one or more pilot projects. The proposal outlines a three-phased project including an investigation, a feasibility study and a full scale demonstration of wind energy in this region. A 4th phase is envisaged, and this will include the large scale introduction of wind energy applications using national and international financing and resulting in increased local production. The report covers the first phase, the investigation which includes data acquisition and desk studies. It is shown that technically exploitable wind potential exists in the St. Petersburg region, that local production of wind turbine equipment will reduce wind turbine costs due to decreased transport costs and lower local salaries, that suitable sites for the demonstration of both grid-connected wind farms and wind-diesel systems have been preliminarily identified and that the demonstration plants investigated have exhibited reasonable economic parameters - IRR in the range of 9 - 15%. But a feasibility study phase (2) including engineering and economic analyses must be carried out in order to reach the necessary detailed understanding of the technical and economic implications of full scale demonstration projects. (EG)

Does Britain need nuclear weapons?

International Nuclear Information System (INIS)

Hill, C.R.; Pease, R.S.; Peierls, R.E.; Rotblat, J.

1995-01-01

This report from the British Pugwash Group follows up a detailed international study of the desirability and feasibility of a world free from nuclear weapons with an analysis of issues particular to British nuclear weapons and the associated defense policies. United Kingdom nuclear weapons are reviewed historically, as are the nuclear weapons policies of other countries. A critique of present government policy is presented, with alternative uses for nuclear weapons in the post-Cold war world. The document concludes with a summary of the text and suggests how a British government could move towards global nuclear disarmament. (UK)

High temperature reactor and helium turbine for naval propeller (Study of feasibility and performances of the system)

International Nuclear Information System (INIS)

Brisbois, J.; Malherbe, J.; Rastoin, J.; Courau; Metayer.

1976-01-01

The nuclear reactor HTGR can get an outlet helium temperature greater than 800 deg C. That gives the means to use an helium turbine in a direct cycle. This type of reactor has been studied for a supply-ship (25,000t, 85,000Cv) and feasibility of such a system can be proved without employing any unknown materials. Because the weakness of helium activity, only the core can be shielded. All the propeller system is inside a containment which has to stand with a small over pressure after a core depressurisation. An efficiency of 35% is realized in a compact set up. This nuclear propeller get a very long core life 860FPD with constant worth- and very flexible working conditions. The HTGR direct cycle make a naval propeller very attractive [fr

Green technology into nuclear industry Eligibility of Ambidexter nuclear complex for a generation IV nuclear power system

International Nuclear Information System (INIS)

Park, Kwangheon; Koh, Moosung; Ryu, Jeongdong; Kim, Yangeun; Lee, Bumsik; Park, Hyuntack

2000-01-01

Green power is being developed up to a point that is feasible not only in an environmental sense, but also in an economical viewpoint. This paper introduces two case studies that applied green technology into nuclear industry. 1) Nuclear laundry: A laundry machine that uses liquid and supercritical Co 2 as a solvent for decontamination of contaminated working dresses in nuclear power plants was developed. The machine consists of a 16 liter reactor, a recovery system with compressors, and storage tanks. All CO 2 used in cleaning is fully recovered and reused in next cleaning, resulting in no production

Identification of seismically risk-sensitive systems and components in nuclear power plants: feasibility study

International Nuclear Information System (INIS)

Azarm, M.; Boccio, J.; Farahzad, P.

1983-06-01

An approach for the identification of risk-sensitive components in a nuclear power plant during and after a seismic event is described. Application of the methodology to two hypothetical power plants - a Boiling Water Reactor and a Pressurized Water Reactor - are presented and the results are given in tabular and graphical form. Conclusions drawn and lessons learned through the course of this study, based on the relative importance of various accident scenarios and sensitivity analyses, are discussed. In addition, the areas that may need further investigation are identified

Possibilities of electricity generation in Schleswig-Holstein without using nuclear power

International Nuclear Information System (INIS)

Fischer; Kohler; Natsch; Rossnagel; Sailer.

1986-10-01

The study is arranged in three main parts: Part A discusses safety reasons for backing out of nuclear energy utilisation, and the current legal situation and available scope of action. Part B investigates the technical feasibility of an immediate, complete reactor shut-down in Schleswig-Holstein (in 1987). Part C deals with the framework conditions of a nuclear power shut-off and with accompanying measures on the energy market. According to the order, the main goal of the study was to prove that a nuclear power shut-off is technically feasible. So this study presents assessments with a view to technical feasibility, legal scope of action, costs, ecological effects, and alternative strategies for efficient energy policy on the Land level. This relatively restricted framework, considering exclusively the possibilities of the Land Schleswig-Holstein, necessarily brings about a reduction of the scope of action or optimisation. It is therefore recommended to have an analysis prepared that considers the country as a whole, in order to enhance perspectives and the scope of action. The study does not deal with aspects such as political acceptability and feasibility, or concrete legal processes or procedural steps that would have to be taken in case of backing out and making the turn in energy. The study to a great part relies on assumptions and framework conditions defined in another study by the authors Mueller-Reissmann and Schaffner, entitled 'Power generation without nuclear energy - consequences of backing out of nuclear power'. A brief summary of this study is given in the appendix to the study in hand. (orig./UA) [de

Economic Analysis of Nuclear Energy

International Nuclear Information System (INIS)

Lee, Man Ki; Moon, K. H.; Kim, S. S.; Lim, C. Y.; Song, K. D.; Lee, H. M.; Oh, K. B.

2003-12-01

This study consists of various issues as follows; electricity price regulation in the liberalized electricity market, establishment of carbon emission limit in national electricity sector, the role of nuclear power as an future energy supply option, the future prospect of CO2 capture and sequestration and current research status of that area in Korea, and Preliminary economic feasibility study of MIP(Medical Isotopes Producer). In the price regulation in the liberalized electricity market, the characteristic of liberalized electricity market in terms of regulation was discussed. The current status and future projection of GHG emission in Korean electricity sector was also investigated. After that, how to set the GHG emission limit in the national electricity sector was discussed. The characteristic of nuclear technology and the research in progress were summarized with the suggestion of the possible new application of nuclear power. The current status and future prospect of the CO2 capture and sequestration research was introduced and current research status of that area in Korea was investigated. Preliminary economic feasibility study of MIP(Medical Isotopes Producer), using liquid nuclear fuel to produce medical isotopes of Mo-99 and Sr-89, was performed

Radiation processing of flue gases: Guidelines for feasibility studies

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-12-01

The aim of this publication is to facilitate the performance of feasibility studies for Electron Beam flue gas cleanup projects by providing guidelines to conduct these studies and compiling information on the state of the art. This document summarizes the contents of a feasibility study; discusses the main items in plant construction, measurement and control systems, radiation safety and building construction; and lists the required economic data for internationally funded projects.

Radiation processing of flue gases: Guidelines for feasibility studies

International Nuclear Information System (INIS)

2000-12-01

The aim of this publication is to facilitate the performance of feasibility studies for Electron Beam flue gas cleanup projects by providing guidelines to conduct these studies and compiling information on the state of the art. This document summarizes the contents of a feasibility study; discusses the main items in plant construction, measurement and control systems, radiation safety and building construction; and lists the required economic data for internationally funded projects

A seismic design of nuclear reactor building structures applying seismic isolation system in a seismicity region-a feasibility case study in Japan

Energy Technology Data Exchange (ETDEWEB)

Kubo, Tetsuo [The University of Tokyo, Tokyo (Japan); Yamamoto, Tomofumi; Sato, Kunihiko [Mitsubishi Heavy Industries, Ltd., Kobe (Japan); Jimbo, Masakazu [Toshiba Corporation, Yokohama (Japan); Imaoka, Tetsuo [Hitachi-GE Nuclear Energy, Ltd., Hitachi (Japan); Umeki, Yoshito [Chubu Electric Power Co. Inc., Nagoya (Japan)

2014-10-15

A feasibility study on the seismic design of nuclear reactor buildings with application of a seismic isolation system is introduced. After the Hyogo-ken Nanbu earthquake in Japan of 1995, seismic isolation technologies have been widely employed for commercial buildings. Having become a mature technology, seismic isolation systems can be applied to NPP facilities in areas of high seismicity. Two reactor buildings are discussed, representing the PWR and BWR buildings in Japan, and the application of seismic isolation systems is discussed. The isolation system employing rubber bearings with a lead plug positioned (LRB) is examined. Through a series of seismic response analyses using the so-named standard design earthquake motions covering the design basis earthquake motions obtained for NPP sites in Japan, the responses of the seismic isolated reactor buildings are evaluated. It is revealed that for the building structures examined herein: (1) the responses of both isolated buildings and isolating LRBs fulfill the specified design criteria; (2) the responses obtained for the isolating LRBs first reach the ultimate condition when intensity of motion is 2.0 to 2.5 times as large as that of the design-basis; and (3) the responses of isolated reactor building fall below the range of the prescribed criteria.

Technical feasibility and costs of the retention of radionuclides during accidents in nuclear power plants demonstrated by the example of a pressurized water reactor

International Nuclear Information System (INIS)

Braun, H.; Grigull, R.; Lahner, K.; Gutowski, H.; Weber, J.

1985-01-01

The maximum allowable radiation doses during accidents in nuclear power plants, i.e., 5 rem whole-body dose and 15 rem thyroid dose, have been laid down in the German Radiation Protection Act. In order to ensure that these limits are not exceeded for all exposure paths including the ingestion path or, if possible, to remain far below them, the Federal Ministry of the Interior has initiated a study on the effectiveness and cost of additional safety features for reducing the release of activity and the dose exposure during accidents in nuclear power plants. Detailed investigations were carried out for the following three radiologically representative types of accidents: break of a reactor coolant line, break of an instrument line in one of the outer ring rooms, and break of a main stream line outside the containment. The technical basis of the study was a BBR-type nuclear power plant with pressurized water reactor and once-through steam generator. I-131 was chosen for determining the activity release as this is the critical nuclide for the ingestion path. Altogether 33 feasible technical measures were investigated and their potential improvement was assessed

Nuclear power and the nuclear fuel cycle

International Nuclear Information System (INIS)

Scurr, I.F.; Silver, J.M.

1990-01-01

Australian Nuclear Science and Technology Organization maintains an ongoing assessment of the world's nuclear technology developments, as a core activity of its Strategic Plan. This publication reviews the current status of the nuclear power and the nuclear fuel cycle in Australia and around the world. Main issues discussed include: performances and economics of various types of nuclear reactors, uranium resources and requirements, fuel fabrication and technology, radioactive waste management. A brief account of the large international effort to demonstrate the feasibility of fusion power is also given. 11 tabs., ills

Nuclear magnetic resonance studies of quadrupolar nuclei and dipolar field effects

Energy Technology Data Exchange (ETDEWEB)

Urban, Jeffry Todd [Univ. of California, Berkeley, CA (United States)

2004-01-01

Experimental and theoretical research conducted in two areas in the field of nuclear magnetic resonance (NMR) spectroscopy is presented: (1) studies of the coherent quantum-mechanical control of the angular momentum dynamics of quadrupolar (spin I > 1/2) nuclei and its application to the determination of molecular structure; and (2) applications of the long-range nuclear dipolar field to novel NMR detection methodologies.The dissertation is organized into six chapters. The first two chapters and associated appendices are intended to be pedagogical and include an introduction to the quantum mechanical theory of pulsed NMR spectroscopy and the time dependent theory of quantum mechanics. The third chapter describes investigations of the solid-state multiple-quantum magic angle spinning (MQMAS) NMR experiment applied to I = 5/2 quadrupolar nuclei. This work reports the use of rotary resonance-matched radiofrequency irradiation for sensitivity enhancement of the I = 5/2 MQMAS experiment. These experiments exhibited certain selective line narrowing effects which were investigated theoretically.The fourth chapter extends the discussion of multiple quantum spectroscopy of quadrupolar nuclei to a mostly theoretical study of the feasibility of enhancing the resolution of nitrogen-14 NMR of large biomolecules in solution via double-quantum spectroscopy. The fifth chapter continues to extend the principles of multiple quantum NMR spectroscopy of quadrupolar nuclei to make analogies between experiments in NMR/nuclear quadrupolar resonance (NQR) and experiments in atomic/molecular optics (AMO). These analogies are made through the Hamiltonian and density operator formalism of angular momentum dynamics in the presence of electric and magnetic fields.The sixth chapter investigates the use of the macroscopic nuclear dipolar field to encode the NMR spectrum of an analyte nucleus indirectly in the magnetization of a sensor nucleus. This technique could potentially serve as an

Nuclear magnetic resonance studies of quadrupolar nuclei and dipolar field effects

International Nuclear Information System (INIS)

Urban, Jeffry Todd

2004-01-01

Experimental and theoretical research conducted in two areas in the field of nuclear magnetic resonance (NMR) spectroscopy is presented: (1) studies of the coherent quantum-mechanical control of the angular momentum dynamics of quadrupolar (spin I > 1/2) nuclei and its application to the determination of molecular structure; and (2) applications of the long-range nuclear dipolar field to novel NMR detection methodologies.The dissertation is organized into six chapters. The first two chapters and associated appendices are intended to be pedagogical and include an introduction to the quantum mechanical theory of pulsed NMR spectroscopy and the time dependent theory of quantum mechanics. The third chapter describes investigations of the solid-state multiple-quantum magic angle spinning (MQMAS) NMR experiment applied to I 5/2 quadrupolar nuclei. This work reports the use of rotary resonance-matched radiofrequency irradiation for sensitivity enhancement of the I = 5/2 MQMAS experiment. These experiments exhibited certain selective line narrowing effects which were investigated theoretically.The fourth chapter extends the discussion of multiple quantum spectroscopy of quadrupolar nuclei to a mostly theoretical study of the feasibility of enhancing the resolution of nitrogen-14 NMR of large biomolecules in solution via double-quantum spectroscopy. The fifth chapter continues to extend the principles of multiple quantum NMR spectroscopy of quadrupolar nuclei to make analogies between experiments in NMR/nuclear quadrupolar resonance (NQR) and experiments in atomic/molecular optics (AMO). These analogies are made through the Hamiltonian and density operator formalism of angular momentum dynamics in the presence of electric and magnetic fields.The sixth chapter investigates the use of the macroscopic nuclear dipolar field to encode the NMR spectrum of an analyte nucleus indirectly in the magnetization of a sensor nucleus. This technique could potentially serve as an encoding

Feasibility Study on Dual-Cooled Annular Fuel for OPR-1000 Power Uprate

International Nuclear Information System (INIS)

Chun, Tae Hyun; In, Wang Kee; Oh, Dong Suck

2010-04-01

A dual-cooled annular fuel (DCAF) is a highly promising concept as a high power density fuel for PWR power-uprate. The purpose of this study is to assess a feasibility of 120% core power for OPR-1000 with the DCAF. So the feasibility study were done through the code establishments for annular fuel analysis, evaluations of core physics, thermal-hydraulics and safety analyses at a 120% power with OPR-1000 and the preliminary economic benefits of 20% power-uprate. As results of the analyses, DCAF at 120% power showed sufficient margins available on DNB, PCT and fuel pellet temperature relative to the solid fuel at 100% power. However, judging from an anticipated wide range of the gap conductance variation in inner and outer clearances as fuel burn-up in the reactor core, irradiation behavior of DCAF has to be observed through research reactor test. On the other hand, the nuclear physics parameters like moderator temperature coefficient, power coefficient and so on comply with the technical specifications. An impact of 20% power-uprate on NSSS and BOP was also investigated, and accordingly some components and parts need to be changed were identified. Moreover, the economical benefits from the power-uprate was roughly estimated. It turned out that the power-uprating with DCAF could give an enormous profit even considering the expenses of components and parts to be replaced, additional fuel cycle cost and extended overhaul period

Studies and research concerning BNFP: spent fuel dry storage studies at the Barnwell Nuclear Fuel Plant

International Nuclear Information System (INIS)

Anderson, K.J.

1980-09-01

Conceptual designs are presented utilizing the Barnwell Nuclear Fuel Plant for the dry interim storage of spent light water reactor fuel. Studies were conducted to determine feasible approaches to storing spent fuel by methods other than wet pool storage. Fuel that has had an opportunity to cool for several years, or more, after discharge from a reactor is especially adaptable to dry storage since its thermal load is greatly reduced compared to the thermal load immediately following discharge. A thermal analysis was performed to help in determining the feasibility of various spent fuel dry storage concepts. Methods to reject the heat from dry storage are briefly discussed, which include both active and passive cooling systems. The storage modes reviewed include above and below ground caisson-type storage facilities and numerous variations of vault, or hot cell-type, storage facilities

Selected bibliography for the extraction of uranium from seawater: chemical process and plant design feasibility study

Energy Technology Data Exchange (ETDEWEB)

Binney, S.E.; Polkinghorne, S.T.; Jante, R.R.; Rodman, M.R.; Chen, A.C.T.; Gordon, L.I.

1979-02-01

A selected annotated bibliography of 521 references was prepared as a part of a feasibility study of the extraction of uranium from seawater. For the most part, these references are related to the chemical processes whereby the uranium is removed from the seawater. A companion docment contains a similar bibliography of 471 references related to oceanographic and uranium extraction plant siting considerations, although some of the references are in common. The bibliography was prepared by computer retrieval from Chemical Abstracts, Nuclear Science Abstracts, Energy Data Base, NTIS, and Oceanic Abstracts. References are listed by author, country of author, and selected keywords.

Selected bibliography for the extraction of uranium from seawater: chemical process and plant design feasibility study

International Nuclear Information System (INIS)

Binney, S.E.; Polkinghorne, S.T.; Jante, R.R.; Rodman, M.R.; Chen, A.C.T.; Gordon, L.I.

1979-02-01

A selected annotated bibliography of 521 references was prepared as a part of a feasibility study of the extraction of uranium from seawater. For the most part, these references are related to the chemical processes whereby the uranium is removed from the seawater. A companion docment contains a similar bibliography of 471 references related to oceanographic and uranium extraction plant siting considerations, although some of the references are in common. The bibliography was prepared by computer retrieval from Chemical Abstracts, Nuclear Science Abstracts, Energy Data Base, NTIS, and Oceanic Abstracts. References are listed by author, country of author, and selected keywords

TMI-2 fuel-recovery plant. Feasibility study

International Nuclear Information System (INIS)

Evans, D.L.

1982-12-01

This project is a feasibility study for constructing a TMI-2 core Fuel Recovery Plant at the Idaho National Engineering Laboratory (INEL). The primary objectives of the Fuel Recovery Plant (FRP) are to recover and account for the fuel and to process, isolate, and package the waste material from the TMI-2 core. This feasibility study is predicated on a baseline plant and covers its design, fabrication, installation, testing and operation. Alternative methods for the disposal of the TMI-2 core have also been considered, but not examined in detail for their feasibility. The FRP will receive TMI-2 fuel in canisters. The fuel will vary from core debris to intact fuel assemblies and include some core structural materials. The canister contents will be shredded and subsequently fed to a dissolver. Uranium, plutonium, fission products, and some core structural material will be dissolved. The uranium will be separated by solvent extraction and solidified by calcination. The plutonium will also be separated by solvent extraction and routed to the Plutonium Extraction Facility. The wastes will be packaged for further treatment, temporary storage or permanent disposal

A preliminary feasibility study of passive in-core thermionic reactors for highly compact space nuclear power systems

International Nuclear Information System (INIS)

Parlos, A.G.; Khan, E.U.; Frymire, R.; Negron, S.; Thomas, J.K.; Peddicord, K.L.

1991-01-01

Results of a preliminary feasibility study on a new concept for a highly compact space reactor power systems are presented. Notwithstanding the preliminary nature of the present study, the results which include a new space reactor configuration and its associated technologies indicate promising avenues for the devleopment of highly compact space reactors. The calculations reported in this study include a neutronic design trade-off study using a two-dimensioinal neutron transport model, as well as a simplified one-dimensional thermal analysis of the reactor core. In arriving at the most desirable configuration, various options have been considered and analyzed, and their advantages/disadvantages have been compared. However, because of space limitation, only the most favorable reactor configuration is presented in this summary

Ute Mountain Ute Tribe Community-Scale Solar Feasibility Study

Energy Technology Data Exchange (ETDEWEB)

Rapp, Jim [Parametrix; Knight, Tawnie [Ute Mountain Ute Tribe

2014-01-30

Parametrix Inc. conducted a feasibility study for the Ute Mountain Ute Tribe to determine whether or not a community-scale solar farm would be feasible for the community. The important part of the study was to find where the best fit for the solar farm could be. In the end, a 3MW community-scale solar farm was found best fit with the location of two hayfield sites.

Study of a conceptual nuclear energy center at Green River, Utah: institutional and licensing issues

International Nuclear Information System (INIS)

Heilman, C.B.; Herman, A.A. Jr.; Vito, D.J.

1982-04-01

This document constitutes a segment of a feasibility study investigating the ramification of construcing a nuclear energy center in an arid western region. In this phase of the study, the institutional and licensing issues impacting a NEC were analyzed. The most prominent issue facing such a concept is the ownership form of NEC. In addition, legislation and regulation also have a substantial impact regardless of the ownership format

PET/CT colonography in patients with colorectal polyps: a feasibility study

International Nuclear Information System (INIS)

Mainenti, Pier P.; Pace, Leonardo; Salvatore, Marco; Salvatore, Barbara; D'Antonio, Dario; Bucci, Luigi; De Falco, Teresa; De Palma, Giovanni D.; D'Armiento, Francesco P.

2007-01-01

To examine: (1) the feasibility of PET/CT colonography (PET/CTc) in patients with colorectal polyps; (2) the impact of metabolic information on CTc interpretation and, conversely, the impact of morphological information on PET characterisation of focal colorectal uptake. Ten patients with colorectal polyps underwent PET/CTc, followed within 3 h by therapeutic conventional colonoscopy (CC). A radiologist and a nuclear medicine physician analysed the PET/CTc images. The agreement of morphological and metabolic information in the colon and rectum was evaluated. The sensitivity and specificity of PET, CT and PET/CT were calculated for colorectal polyps. Seventeen polypoid lesions were identified at CC: six≤5 mm, six between 6 and 9 mm, and five ≥10 mm (four hyperplastic polyps, 11 tubular adenomas, one adenocarcinoma and one submucosal lipoma). A total of 20 scans (supine and prone) were performed in the ten patients: the agreement of morphological and metabolic information was excellent in 17 scans, good in two and moderate in one. PET/CTc showed a sensitivity of 91% for lesions ≥6 mm and a specificity of 100%. The metabolic information did not disclose any further polyps missed on CTc. The morphological information permitted correct classification of all eight instances of focal radiotracer uptake. PET/CTc is a feasible study. Adding a colonographic protocol to PET/CT images seems to allow correct characterisation of all cases of colorectal focal radiotracer uptake. The metabolic information does not seem to increase the accuracy of CTc. (orig.)

The feasibility study on fuel types for the KALIMER

International Nuclear Information System (INIS)

Hwang, W.; Nam, C.; Yim, J. S.; Na, B. C.; Hahn, D. H.; Kim, Y. I.; Kim, Y. C.; Park, C. K.

1997-08-01

The economics of LMR is largely dependent on the construction cost of the power plant, and the fuel cycle options usually constitute 20 to 30 % of total electricity generation cost. The choice of fuel cycle technology and the fuel type is important in order to develop a LMR with better economics, performance and safety. The LMR fuel types, whose performances have been proven up to 15 at% burnup, are MOX and IFR metal fuel. The base alloy, binary (U-10% Zr) metal fuel with HT9 is used as structural materials of KALIMER. The design concept of KALIMER fuel has been established through the investigation of technical feasibilities on the fuel and recycle systems for MOX and IFR metal fuel. According to the results of comparative analysis for MOX and metal fuel, metal fuel is better than MOX in view of safety, in-reactor performance, nuclear characteristics, economics and non-proliferation, while MOX fuels have advantages in the developmental status and technical cooperation potential. The overall performance of binary (U-10% Zr) metal fuel with HT9 cladding, which is a potential start-up fuel for KALIMER, is not only superior to that of MOX fuel, but also has enough technical feasibility in its high-burnup performance, safety and economics. (author). 54 ref., 13 tabs., 20 figs

The elementary study on the building of the virtual nuclear monitoring system

International Nuclear Information System (INIS)

Tang Wanlin; Dai Zhuangrong; Zhang Yu

2004-01-01

In this paper we discuss the feasibility to build the virtual nuclear monitoring system using the modern detecting technology, the modern information managing technology and the computer virtual reality technology. We also present the model of this system. (authors)

Technological study report on synthetic evaluation for FBR cycle. The report of the feasibility studies on commercialized FBR cycle system. Phase 1

International Nuclear Information System (INIS)

Shinoda, Yoshihiko; Ohtaki, Akira; Kofuji, Hirohide; Ono, Kiyoshi; Hirao, Kazunori

2001-03-01

This report is intended to explain the outline of the characteristic evaluation work on various FR cycle system concepts, following the design work, in the 1st phase of the JNC's 'Feasibility Study on Commercialized Fast Reactor Cycle System (the F/S)' (from 1999 to March 2001). The purpose of this characteristic evaluation is to reveal the performance of candidate FR cycle systems. For this synthetic estimation, six viewpoints, such as Economics, Effective utilization of uranium resource, Reduction of environmental impact, Safety, Proliferation resistance, and Technological feasibility, are selected. In addition, aiming at the practical use in phase 2, we examined an application to FBR research and development of cost benefit analysis method used for the policy evaluation. Furthermore, long-term nuclear material mass flow was analyzed and the scenario of 'FBR application for the hydrogen production' is proposed, considering how FBR would be utilized for the 21st century. And, a database including the various documents and data used for evaluation was constructed. (author)

Feasibility analysis of nuclear power development in Sichuan province

International Nuclear Information System (INIS)

Yang Qi; Li Jie

2003-01-01

Sichuan province should take this opportunity to develop nuclear power actively since the application of nuclear power has been enhanced worldwide. It is accepted that nuclear power is one kind of safe and clean energy, and the economic has been improved greatly. Considering the electricity demands and structure conflict in near 20 years, nuclear power could solve the problem of electricity shortness in Sichuan, optimize the electricity structure and meliorate the environment, and thus maintain the sustainable development of the economy in Sichuan Province

Feasibility study on consolidation of Fernald Environmental Management Project depleted uranium materials

International Nuclear Information System (INIS)

1995-01-01

In 1991, the DOE made a decision to close the FMPC located in Fernald, Ohio, and end its production mission. The site was renamed FEMP to reflect Fernald's mission change from uranium production to environmental restoration. As a result of this change, the inventory of strategic uranium materials maintained at Fernald by DOE DP will need to be relocated to other DOE sites. Although considered a liability to the Fernald Plant due to its current D and D mission, the FEMP DU represents a potentially valuable DOE resource. Recognizing its value, it may be important for the DOE to consolidate the material at one site and place it in a safe long-term storage condition until a future DOE programmatic requirement materializes. In August 1995, the DOE Office of Nuclear Weapons Management requested, Lockheed Martin Energy Systems (LMES) to assess the feasibility of consolidating the FEMP DU materials at the Oak Ridge Reservation (ORR). This feasibility study examines various phases associated with the consolidation of the FEMP DU at the ORR. If useful short-term applications for the DU fail to materialize, then long-term storage (up to 50 years) would need to be provided. Phases examined in this report include DU material value; potential uses; sampling; packaging and transportation; material control and accountability; environmental, health and safety issues; storage; project management; noneconomic factors; schedule; and cost

Executive summary. Conceptual studies nuclear energy center Lake Hartwell, S.C., Phase III

International Nuclear Information System (INIS)

1981-01-01

This document summarizes a conceptual study on the feasibility and practicality of developing a nuclear energy center (NEC) at a specific site in the SSEB region. The site selected for this conceptual study is at Lake Hartwell, South Carolina. The conceptual NEC at Lake Hartwell consists of twelve 1250-MW(e) LWRs arranged on the site in four cluster of three units each, know as triads. The nominal distance between triads was selected as 2-1/2 miles. The total electric output of 15,000 MWe to be generated by the NEC would be transmitted to five major utilities in South Carolina, North Carolina, and Georgia. Objective of the study was to assess the technical, socioeconomic, environmental, and institutional issues relating to the NEC at the conceptual study site. The basic finding was that the concept of a NEC on the Lake Hartwell site is feasible, but further analysis of institutional issues and possible legislation would be required

Report to the Congress on the need for, and the feasibility of, establishing a security agency within the Office of Nuclear Material Safety and Safeguards

International Nuclear Information System (INIS)

1976-08-01

In response to the Congressional mandate Section 204(b)-(2) (C) of the Energy Reorganization Act of 1974, the Director of the Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission (NRC) has assessed the need for and the feasibility of establishing a security agency within that office for the performance of safeguards functions. The study assessed guard force effectiveness, and addressed public policy, administrative and legal issues. The study concluded that creation of a special security force within NRC would not result in a higher degree of guard force effectiveness than can be achieved through the use of private guards who have been properly trained and certified. Disparate gun laws in various states, it concluded, restrict arms possessed by both private and federal guards and private and federal transportation guards would require legislation authorizing them to bear the necessary weapons to protect nuclear material in transit. The role of reaction forces was also addressed and it was concluded that primary reliance at fixed sites should be placed on onsite protection systems; for material in transit, on invulnerability of vehicles and containers and on guard forces accompanying shipments

General overview of nuclear activities in Morocco

International Nuclear Information System (INIS)

Karouani, K.

1998-01-01

Nuclear activities have been introduced in Morocco since the early seventies. These activities concern the utilization of nuclear techniques in medicine, food and agriculture as well as training and research in nuclear physics. In 1984, Morocco decided to undertake a technical and economic feasibility study as well as the site study of the first nuclear power plant. Two years after, he decided to create the ''Centre National de l'Energie des Sciences et des Techniques Nucleaires'' as a technical and research support for the nuclear power program and as a promoting institute of nuclear techniques. Obviously, he also decided to set up a regulatory framework. (author)

Feasibility studies of computed tomography in partial defect detection of spent BWR fuel

International Nuclear Information System (INIS)

Levai, F.; Tikkinen, J.; Tarvainen, M.; Arlt, R.

1990-10-01

Feasibility studies were made for tomographic reconstruction of a cross-sectional activity distribution of a spent nuclear fuel assembly. The purpose was to determine the number of fuel rods (pins) and localize the positisons where pins are missing. The activity distribution map showing the locations of fuel rods in the assembly was reconstructed. The theoretical part of this work consists of simulation of image reconstruction based on theoretically calculated data from a reference assembly model. Evaluation of different image reconstruction techniques was made. Measurements were made in real facility conditions. Gamma radiation from an irradiated 8 x 8 - 1 BWR fuel assembly was measured through a narrow custom made collimator from different angles and positions. The measured data set was used as projections for reconstructing the activity profile of the assembly in cross-sectional plane

Applicability study of optical fiber distribution sensing to nuclear facilities

International Nuclear Information System (INIS)

Takada, Eiji; Kimura, Atsushi; Nakazawa, Masaharu; Kakuta, Tsunemi

1999-01-01

Optical fibers have advantages like flexible configuration, intrinsic immunity for electromagnetic fields etc., and they have been used for signal transmission and as optical fiber sensors (OFSs). By some of these sensor techniques, continuous or discrete distribution of physical parameters can be measured. Here, in order to discuss the applicability of these OFSs to nuclear facilities, irradiation experiments to optical fibers were carried out using the fast neutron source reactor 'YAYOI' and a 60 Co γ source. It has been shown that, under irradiation with fast neutrons, the radiation induced loss increase almost linearly with the neutron fluence. On the other hand, when irradiated with 60 Co γ rays, the loss shows a saturation tendency. As an example of the OFSs, applicability of the Raman distributed temperature sensor (RDTS) to the monitoring of nuclear facilities has been examined. Two correction techniques for radiation induced errors have been developed and for the demonstration of their feasibility, measurements were carried out along the primary piping system of the experimental fast reactor: JOYO. During the continuous measurements with the total dose of more than 10 7 [R], the radiation induced errors showed a saturating tendency and the feasibility of the loss correction technique was demonstrated. Although the time response of the system should be improved, the RDTS can be expected as a noble temperature monitor in nuclear facilities. (author)

Feasibility study of an optical resonator for applications in neutral-beam injection systems for the next generation of nuclear fusion reactors

International Nuclear Information System (INIS)

Fiorucci, Donatella

2015-01-01

This work is part of a larger project called SIPHORE (Single gap Photo-neutralizer energy Recovery injector), which aims to enhance the overall efficiency of one of the mechanisms through which the plasma is heated, in a nuclear fusion reactor, i.e. the Neutral Beam Injection (NBI) system. An important component of a NBI system is the neutralizer of high energetic ion beams. SIPHORE proposes to substitute the gas cell neutralizer, used in the current NBI systems, with a photo-neutralizer exploiting the photo-detachment process within Fabry Perot cavities. This mechanism should allow a relevant NBI global efficiency of η≥ 60%, significantly higher than the one currently possible (η≤25% for ITER). The present work concerns the feasibility study of an optical cavity with suitable properties for applications in NBI systems. Within this context, the issue of the determination of an appropriated optical cavity design has been firstly considered and the theoretical and experimental analysis of a particular optical resonator has been carried on. The problems associated with the high levels of intracavity optical power (∼3 MW) required for an adequate photo-neutralization rate have then been faced. In this respect, we addressed both the problem of the thermal effects on the cavity mirrors due to their absorption of intra-cavity optical power (∼1 W) and the one associated to the necessity of a high powerful input laser beam (∼1 kW) to feed the optical resonator. (author)

Feasibility analysis in the expansion proposal of the nuclear power plant Laguna Verde: application of real options, binomial model

International Nuclear Information System (INIS)

Hernandez I, S.; Ortiz C, E.; Chavez M, C.

2011-11-01

At the present time, is an unquestionable fact that the nuclear electrical energy is a topic of vital importance, no more because eliminates the dependence of the hydrocarbons and is friendly with the environment, but because is also a sure and reliable energy source, and represents a viable alternative before the claims in the growing demand of electricity in Mexico. Before this panorama, was intended several scenarios to elevate the capacity of electric generation of nuclear origin with a variable participation. One of the contemplated scenarios is represented by the expansion project of the nuclear power plant Laguna Verde through the addition of a third reactor that serves as detonator of an integral program that proposes the installation of more nuclear reactors in the country. Before this possible scenario, the Federal Commission of Electricity like responsible organism of supplying energy to the population should have tools that offer it the flexibility to be adapted to the possible changes that will be presented along the project and also gives a value to the risk to future. The methodology denominated Real Options, Binomial model was proposed as an evaluation tool that allows to quantify the value of the expansion proposal, demonstrating the feasibility of the project through a periodic visualization of their evolution, all with the objective of supplying a financial analysis that serves as base and justification before the evident apogee of the nuclear energy that will be presented in future years. (Author)

Nuclear Aircraft Feasibility Study. Volume 1

Science.gov (United States)

1975-03-01

Iso Dose 10-12 10.1.4-3 Absorption Cross Section Ratio 10-14 10.1.5-1 Engine Systems Study Diagram 10-15 10.1.8-1 Life Cycle Cost for 60...0 00 ■ 3 15.00 OC z ^ 10.00 X s -i 1 UJ 5 < oc D I 50.00 40.00 30.00 20.00 1 ’ ISO LBS/SQ FT WING...4.1.6-1. Payload vs Wing Loading 4-17 m I - 27000 | i i ^1 ̂ N GROSS WEIGHT > 1.600,000 LBS 523 FT/SEC P 30.000 FT ONE GAS REACTOR 1

Feasibility study on tandem fuel cycle

International Nuclear Information System (INIS)

Han, P.S.; Suh, I.S.; Rim, C.S.; Kim, B.K.; Suh, K.S.; Ro, S.K.; Juhn, P.I.; Kim, S.Y.

1983-01-01

The objective of this feasibility study is to review and assess the current state of technology concerning the tandem fuel cycle. Based on the results from this study, a long-term development plan suitable for Korea has been proposed for this cycle, i.e., the PWR → CANDU tandem fuel cycle which used plutonium and uranium, recovered from spent PWR fuel by co-processing, as fuel material for CANDU reactors. (Author)

Feasibility study for a computerized emergency preparedness simulation facility

International Nuclear Information System (INIS)

Gerhardstein, L.H.; Schroeder, J.O.; Sandusky, W.F.

1979-11-01

This report details the feasibility of a computerized Emergency Preparedness Simulation Facility (EPSF) for use by the Nuclear Regulatory Commission (NRC). The proposed facility would be designed to provide the NRC and other federal, state, and local government agencies with a capability to formulate, test, and evaluate the Emergency Preparedness Plans (EPP) which local and state agencies have/will establish for use during nuclear emergencies. In cases of any state emergency (including a nuclear emergency), high level state government officials will direct emergency procedures and insure that state and local emergency teams carry out tasks which have been established in their EPP. When an emergency exists, rapid mobilization of emergency teams, efficient communication, and effective coordination of individual team efforts is essential to safety, preservation of property, and overall public welfare. Current EPP evaluation procedures are qualitative in nature and while they do compare emergency drill performance with the EPP, the nature of the drills often does not provide enough realism to actual emergency conditions. Automated simulation of real emergency conditions using modern computer equipment and programming techniques will provide the NRC emergency evaluation teams a simulated environment which closely approximates conditions which would actually exist during a real emergency. In addition, the computer can be used to collect and log performance and event data which will aid the evaluation team in making assessments of the state or local area's EPP and their Emergency Preparedness Teams performance during emergency drills. Overall, a computerized EPSF can improve drill testing and evaluation efficiency, provide approximate emergency condition realism, and improve public awareness of local emergency procedures

Prospect and potential of nuclear power plants in Indonesia

International Nuclear Information System (INIS)

Subki, I.R.; Adiwardojo; Kasim, M.S.; Iskandar, A.; Mulyanto

1997-01-01

In line with the national energy policy of Indonesia in promoting the intensification, diversification and conversation of energy, some important steps need to be taken in order to establish alternative energy strategies which will be decisive in the formulation and development of the national energy plan in the future. At present, Indonesia does not have any nuclear power plants. The introduction of nuclear power In Indonesia is not only to reach an optimum energy mix based on costs and the environment, but also to relieve the pressure arising from increasing domestic demand for oil and gas. This paper addresses the present feasibility study being performed on the introduction of nuclear power plants in Indonesia. It is anticipated that nuclear power will contribute about 10% of Indonesia's electrical supply as of the year 2019. This represents approximately 12,600 MWe in capability. The paper describes the results, to date, of the Feasibility Study on nuclear power including the national energy market analysis, the electricity expansion plan and the associated role of nuclear power, the economics and financial plan, site studies on volcanology, seismology and the environment. (author). 3 refs, 1 fig., 4 tabs

Study on feasibility of replacing 321 with 316LN stainless steel for main reactor coolant pipe material

International Nuclear Information System (INIS)

Luo Yijun

2013-01-01

The metallurgical, physical and mechanical performance, and the corrosion and welding properties of 00Cr17Ni12Mo2 (controlled Nitrogen, ANSI316LN) and 0Cr18Ni10Ti (ANSI321SS) for main pipe material were analyzed comparatively in this paper. The feasibility of 316LN pipe material manufacturing was studied too. The analysis results showed that under the operation condition of the nuclear reactor, the general properties of 316LN are better than that of 321SS. Therefore, 316LN could be used for main pipe material, replacing 321SS. (authors)

Response to 'Burden of proof: A comprehensive review of the feasibility of 100% renewable-electricity systems'

DEFF Research Database (Denmark)

Brown, Tom; Bischof-Niemz, Tobias; Breyer, Christian

2018-01-01

A recent article 'Burden of proof: A comprehensive review of the feasibility of 100% renewable-electricity systems' claims that many studies of 100% renewable electricity systems do not demonstrate sufficient technical feasibility, according to the criteria of the article's authors (henceforth 'the...... authors'). Here we analyse the authors' methodology and find it problematic. The feasibility criteria chosen by the authors are important, but are also easily addressed at low economic cost, while not affecting the main conclusions of the reviewed studies and certainly not affecting their technical...... feasibility. A more thorough review reveals that all of the issues have already been addressed in the engineering and modelling literature. Nuclear power, as advocated by some of the authors, faces other, genuine feasibility problems, such as the finiteness of uranium resources and a reliance on unproven...

A Feasibility study of a mining business

Directory of Open Access Journals (Sweden)

Cehlár Michal

2001-06-01

Full Text Available The economic evaluation of a project requires a great deal of diverse information to be brought together in one place. The greatest concern is that there will be an error by omission, so it is useful to have a detailed list of what one needs to know in order to make a thorough evaluation.There are various of detail required at the different stages of evaluation in the project, from the "quick and dirty" overview to the pre-feasibility study, through a full detailed feasibility study, to a due diligence review. This list addresses most of the economic variables in project and can be used at all levels of studies. Its purpose is to identify a variable or issue and to raise a question, which the review can pursue in more detail using an increasingly more comprehensive checklist for each topic. While developed from the point of view of a new project, this list is equally valid for an ongoing operation.A feasibility study is defined as an assessment of all aspects of a project including technical, infrastructural, environmental, social, legislative and commercial factors, which is sufficiently detailed to support a decision on the implementation. Each project has an associated level of risk. For a proposed investment to increase the value of a firm's stock, it should have a higher expected rate of return than shareholders require for assuming that risk. Since investors demand for a higher potential returns from a riskier project, the cost of capital depends on the venture's risk.

Problems facing a first nuclear power plant

International Nuclear Information System (INIS)

Diaz, E.

1986-01-01

Requirement of nuclear power generation. Reason for considering a nuclear power programme. Decision to 'go nuclear'. Existing antecedents in the country (nuclear research institution, conventional generating plants, other nuclear utilities). - First organizational steps. Feasibility studies. Site selection and power module. Eventual reactor type decision. Site approval. - Pre-purchasing activities. Eventual selection of a consultant. Domestic participation capabilities. Pre-qualification bids. - Definition of contract type and scopes. Turn-key/non-turn-key. Architect Engineer organization. Bidding documentation. Financing. Warranties. Role of the owner. Licensing procedures and regulations. (orig./GL)

MacMillan Pier Transportation Center Feasibility Study.

Science.gov (United States)

2006-06-01

The MacMillan Pier Transportation Center Feasibility Study examines two potential sites (landside and waterside) for a transportation center that provides a range of tourist and traveler information. It would serve as a gateway for Provincetown and t...

Nuclear plant undergrounding

International Nuclear Information System (INIS)

Brown, R.C.; Bastidas, C.P.

1978-01-01

Under Section 25524.3 of the Public Resources Code, the California Energy Resources Conservation and Development Commission (CERCDC) was directed to study ''the necessity for '' and the effectiveness and economic feasibility of undergrounding and berm containment of nuclear reactors. The author discusses the basis for the study, the Sargent and Lundy (S and L) involvement in the study, and the final conclusions reached by S and L

Attitudes and opposition in siting a high level nuclear waste repository

International Nuclear Information System (INIS)

Sjoeberg, L.; Viklund, M.; Truedsson, J.

1998-09-01

In Sweden, the Swedish Nuclear Fuel and Waste Management Company (SKB) handles all issues concerning nuclear waste, including the siting process, in which the final outcome is intended to be a repository for high level nuclear waste placed deep down in bedrock. The main objective of the siting process is to find a host community fulfilling two important conditions: the safety demands have been met and agreements with the municipality can be accomplished. Only in such municipalities, so-called feasibility studies will be conducted. After conducting general studies in the whole country, SKB, in October 1992, sent letters with information about the intended feasibility studies to all Swedish municipalities. As a result, feasibility studies are or have been considered - and in some cases also been conducted - in eleven Swedish municipalities up until 1998. These are the municipalities where the attitudes and opposition towards a feasibility study, and possibly a final repository, are studied. The discussion can be divided into three main parts: Management of the siting process; Inherent 'chaotic' processes and/or factors and risk perception. It is argued that two important problems could have been avoided at least partly: The citizens in many municipalities were uncertain of the relationship between a feasibility study and a final repository, and in many municipalities the citizens were afraid that the Government could overrule the municipal veto. Because of these fears, a common argument among the opponents of a feasibility study was: 'to be sure of not receiving a final repository, we say no to a feasibility study'. Some inherent factors, more or less prevalent in the municipalities as well as in society in general, may also partly explain the outcome of the siting process. The municipalities in which the debate has been heated, and where public support has been more difficult to reach, share some common characteristics. Esp. in the municipalities in the north of

Attitudes and opposition in siting a high level nuclear waste repository

Energy Technology Data Exchange (ETDEWEB)

Sjoeberg, L.; Viklund, M.; Truedsson, J

1998-09-01

In Sweden, the Swedish Nuclear Fuel and Waste Management Company (SKB) handles all issues concerning nuclear waste, including the siting process, in which the final outcome is intended to be a repository for high level nuclear waste placed deep down in bedrock. The main objective of the siting process is to find a host community fulfilling two important conditions: the safety demands have been met and agreements with the municipality can be accomplished. Only in such municipalities, so-called feasibility studies will be conducted. After conducting general studies in the whole country, SKB, in October 1992, sent letters with information about the intended feasibility studies to all Swedish municipalities. As a result, feasibility studies are or have been considered - and in some cases also been conducted - in eleven Swedish municipalities up until 1998. These are the municipalities where the attitudes and opposition towards a feasibility study, and possibly a final repository, are studied. The discussion can be divided into three main parts: Management of the siting process; Inherent `chaotic` processes and/or factors and risk perception. It is argued that two important problems could have been avoided at least partly: The citizens in many municipalities were uncertain of the relationship between a feasibility study and a final repository, and in many municipalities the citizens were afraid that the Government could overrule the municipal veto. Because of these fears, a common argument among the opponents of a feasibility study was: `to be sure of not receiving a final repository, we say no to a feasibility study`. Some inherent factors, more or less prevalent in the municipalities as well as in society in general, may also partly explain the outcome of the siting process. The municipalities in which the debate has been heated, and where public support has been more difficult to reach, share some common characteristics. Esp. in the municipalities in the north of

Three Affliated Tribes Renewable Energy Feasibility Study

Energy Technology Data Exchange (ETDEWEB)

Belvin Pete; Kent Good; Krista Gordon; Ed McCarthy,

2006-05-26

The Three Affliated Tribes on the Fort Berthold Reservation studied the feasibility of a commercial wind facility on land selected and owned by the Tribes and examined the potential for the development of renewable energy resources on Tribal Lands.

Case study - Argentina

International Nuclear Information System (INIS)

Diaz, E.

1986-01-01

Antecedents and experience of nuclear activities in Argentina; the Atomic Energy Commission (CNEA). First development and research activities. Research reactors and radioisotopes plants. Health physics and safety regulations. - Feasibility studies for the first nuclear power plant. Awarding the first plant CNA I (Atucha I). Relevant data related to the different project stages. Plant performance. - Feasibility study for the second nuclear power plant. Awarding the second plant CNE (Central Nuclear Embalse). Relevant data related to established targets. Differences compared with the first station targets. Local participation. Plant performance. (orig./GL)

A study of design features of civil works of nuclear installations facilitating their eventual refurbishing, renewal, dismantling or demolition

International Nuclear Information System (INIS)

Paton, A.A.; Benwell, P.; Irwin, T.F.; Hunter, I.

1984-03-01

This report describes a study that has been carried out to identify civil engineering features which could be incorporated in future gas cooled and light water cooled nuclear power plants to facilitate their decommissioning. The report reviews the problems likely to be met in decommissioning present day nuclear power plants and concludes that there is a number of such features which could be introduced in future designs to overcome or eliminate the problems. The report identifies and describes these features and recommends that further work be carried out to confirm their feasibility. The study briefly considered the possibility of refurbishing nuclear plants and concluded that this is not a realistic option in present circumstances. (author)

Feasibility Study of Hydrogen Production from Existing Nuclear Power Plants Using Alkaline Electrolysis

International Nuclear Information System (INIS)

Swalla, Dana R.

2008-01-01

The mid-range industrial market currently consumes 4.2 million metric tons of hydrogen per year and has an annual growth rate of 15% industries in this range require between 100 and 1000 kilograms of hydrogen per day and comprise a wide range of operations such as food hydrogenation, electronic chip fabrication, metals processing and nuclear reactor chemistry modulation

FEASIBILITY STUDY FOR POTASSIUM IODIDE (KI) DISTRIBUTION IN NEW YORK CITY

International Nuclear Information System (INIS)

MOSS, STEVEN

2005-01-01

The New York City Department of Health and Mental Hygiene (DOHMH), Bureau of Environmental Science and Engineering, Office of Radiological Health (ORH) [as the primary local technical consultant in the event of a radiological or nuclear incident within the boundaries of New York City] requested the assistance of Brookhaven National Laboratory (BNL) with the development of a Feasibility Study for Potassium Iodide (KI) distribution in the unlikely event of a significant release of radioactive iodine in or near New York City. Brookhaven National Laboratory had previously provided support for New York City with the development of the radiological/nuclear portions of its All Hazards Emergency Response Plans. The work is funded by Medical and Health Research Association (MHRA) of New York City, Inc., under a work grant by the Federal Centers for Disease Control (CDC) for Public Health Preparedness and Response for Bioterrorism. This report is part of the result of that effort. The conclusions of this report are that: (1) There is no credible radiological scenario that would prompt the need for large segments of the general population of New York City to take KI as a result of a projected plume exposure to radioiodine reaching even the lowest threshold of 5 rem to the thyroid; and (2) KI should be stockpiled in amounts and locations sufficient for use by first responders/emergency responders in response to any localized release of radioiodine

FEASIBILITY STUDY FOR POTASSIUM IODIDE (KI) DISTRIBUTION IN NEW YORK CITY.

Energy Technology Data Exchange (ETDEWEB)

MOSS, STEVEN

2005-04-29

The New York City Department of Health and Mental Hygiene (DOHMH), Bureau of Environmental Science and Engineering, Office of Radiological Health (ORH) [as the primary local technical consultant in the event of a radiological or nuclear incident within the boundaries of New York City] requested the assistance of Brookhaven National Laboratory (BNL) with the development of a Feasibility Study for Potassium Iodide (KI) distribution in the unlikely event of a significant release of radioactive iodine in or near New York City. Brookhaven National Laboratory had previously provided support for New York City with the development of the radiological/nuclear portions of its All Hazards Emergency Response Plans. The work is funded by Medical and Health Research Association (MHRA) of New York City, Inc., under a work grant by the Federal Centers for Disease Control (CDC) for Public Health Preparedness and Response for Bioterrorism. This report is part of the result of that effort. The conclusions of this report are that: (1) There is no credible radiological scenario that would prompt the need for large segments of the general population of New York City to take KI as a result of a projected plume exposure to radioiodine reaching even the lowest threshold of 5 rem to the thyroid; and (2) KI should be stockpiled in amounts and locations sufficient for use by first responders/emergency responders in response to any localized release of radioiodine.

The Feasibility study of laser peening effects on the Nuclear power plants Using Shot peening treatment with operating temperature

International Nuclear Information System (INIS)

Kim, Jong Cheon; Kim, Tae Hyung; Cheong, S. K.; Cho, Hong Seok

2010-01-01

Recently, the nuclear power plants industry was faced with material aging problems. One of them is Primary water stress corrosion cracking (PWSCC). Even if Alloy 600, which is a nickel based superalloy, has been used in some parts of nuclear power plants, it is widely used in the manufacturing of commercial and military components. The Alloy 600 is a standard structural engineering material which requires the resistance to corrosion and thermal effects. However, some parts of BMI nozzle have PWSCC problem. Several methods have been used to prevent PWSSC. Typically, peening process is used extensively in the industry to improve life time and to mitigate stress corrosion cracking (SCC). Laser peening (LP) is one of the best ways to achieve the above reasons. This technology was already applied to nuclear power plants by developed countries. Nowadays Korea nuclear power plants industry is highly ranked in the world market. Thus, the demands of laser peening technology will increase. However, it is very difficult to characterize the material properties after peening treatment on the parts of nuclear power plants. Therefore, we accomplished a precedent study of experiments to investigate the effects of peening process on the Alloy 600, and the threshold temperature for stress relief and the effect of LP through the Shop peening(SP). LP and SP process have equal mechanism but just different peening media. In this paper, to determine the effects of laser peening process on the nuclear power plants manufacture Alloy 600 using the shot peening treatment with operating temperatures

Restoring effective sleep tranquility (REST): A feasibility and pilot study.

Science.gov (United States)

Eakman, Aaron M; Schmid, Arlene A; Henry, Kimberly L; Rolle, Natalie R; Schelly, Catherine; Pott, Christine E; Burns, Joshua E

2017-06-01

The purpose of this pilot study was to establish the feasibility of completing a future controlled trial of a multi-component cognitive behavioral therapy for insomnia program for military veterans with sleep disturbance. This was a single-arm feasibility and pilot study. Participants were United States post-9/11 veterans with service-connected injuries, university students, and had self-reported sleep disturbances. Restoring Effective Sleep Tranquility was a multi-component cognitive behavioral therapy for insomnia intervention consisting of seven sessions of group therapy and eight 1:1 sessions delivered by occupational therapists. Feasibility and pilot indicators were process, resources, management, and scientific, including pre-post-assessments of sleep difficulties, dysfunctional sleep beliefs, participation, and pain interference. Indicators were supportive of feasibility, including reduced sleep difficulties (for example Medical Outcomes Study Sleep Measure [ t  = 3.29, p  = .02]), reduced nightmares: t  = 2.79, p  = .03; fewer dysfunctional sleep beliefs: t  = 3.63, p  = .01, and greater ability to participate in social roles: t  = -2.86, p  = .03, along with trends towards improved satisfaction with participation and reduced pain interference. The Restoring Effective Sleep Tranquility program may reduce sleep difficulties and improve participation in US veterans with service-connected injuries, and evidence indicates a controlled trial would be feasible to deliver.

Study of a conceptual nuclear energy center at Green River, Utah. Final summary report

Energy Technology Data Exchange (ETDEWEB)

Williams, J.T. (ed.)

1982-09-01

This document summarizes a conceptual study on the feasibility and practicality of developing a nuclear energy center (NEC) at a representative Western site. The site selected for this conceptual study, an area of about 50 square miles, is located 15 miles south of Green River, Utah. The conceptual NEC would consist of nine nuclear electric generating units, arranged on the site in three clusters of three reactors each (triads), separated by about 2 1/2 miles. Of the total electric output of 11,250 MWe that the NEC could produce, about 82% is assumed to be transmitted out of Utah to Colorado, New Mexico, Arizona, Nevada, and California. The technical engineering issues studied included geology and seismology, plant design, low-level radioactive waste disposal, transmission, and construction schedules and costs. Socioeconomic issues included were demographics, land use, community service needs, and fiscal impacts. Environmental considerations included terrestrial and aquatic ecology, visual impact, and secondary population impacts. Radiological issues were concerned with the safety and risks of an NEC and an on-site low-level waste facility. Institutional issues included methods of ownership, taxation, implications of energy export, and water allocation. The basic finding was that an NEC would be technically feasible, but a number of socioeconomic and institutional issues would require resolution before a Western regional NEC could be considered a viable power plant siting option.

Study of a conceptual nuclear energy center at Green River, Utah. Final summary report

International Nuclear Information System (INIS)

Williams, J.T.

1982-09-01

This document summarizes a conceptual study on the feasibility and practicality of developing a nuclear energy center (NEC) at a representative Western site. The site selected for this conceptual study, an area of about 50 square miles, is located 15 miles south of Green River, Utah. The conceptual NEC would consist of nine nuclear electric generating units, arranged on the site in three clusters of three reactors each (triads), separated by about 2 1/2 miles. Of the total electric output of 11,250 MWe that the NEC could produce, about 82% is assumed to be transmitted out of Utah to Colorado, New Mexico, Arizona, Nevada, and California. The technical engineering issues studied included geology and seismology, plant design, low-level radioactive waste disposal, transmission, and construction schedules and costs. Socioeconomic issues included were demographics, land use, community service needs, and fiscal impacts. Environmental considerations included terrestrial and aquatic ecology, visual impact, and secondary population impacts. Radiological issues were concerned with the safety and risks of an NEC and an on-site low-level waste facility. Institutional issues included methods of ownership, taxation, implications of energy export, and water allocation. The basic finding was that an NEC would be technically feasible, but a number of socioeconomic and institutional issues would require resolution before a Western regional NEC could be considered a viable power plant siting option

Feasibility Study on HYSOL CSP

DEFF Research Database (Denmark)

Nielsen, Lars Henrik; Baldini, Mattia; Skytte, Klaus

2016-01-01

integrated HYSOL concept, therefore, becomes a fully dispatchable (offering firm power) and fully renewable energy source (RES) based power supply alternative, offering CO2-free electricity in regions with sufficient solar resources. The economic feasibility of HYSOL configurations is addressed in this paper....... The CO2 free HYSOL alternative is discussed relative to conventional reference firm power generation technologies. In particular the HYSOL performance relative to new power plants based on natural gas (NG) such as open cycle or combined cycle gas turbines (OCGT or CCGT) are in focus. The feasibility...

Feasibility study of passive gamma spectrometry of molten core material from Fukushima Daiichi Nuclear Power Station unit 1, 2, and 3 cores for special nuclear material accountancy - low-volatile FP and special nuclear material inventory analysis and fundamental characteristics of gamma-rays from fuel debris

International Nuclear Information System (INIS)

Sagara, Hiroshi; Tomikawa, Hirofumi; Watahiki, Masaru; Kuno, Yusuke

2014-01-01

The technologies applied to the analysis of the Three Mile Island accident were examined in a feasibility study of gamma spectrometry of molten core material from the Fukushima Daiichi Nuclear Power Station unit 1, 2, and 3 cores for special nuclear material accountancy. The focus is on low-volatile fission products and heavy metal inventory analysis, and the fundamental characteristics of gamma-rays from fuel debris with respect to passive measurements. The inventory ratios of the low-volatile lanthanides, "1"5"4Eu and "1"4"4Ce, to special nuclear materials were evaluated by the entire core inventories in units 1, 2, and 3 with an estimated uncertainty of 9%-13% at the 1σ level for homogenized molten fuel material. The uncertainty is expected to be larger locally owing to the use of the irradiation cycle averaging approach. The ratios were also evaluated as a function of burnup for specific fuel debris with an estimated uncertainty of 13%-25% at the 1σ level for units 1 and 2, and most of the fuels in unit 3, although the uncertainty regarding the separated mixed oxide fuel in unit 3 would be significantly higher owing to the burnup dependence approach. Source photon spectra were also examined and cooling-time-dependent data sets were prepared. The fundamental characteristics of high-energy gamma-rays from fuel debris were investigated by a bare-sphere model transport calculation. Mass attenuation coefficients of fuel debris were evaluated to be insensitive to its possible composition in a high-energy region. The leakage photon ratio was evaluated using a variety of parameters, and a significant impact was confirmed for a certain size of fuel debris. Its correlation was summarized with respect to the leakage photopeak ratio of source "1"5"4Eu. Finally, a preliminary study using a hypothetical canister model of fuel debris based on the experience at Three Mile Island was presented, and future plans were introduced. (author)

Contraband Detection with Nuclear Resonance Fluorescence: Feasibility and Impact

International Nuclear Information System (INIS)

Pruet, J; Lange, D

2007-01-01

In this report they show that cargo interrogation systems developed to thwart trafficking of illicit nuclear materials could also be powerful tools in the larger fight against contraband smuggling. In particular, in addition to detecting special nuclear materials, cargo scanning systems that exploit nuclear resonance fluorescence to detect specific isotopes can be used to help find: chemical weapons; some drugs as well as some chemicals regulated under the controlled substances act; precious metals; materials regulated under export control laws; and commonly trafficked fluorocarbons

Feasibility of Optical Instruments Based on Multiaperture Optics.

Science.gov (United States)

1984-10-16

system may be configured. The optical elements may be nonimaging concentrators (light horns), the field of view (FOV) of which may be controlled by a...RD-RI58 868 FEASIBILITY OF OPTICAL INSTRUMENTS BASED ON i/I MULTIAPERTURE OPTICS (U) FLORIDA UNIV GAINESVILLE DEPT OF NUCLEAR ENGINEERING SCIENCES J D...d Subtitle) 5. TYPE OF REPORT & PERIOD COVERED ’ 0 Feasibility of Optical Instruments Based on Final Report * CD Multiaperature Optics 615/83 to 9/30

Nuclear Data Parameter Adjustment BNL-INL

International Nuclear Information System (INIS)

Palmiotti, G.; Hoblit, S.; Herman, M.; Nobre, G.P.A.; Palumbo, A.; Hiruta, H.; Salvatores, M.

2013-01-01

This presentation reports on the consistent adjustment of nuclear data parameters performed within a BNL-INL collaboration. The main advantage compared to the classical adjustment of multigroup constants is to provide final nuclear data constrained by the nuclear reaction theory and consistent with both differential and integral measurements. The feasibility of a single-isotope assimilation was tested on a few priority materials ( 23 Na, 56 Fe, 105 Pd, 235,238 U, 239 Pu) using a selection of clean integral experiments. The multi-isotope assimilation is under study for the Big-3 ( 235,238 U, 239 Pu). This work shows that a consistent assimilation is feasible, but there are pitfalls to avoid (e.g. non-linearity, cross section fluctuations) and prerequisites (e.g. realistic covariances, good prior, realistic weighting of differential and integral experiments). Finally, only all experimental information combined with the state of the art modelling may provide a 'right' answer

A study on the establishment of nuclear cooperative relations and future direction between Korea and Vietnam

Energy Technology Data Exchange (ETDEWEB)

Yang, M H; Kim, H S; Chung, W S; Yun, S W; Ko, H S; Lee, J K

2000-10-01

This study was carried out in order to review the cooperation with vietnam and establish and activate the cooperative relations with Vietnam. During the study, current status of use and development of nuclear energy in vietnam, were investigated including nuclear power plant and cooperative relations between two nations were also established. It was agreed through exchanges of visits of cooperation delegation; 1) exchange of visits of cooperation delegation, 2) holding of policy seminar for high level decision makers of Vietnam 3) cooperaton between KAERI/VAEC, 4) joint feasibility study for the construction of KSNP into Vietnam and technical presentation of KSNP. It is recommended that cooperaion with vietnam be implemented systematically through the long term based basic directions and integrated national strategies.

A study on the establishment of nuclear cooperative relations and future direction between Korea and Vietnam

International Nuclear Information System (INIS)

Yang, M. H.; Kim, H. S.; Chung, W. S.; Yun, S. W.; Ko, H. S.; Lee, J. K.

2000-10-01

This study was carried out in order to review the cooperation with vietnam and establish and activate the cooperative relations with Vietnam. During the study, current status of use and development of nuclear energy in vietnam, were investigated including nuclear power plant and cooperative relations between two nations were also established. It was agreed through exchanges of visits of cooperation delegation; 1) exchange of visits of cooperation delegation, 2) holding of policy seminar for high level decision makers of Vietnam 3) cooperaton between KAERI/VAEC, 4) joint feasibility study for the construction of KSNP into Vietnam and technical presentation of KSNP. It is recommended that cooperaion with vietnam be implemented systematically through the long term based basic directions and integrated national strategies

A SEISMIC DESIGN OF NUCLEAR REACTOR BUILDING STRUCTURES APPLYING SEISMIC ISOLATION SYSTEM IN A HIGH SEISMICITY REGION –A FEASIBILITY CASE STUDY IN JAPAN-

Directory of Open Access Journals (Sweden)

TETSUO KUBO

2014-10-01

Full Text Available A feasibility study on the seismic design of nuclear reactor buildings with application of a seismic isolation system is introduced. After the Hyogo-ken Nanbu earthquake in Japan of 1995, seismic isolation technologies have been widely employed for commercial buildings. Having become a mature technology, seismic isolation systems can be applied to NPP facilities in areas of high seismicity. Two reactor buildings are discussed, representing the PWR and BWR buildings in Japan, and the application of seismic isolation systems is discussed. The isolation system employing rubber bearings with a lead plug positioned (LRB is examined. Through a series of seismic response analyses using the so-named standard design earthquake motions covering the design basis earthquake motions obtained for NPP sites in Japan, the responses of the seismic isolated reactor buildings are evaluated. It is revealed that for the building structures examined herein: (1 the responses of both isolated buildings and isolating LRBs fulfill the specified design criteria; (2 the responses obtained for the isolating LRBs first reach the ultimate condition when intensity of motion is 2.0 to 2.5 times as large as that of the design-basis; and (3 the responses of isolated reactor building fall below the range of the prescribed criteria.

Theoretical studies in nuclear reactions and nuclear structure

International Nuclear Information System (INIS)

Wallace, S.J.

1991-05-01

This report discusses topics in the following areas: Hadronic structure; hadrons in nuclei; hot hadronic matter; relativistic nuclear physics and NN interaction; leptonic emissions from high-Z heavy ion collisions; theoretical studies of heavy ion dynamics; nuclear pre-equilibrium reactions; classical chaotic dynamics and nuclear structure; and, theory of nuclear fission

Feasibility study for a DOE research and production fuel multipurpose canister

International Nuclear Information System (INIS)

Lopez, D.A.; Abbott, D.G.

1994-02-01

This is a report of the feasibility of multipurpose canisters for transporting, storing, and sing of Department of Energy research and production spent nuclear fuel. Six representative Department of Energy fuel assemblies were selected, and preconceptual canister designs were developed to accommodate these assemblies. The study considered physical interface, structural adequacy, criticality safety, shielding capability, thermal performance of the canisters, and fuel storage site infrastructure. The external envelope of the canisters was designed to fit within the overpack casks for commercial canisters being developed for the Department of Energy Office of Civilian Radioactive Waste Management. The budgetary cost of canisters to handle all fuel considered is estimated at $170.8M. One large conceptual boiling water reactor canister design, developed for the Office of Civilian Radioactive Waste Management, and two new canister designs can accommodate at least 85% of the volume of the Department of Energy fuel considered. Canister use minimizes public radiation exposure and is cost effective compared with bare fuel handling. Results suggest the need for additional study of issues affecting canister use and for conceptual design development of the three canisters

Technical feasibility study on polycarbonate solar panels

NARCIS (Netherlands)

Hackmann, M.M.; Meuwissen, M.H.H.; Bots, T.L.; Buijs, J.A.H.M.; Broek, K.M.; Kinderman, R.; Tanck, O.B.F.; Schuurmans, F.M.

2004-01-01

This paper describes a technical feasibility study on the application of polycarbonate (PC) plates in a superstrate photovoltaic module design. The lamination process was performed in a conventional laminator apparatus using low temperature curing (100°C) ethylene-vinyl-acetate (EVA) as the potting

Feasibility study of application of Prompt Gamma Neutron Activation Analysis (PGNAA) method in TRIGA IPR-R1 reactor

International Nuclear Information System (INIS)

Guerra, Bruno Teixeira

2016-01-01

The TRIGA Mark I IPR-R1 research reactor is located at Nuclear Technology Development Centre (CDTN), Brazilian Commission for Nuclear Energy (CNEN), in Belo Horizonte, Brazil. The reactor operates at 100 kW but the core configuration allows the increasing of the power up to 250 kW. It has been applied research, training and radioisotopes production. The establishment of the Prompt Gamma Neutron Activation Analysis (PGNAA) method at the TRIGA IPR-R1 reactor will significantly increase the types of matrices analysed as well as the number of chemical elements. Additionally it will complement the neutron activation analysis. This work presents a proposed design of a PGNAA facility to be installed at the TRIGA IPR-R1. The proposed design is based on a tube as a neutron guide from the reactor core, inside the reactor pool, 6 m below the room’s level where shall be located the rack containing the set sample/detector/shielding. Thus, the aim of this study is to verify the feasibility to establish the PGNAA method in IPR-R1 through theoretical study applying the Monte Carlo code. The feasibility of establishing the PGAA method at the IPR-R1 installations was evaluated through of the calculations of neutron flux, radioactive capture reaction rates and detection limits for some isotopes. According to the obtained results, it can be concluded that is possible to establish the PGAA method at the IPR-R1 reactor, even with some restrictions in its theoretical design calculated by MCNP. (author)

Lifetime management research trend of Kori-1 nuclear power plant

International Nuclear Information System (INIS)

Kim, J. S.; Jeong, I. S.; Hong, S. Y.

1998-01-01

KEPRI launched the Nuclear Power Plant Lifetime Management Study(II) for the management of the latter half life of Kori-1. Main goal of LCM-IV study is the detail evaluation of main equipment life and establishment of aging management based on LCM-IV result. The result of LCM-IV on the kori-1 confirmed the technical and economical feasibility of life extension beyond the design life. Owing to absence of The regulatory policy for the life extension in korea, LCM-IV will focus on the minimum study which is essential for the actual lifetime management for the old nuclear power plant. License renewal study is expected after the establishment of Regulatory policy about the life extension of nuclear power plant. LCM trend in korea and abroad, result of technical and economical feasibility study and summary of LCM-IV is described on this paper

Feasibility study: Assess the feasibility of siting a monitored retrievable storage facility

International Nuclear Information System (INIS)

King, J.W.

1993-01-01

The purpose of phase one of this study are: To understand the waste management system and a monitored retrievable storage facility; and to determine whether the applicant has real interest in pursuing the feasibility assessment process. Contents of this report are: Generating electric power; facts about exposure to radiation; handling storage, and transportation techniques; description of a proposed monitored retrievable storage facility; and benefits to be received by host jurisdiction

Feasibility Study for a Hopi Utility-Scale Wind Project

Energy Technology Data Exchange (ETDEWEB)

Kendrick Lomayestewa

2011-05-31

The goal of this project was to investigate the feasibility for the generation of energy from wind and to parallel this work with the development of a tribal utility organization capable of undertaking potential joint ventures in utility businesses and projects on the Hopi reservation. The goal of this project was to investigate the feasibility for the generation of energy from wind and to parallel this work with the development of a tribal utility organization capable of undertaking potential joint ventures in utility businesses and projects on the Hopi reservation. Wind resource assessments were conducted at two study sites on Hopi fee simple lands located south of the city of Winslow. Reports from the study were recently completed and have not been compared to any existing historical wind data nor have they been processed under any wind assessment models to determine the output performance and the project economics of turbines at the wind study sites. Ongoing analysis of the wind data and project modeling will determine the feasibility of a tribal utility-scale wind energy generation.

Final Technical Report: Renewable Energy Feasibility Study and Resources Assessment

Energy Technology Data Exchange (ETDEWEB)

Rivero, Mariah [BEC Environmental, Inc., Las Vegas, NV (United States)

2016-02-28

In March 2011, the U.S. Department of Energy (DOE) awarded White Pine County, Nevada, a grant to assess the feasibility of renewable resource-related economic development activities in the area. The grant project included a public outreach and training component and was to include a demonstration project; however, the demonstration project was not completed due to lack of identification of an entity willing to locate a project in White Pine County. White Pine County completed the assessment of renewable resources and a feasibility study on the potential for a renewable energy-focused economic sector within the County. The feasibility study concluded "all resources studied were present and in sufficient quantity and quality to warrant consideration for development" and there were varying degrees of potential economic impact based on the resource type and project size. The feasibility study and its components were to be used as tools to attract potential developers and other business ventures to the local market. White Pine County also marketed the County’s resources to the renewable energy business community in an effort to develop contracts for demonstration projects. The County also worked to develop partnerships with local educational institutions, including the White Pine County School District, conducted outreach and training for the local community.

Public acceptance of nuclear power declining

International Nuclear Information System (INIS)

Krieger, J.H.

1982-01-01

The view is presented that current policy toward nuclear energy reflects an ideology more than actual behavior. Public attitudes toward nuclear power make its future less certain than at any time since the accident at Three Mile Island in 1979, but a public opinion study also produced evidence that polarization is less than was thought. Social, political, and human value issues are causing the nuclear stalemate, not economic or technical feasibility. It is suggested that the Reagan administration's support of nuclear energy at the expense of conservation should consider that a Gallup pole found nuclear power to be the least popular energy alternative. A policy which includes both nuclear energy and conservation is more likely to be productive

Accelerator for nuclear transmutation

International Nuclear Information System (INIS)

Schapira, J.P.

1984-01-01

A review on nuclear transmutation of radioactive wastes using particle accelerators is given. Technical feasibility, nuclear data, costs of various projects are discussed. It appears that one high energy accelerator (1500 MeV, 300 mA proton) could probably handle the amount of actinides generated by the actual French nuclear program [fr

PV solar system feasibility study

International Nuclear Information System (INIS)

Ashhab, Moh’d Sami S.; Kaylani, Hazem; Abdallah, Abdallah

2013-01-01

Highlights: ► This research studies the feasibility of PV solar systems. ► The aim is to develop the theory and application of a hybrid system. ► Relevant research topics are reviewed and some of them are discussed in details. ► A prototype of the PV solar system is designed and built. - Abstract: This research studies the feasibility of PV solar systems and aims at developing the theory and application of a hybrid system that utilizes PV solar system and another supporting source of energy to provide affordable heating and air conditioning. Relevant research topics are reviewed and some of them are discussed in details. Solar heating and air conditioning research and technology exist in many developed countries. To date, the used solar energy has been proved to be inefficient. Solar energy is an abundant source of energy in Jordan and the Middle East; with increasing prices of oil this source is becoming more attractive alternative. A good candidate for the other system is absorption. The overall system is designed such that it utilizes solar energy as a main source. When the solar energy becomes insufficient, electricity or diesel source kicks in. A prototype of the PV solar system that operates an air conditioning unit is built and proper measurements are collected through a data logging system. The measured data are plotted and discussed, and conclusions regarding the system performance are extracted.

The inventory model for feasibility studies of a deep geological disposal for high level and long lived waste

International Nuclear Information System (INIS)

Dutzer, M.; Lagrange, M.H.; Porcher, J.B.; Chupeau, J.

2001-01-01

A detailed inventory of high level and long lived waste packages was established to perform studies for the feasibility of an underground repository. This inventory takes into account existing conditioned waste, unconditioned waste and arisings generated by existing facilities. Grouping of waste package sorts in package types is done regarding relevant characteristics that determine the design of disposal vaults. The radiological content of each package type is derived from calculations of nuclear interactions inside the reactors, from the distribution of the nuclides in the different package types; it is cross-checked with available data on waste sorts. (author)

Study of feasibility of detecting effects of low-dose radiation in shipyard workers. Final report, May 15-August 15, 1978

International Nuclear Information System (INIS)

Matanoski, G.M.

1982-12-01

There is very little information available on the chronic health effects from repeated low-level doses of radiation. This study examines the adequacy of determining radiation exposure doses in shipyard workers, the procedures used in the radiation control programs, and the feasibility of establishing an appropriate population of nuclear and non-nuclear shipyard workers for long-term studies of low-level radiation. The availability of records and the methods of population identification and of measurement of radiation dose were determined during initial visits to the yards. Personnel, industrial hygiene, radiation and medical records were examined for suitability, completeness and accuracy. It was necessary to assure that no possible errors or omissions in personnel and radiation records existed in order that the final data will have validity. Preliminary investigations on the methods of follow-up in the Portsmouth population and the time required for each procedure were also undertaken in order to have a better estimate of the total cost for a long term study

Feasibility study for a postaccident heat removal facility

International Nuclear Information System (INIS)

Barts, E.W.; Apperson, C.E. Jr.; Dunwoody, W.E.; Bennett, J.G.

1978-01-01

An initial feasibility investigation for PAHRTEF, a Postaccident Heat Removal Test Facility, is presented. The facility would provide an experimental capability for PAHR experiments beyond that available in any currently existing or proposed U.S. safety test facility. The facility design presented in this report is based upon the technology developed for the ROVER nuclear rocket propulsion program. The core is a graphite-moderated, helium-cooled, epithermal core with radial reflector control. The PAHR experiments are located just below the reactor containment vessel, very near the bottom of the core. The experiments (up to 55% enriched) are driven and controlled by neutrons leaking axially from the core such that the PAHRTEF core and the experiment form a coupled reactor system. The experiment can be designed so that it is extremely unlikely that the test fuel by itself could form a critical system. The investigation indicates that adequate fission heating of large PAHR experiments could be provided at low driver core power levels. Both the reactor and the experiment handling and examination equipment can use available technology and, whenever possible, existing equipment and buildings

Nuclear utility structure. Use of nuclear service companies

International Nuclear Information System (INIS)

Ring, L.E.

1980-01-01

The feasibility of utilities incorporating service companies to construct and maintain nuclear power plants is analyzed. Responsibilities of the service companies and the public opinion of the concept are discussed

Feasibility study on the construction and utilization of charged particle accelerators

International Nuclear Information System (INIS)

Cho, S.W.; Chung, M.K.; Choe, B.H.; Lee, K.W.; In, S.Y.; Park, I.S.; Kang, S.S.

1981-01-01

This is a report on the thorough studies of feasible accelerator to be constructed in Korea from various aspects. By following the brief descriptions on the operational principles and applications of various types of particle accelerators, estimations of required budgeting for construction and operation of those accelerators are given in detail. From the forecasted availability of government investment to accelerator project and also from the expected great role of accelerators to be played for nuclear power developments, we draw three steps' development program of accelerator technology in Korea. The first step is mainly aimed to user development and accumulation of accelerator technology through the construction and utilization of 50-100MeV electron linear accelerator. The second step to be recommended is the construction of 20-30MeV proton linear accelerator which can be used as an injector for future proton synchrotron. The third step is construction and utilization of several GeV proton synchrotron. However, development of accelerator technology in advanced countries is so fast that above-mentioned second and third step may not be regarded to be definite plans

PUEBLO OF ZIA RENEWABLE ENERGY DEVELOPMENT FEASIBILITY STUDY

Energy Technology Data Exchange (ETDEWEB)

Pino, Peter M. [Tribal Administrator (Ret.), Pueblo of Zia; Lakshman, Jai [Project Manager (NDA) for Pueblo of Zia; Toole, G. Loren [Principal Investigator, Los Alamos National Laboratory - Energy Analysis Team/ CCS-3, D-4; Hand, Dan [P.E., Sustainable Enginerring; Witcher, James; Emerson, Michael A. [Senior V.P., ARES Corporation; Turner, Jeremy [Executive Director, NM Renewable Energy Transmission Authority; Sandidge, Wendy [Director of Operations, NM Community Capital

2014-06-30

The Pueblo of Zia will conduct a comprehensive feasibility study for best-use application(s) for development of renewable energy resources on its tribally held TRUST lands (i.e., Trust Lands of Zia Indian Reservation). The feasibility study is essential for determining the technical and economic viability of a future renewable project(s) on Zia tribal lands, including the potential economic and environmental benefits for the Tribe. Project Objectives: The feasibility study is essential for determining the technical and economic viability of future renewable project(s) on Zia tribal lands, including the potential economic and environmental benefits for the Tribe to: 1. Provide a balanced local renewable power supply for Zia Pueblo, its members, tribal offices, schools and buildings, and businesses on tribal lands 2. Provide a firm power supply for export and commercial market distribution 3. Provide economic development for the Tribe and its members, including job training and creation, each in accordance with the goals and objectives as conveyed by the Pueblo of Zia Tribal Council, Tribal Administration, and outlined in The Pueblo of Zia Comprehensive Plan and Pueblo of Zia — Zia Enterprise Zone Master Plan. A key goal of the study is to analyze the integrated development of solar, geothermal, and wind renewable energy resources at Zia Pueblo, with added potential to combine gas-fired generation to accomplish energy firming. Geothermal offers a base load source of energy, providing power continuously for end users. Wind and solar offer intermediate and peaking sources of energy, which can be harvested throughout the day, with periods of variable but predicable output. Variability will be managed in an integrated manner, using Zia Pueblo's combined renewable resources to generate high-quality power. Tasks are intended to collect, catalog, map, and analyze existing data on Zia Pueblo's renewable energy resource base and then match resource attributes with

Feasibility of disposal of high-level radioactive waste into the seabed. Volume 3: Geoscience characterization studies

International Nuclear Information System (INIS)

Shephard, L.E.; Auffret, G.A.; Buckley, D.E.; Schuettenhelm, R.T.E.; Searle, R.C.

1988-01-01

One of the options suggested for disposal of high-level radioactive waste resulting from the generation of nuclear power is burial beneath the deep ocean floor in geologically stable sediment formations which have no economic value. The 8-volume series provides an assessment of the technical feasibility and radiological safety of this disposal concept based on the results obtained by ten years of co-operation and information exchange among the Member countries participating in the NEA Seabed Working Group. This report summarizes the results of a study performed to establish if, on the basis of available data, sites may be found that will satisfy the geoscience requirements for a potential subseabed high-level waste repository

Feasibility study on volcanic power generation system

Energy Technology Data Exchange (ETDEWEB)

None

1977-07-01

Investigations were carried out to determine the feasibility of volcanic power generation on Satsuma Io Island. Earthquakes were studied, as were the eruptions of subaerial and submarine hot springs. Hydrothermal rock alteration was studied and electrical surveys were made. General geophysical surveying was performed with thermocameras and radiation monitoring equipment. In particular, the Toyoba mine was studied, both with respect to its hot spring and its subsurface temperatures.

Technical and economic feasibility study for the reactivation of the integral test facility of IPEN/CNEN Nuclear Engineering Center

Energy Technology Data Exchange (ETDEWEB)

Biaty, Flávia P.; Rocha, Marcelo da S.; Oliveira, Otávio L. de, E-mail: flavia.biaty@usp.br, E-mail: msrocha@ipen.br, E-mail: otavioluis@ipen.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN-SP), São Paulo, SP (Brazil)

2017-07-01

The Integral Test Facility of Nuclear Engineering Center (CEN/IPEN/CNEN-SP), known as 'Loop 70', is a semi-industrial thermal-hydraulic test facility and can operate as a BWR (Boiling Water Reactor) or a PWR (Pressurizing Water Reactor) mode. Designed and built in the 1980's, it is currently disabled. The experimental circuits ('test loop') are facilities that reproduce the thermohydraulic and fluid dynamic conditions that occur inside a reactor and are used to simulate the practical reality which it is not possible to be obtained through mathematical models. In this context, this research project aims the development of a Business Plan to analyze the technical and economic feasibility related to the reactivation of the facility. This methodology (adapted to the government sector) is a decision-making tool that will offer a wide perspective of the project, set the guidelines and actions that will define the future of the facility and provide a general rule to make investments on it. This paper presents the historic aspects to better understand the Loop 70's current situation. It also presents information about similar facilities around the world, services that can be offered (thermal-hydraulics parameters measurements, equipment qualification and transient analysis due accident situations), results of the strategic analysis (SWOT) performed, specific goals for each critical success or failure factor of the facility, financial aspects related to the reactivation and an overview of the facility's perspectives. (author)

Technical and economic feasibility study for the reactivation of the integral test facility of IPEN/CNEN Nuclear Engineering Center

International Nuclear Information System (INIS)

Biaty, Flávia P.; Rocha, Marcelo da S.; Oliveira, Otávio L. de

2017-01-01

The Integral Test Facility of Nuclear Engineering Center (CEN/IPEN/CNEN-SP), known as 'Loop 70', is a semi-industrial thermal-hydraulic test facility and can operate as a BWR (Boiling Water Reactor) or a PWR (Pressurizing Water Reactor) mode. Designed and built in the 1980's, it is currently disabled. The experimental circuits ('test loop') are facilities that reproduce the thermohydraulic and fluid dynamic conditions that occur inside a reactor and are used to simulate the practical reality which it is not possible to be obtained through mathematical models. In this context, this research project aims the development of a Business Plan to analyze the technical and economic feasibility related to the reactivation of the facility. This methodology (adapted to the government sector) is a decision-making tool that will offer a wide perspective of the project, set the guidelines and actions that will define the future of the facility and provide a general rule to make investments on it. This paper presents the historic aspects to better understand the Loop 70's current situation. It also presents information about similar facilities around the world, services that can be offered (thermal-hydraulics parameters measurements, equipment qualification and transient analysis due accident situations), results of the strategic analysis (SWOT) performed, specific goals for each critical success or failure factor of the facility, financial aspects related to the reactivation and an overview of the facility's perspectives. (author)

NTRE extended life feasibility assessment

Science.gov (United States)

Results of a feasibility analysis of a long life, reusable nuclear thermal rocket engine are presented in text and graph form. Two engine/reactor concepts are addressed: the Particle Bed Reactor (PBR) design and the Commonwealth of Independent States (CIS) concept. Engine design, integration, reliability, and safety are addressed by various members of the NTRE team from Aerojet Propulsion Division, Energopool (Russia), and Babcock & Wilcox.

IPNS upgrade: A feasibility study

International Nuclear Information System (INIS)

1995-04-01

Many of Argonne National Laboratory's (ANL's) scientific staff members were very active in R ampersand D work related to accelerator-based spoliation sources in the 1970s and early 1980s. In 1984, the Seitz/Eastman Panel of the National Academy of Sciences reviewed U.S. materials science research facilities. One of the recommendations of this panel was that the United States build a reactor-based steady-state source, the Advanced Neutron Source (ANS), at Oak Ridge National Laboratory. Subsequently, R ampersand D activities related to the design of an accelerator-based source assumed a lower priority. The resumption of pulsed-source studies in this country started simultaneously with design activities in Europe aimed at the European Spallation Source (ESS). The European Community funded a workshop in September 1991 to define the parameters of the ESS. Participants in this workshop included both accelerator builders and neutron source users. A consortium of European countries has proposed to build a 5-MW pulsed source, and a feasibility study is currently under way. Soon after the birth of the ESS, a small group at ANL set about bringing themselves up to date on pulsed-source information since 1984 and studied the feasibility of upgrading ANL's Intense Pulsed Neutron Source (IPNS) to 1 MW by means of a rapidly cycling synchrotron that could be housed, along with its support facilities, in existing buildings. In early 1993, the Kohn panel recommended that (1) design and construction of the ANS should be completed according to the proposed project schedule and (2) development of competitive proposals for cost-effective design and construction of a 1-MW pulsed spallation source should be authorized immediately

IPNS upgrade: A feasibility study

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-04-01

Many of Argonne National Laboratory`s (ANL`s) scientific staff members were very active in R&D work related to accelerator-based spoliation sources in the 1970s and early 1980s. In 1984, the Seitz/Eastman Panel of the National Academy of Sciences reviewed U.S. materials science research facilities. One of the recommendations of this panel was that the United States build a reactor-based steady-state source, the Advanced Neutron Source (ANS), at Oak Ridge National Laboratory. Subsequently, R&D activities related to the design of an accelerator-based source assumed a lower priority. The resumption of pulsed-source studies in this country started simultaneously with design activities in Europe aimed at the European Spallation Source (ESS). The European Community funded a workshop in September 1991 to define the parameters of the ESS. Participants in this workshop included both accelerator builders and neutron source users. A consortium of European countries has proposed to build a 5-MW pulsed source, and a feasibility study is currently under way. Soon after the birth of the ESS, a small group at ANL set about bringing themselves up to date on pulsed-source information since 1984 and studied the feasibility of upgrading ANL`s Intense Pulsed Neutron Source (IPNS) to 1 MW by means of a rapidly cycling synchrotron that could be housed, along with its support facilities, in existing buildings. In early 1993, the Kohn panel recommended that (1) design and construction of the ANS should be completed according to the proposed project schedule and (2) development of competitive proposals for cost-effective design and construction of a 1-MW pulsed spallation source should be authorized immediately.

Nuclear plant life extension

International Nuclear Information System (INIS)

Negin, C.A.

1989-01-01

The nuclear power industry's addressing of life extension is a natural trend in the maturation of this technology after 20 years of commercial operation. With increasing emphasis on how plants are operated, and less on how to build them, attention is turning on to maximizing the use of these substantial investments. The first studies of life extension were conducted in the period from 1978 and 1982. These were motivated by the initiation, by the Nuclear Regulatory Commission (NRC), of studies to support decommissioning rulemaking. The basic conclusions of those early studies that life extension is feasible and worth pursuing have not been changed by the much more extensive investigations that have since been conducted. From an engineering perspective, life extension for nuclear plants is fundamentally the same as for fossil plants

Comparative analysis of public's perception of economic feasibility and reality for selected energy sources in Korea

International Nuclear Information System (INIS)

Roh, Seungkook; Jeong, Ik; Lee, Kibog; Kim, Dongwook; Kim, Hyunjin

2016-01-01

Controversy on nuclear energy has persisted ever since, but nuclear energy has maintained around 30% of electricity generation in Korea. This is because Korean wants to secure energy security and diversity of energy sources, but the most rational driver behind nuclear energy is the economic feasibility. Looking at the actual prices of electricity traded in the Korean Power Exchange, the price of electricity generated by nuclear energy is 39.1 Korean won per kWh, which is lower than that of other sources: 58.9 (bituminous coal), 221.8 (oil), 158.6 (gas), 170.9 (hydropower), 162.8 (wind) and 463.1 (photovoltaic). However only experts, regulators and people from electricity generation industry are aware of this fact and the public does not seem to be perceiving this correctly. This research, therefore, will compare the economic feasibility of energy sources and how it is perceived by the public in general. This research was able to identify the large gap between public's perception on and reality of economic feasibility of energy sources. There are two possible reasons for the gap. Firstly, the electricity price paid by the public is agnostic of energy sources. Therefore, it is difficult for the public to be aware that the electricity from nuclear energy is benefiting them and hence the public would be indifferent to the real economic feasibility. Secondly, public's awareness of nuclear reactor decommissioning and spent fuel processing along with easier access to relevant information the media would have played a role. In fact, number of press and media has questioned the economic feasibility of nuclear energy. However, the price of electricity generated by nuclear energy includes costs for future activities such as decommissioning, radioactive waste disposal and spent fuel disposal. The public seems to be not aware of such fact and therefore favoring the media. Such analysis leads to two major policy implications. Most importantly, the government should emphasize the

Conducting feasibilities in clinical trials: An investment to ensure a good study

Directory of Open Access Journals (Sweden)

Viraj Rajadhyaksha

2010-01-01

Full Text Available Conducting clinical trial feasibility is one of the first steps in clinical trial conduct. This process includes assessing internal and environmental capacity, alignment of the clinical trial in terms of study design, dose of investigational product, comparator, patient type, with the local environment and assessing potential of conducting clinical trial in a specific country. A robust feasibility also ensures a realistic assessment and capability to conduct the clinical trial. For local affiliates of pharmaceutical organizations, and contract research organizations, this is a precursor to study placement and influences the decision of study placement. This article provides details on different types of feasibilities, information which is to be included and relevance of each. The article also aims to provide practical hands-on suggestions to make feasibilities more realistic and informative.

Conducting feasibilities in clinical trials: an investment to ensure a good study.

Science.gov (United States)

Rajadhyaksha, Viraj

2010-07-01

Conducting clinical trial feasibility is one of the first steps in clinical trial conduct. This process includes assessing internal and environmental capacity, alignment of the clinical trial in terms of study design, dose of investigational product, comparator, patient type, with the local environment and assessing potential of conducting clinical trial in a specific country. A robust feasibility also ensures a realistic assessment and capability to conduct the clinical trial. For local affiliates of pharmaceutical organizations, and contract research organizations, this is a precursor to study placement and influences the decision of study placement. This article provides details on different types of feasibilities, information which is to be included and relevance of each. The article also aims to provide practical hands-on suggestions to make feasibilities more realistic and informative.

A feasibility study on FP transmutation for Self-Consistent Nuclear Energy System (SCNES)

International Nuclear Information System (INIS)

Fujita, Reiko; Kawashima, Masatoshi; Ueda, Hiroaki; Takagi, Ryuzo; Matsuura, Haruaki; Fujii-e, Yoichi

1997-01-01

A fast reactor core/fuel cycle concept is discussed for the future 'Self-Consistent Nuclear Energy System (SCNES)' concept. The present study mainly discussed long-lived fission products (LLFPs) burning capability and recycle scheme in the framework of metallic fuel fast reactor cycle, aiming at the goals for fuel breeding capability and confinement for TRU and radio-active FPs within the system. In present paper, burning capability for Cs135 and Zr93 is mainly discussed from neutronic and chemical view points, assuming metallic fuel cycle system. The recent experimental results indicate that Cs can be separable along with the pyroprocess for metal fuel recycle system, as previously designed for a candidate fuel cycle system. Combining neutron spectrum-shift for target sub-assemblies and isotope separation using tunable laser, LLFP burning capability is enhanced. This result indicates that major LLFPs can be treated in the additional recycle schemes to avoid LLFP accumulation along with energy production. In total, the proposed fuel cycle is an candidate for realizing SCNES concept. (author)

Challenges for development and provision of metrological quality control tools in nuclear safeguards, nuclear forensics and nuclear security

International Nuclear Information System (INIS)

Aregbe, Y.; Richter, S.; Jakopic, R.; Bauwens, J.; Truyens, J.; Sturm, M.; Bujak, R.; Eykens, R.; Kehoe, F.; Kuehn, H.; Hennessy, C.

2013-01-01

Joint advancements in quality control tools and measurement sciences of international reference and safeguards laboratories include: -) successful integration of the Modified Total Evaporation technique (MTE) as a new tool for routine thermal ionization mass spectrometry in nuclear safeguards and security, -) research and feasibility studies for the development of new materials standard, particularly for nuclear forensics (Certified Reference Materials - CRMs for age-dating), -) quality control tools to support the additional protocol and nuclear security (particle CRMs, NUSIMEP (inter-laboratory comparisons for U particle analysis), and -) scientific/technical advice, training and knowledge transfer. The European Safeguards Research and Development Association (ESARDA), the Institute of Nuclear Materials Management (INMM) and the CETAMA Commission from the French Commission of Atomic Energy and Alternative Energies (CEA/CETAMA) and the International Atomic Energy Agency (IAEA) Technical Meetings are the platforms to exchange views on the needs and challenges for new Quality Control tools for nuclear safeguards and security. The paper is followed by the slides of the presentation

Muon Beamline Commissioning and Feasibility Study for μSR at a New DC Muon Beamline, MuSIC-RCNP, Osaka University

Science.gov (United States)

Tomono, Dai; Fukuda, Mitsuhiro; Hatanaka, Kichiji; Higemoto, Wataru; Kawashima, Yoshitaka; Kojima, Kenji M.; Kuno, Yoshitaka; Matsuda, Yugo; Matsuzaki, Teiichiro; Miyake, Yasuhiro; Miyamoto, Koichiro; Morita, Yasuyuki; Motoishi, Takahiro; Nakazawa, Yu; Ninomiya, Kazuhiko; Nishikawa, Ryo; Ohta, Saki; Sato, Akira; Shimomura, Koichiro; Takahisa, Keiji; Weichao, Yao; Wong, Ming L.

At the new DC muon beamline MuSIC at Research Center for Nuclear Physics (RCNP), Osaka University, the beamline construction from the solenoid system of the muon production to the experimental port was completed. A beamline commissioning and a feasibility study for μSR are now in progress. With newly refurbished spectrometer installed at the experimental port, we succeeded in observing μSR spectra and μ-e decay asymmetry in a simple setup down to 4 K. We are still under development of other μSR appratuses.

Study of a conceptual nuclear energy center at Green River, Utah. Power demand, load center assessment and transmission

Energy Technology Data Exchange (ETDEWEB)

Smith, D.R.; Thaik, A.; Pingel, P.

1982-02-01

This document constitutes a segment of a feasibility study investigating the ramification of constructing a nuclear energy center in an arid western region. In this phase of the study. The projected power demands and load center locations were reviewed and assessed. Alternative transmission systems were analysed and a conceptual transmission for bulk power transportation is proposed with potential line routes. Environmental impacts of the proposed transmission were also identified.

Study of a conceptual nuclear energy center at Green River, Utah. Power demand, load center assessment and transmission

International Nuclear Information System (INIS)

Smith, D.R.; Thaik, A.; Pingel, P.

1982-02-01

This document constitutes a segment of a feasibility study investigating the ramification of constructing a nuclear energy center in an arid western region. In this phase of the study. The projected power demands and load center locations were reviewed and assessed. Alternative transmission systems were analysed and a conceptual transmission for bulk power transportation is proposed with potential line routes. Environmental impacts of the proposed transmission were also identified

Simultaneous nuclear data target accuracy study for innovative fast reactors

International Nuclear Information System (INIS)

Aliberti, G.; Palmiotti, G.; Salvatores, M.

2007-01-01

The present paper summarizes the major outcomes of a study conducted within a Nuclear Energy Agency Working Party on Evaluation Cooperation (NEA WPEC) initiative aiming to investigate data needs for future innovative nuclear systems, to quantify them and to propose a strategy to meet them. Within the NEA WPEC Subgroup 26 an uncertainty assessment has been carried out using covariance data recently processed by joint efforts of several US and European Labs. In general, the uncertainty analysis shows that for the wide selection of fast reactor concepts considered, the present integral parameters uncertainties resulting from the assumed uncertainties on nuclear data are probably acceptable in the early phases of design feasibility studies. However, in the successive phase of preliminary conceptual designs and in later design phases of selected reactor and fuel cycle concepts, there will be the need for improved data and methods, in order to reduce margins, both for economic and safety reasons. It is then important to define as soon as possible priority issues, i.e. which are the nuclear data (isotope, reaction type, energy range) that need improvement, in order to quantify target accuracies and to select a strategy to meet the requirements needed (e.g. by some selected new differential measurements and by the use of integral experiments). In this context one should account for the wide range of high accuracy integral experiments already performed and available in national or, better, international data basis, in order to indicate new integral experiments that will be needed to account for new requirements due to innovative design features, and to provide the necessary full integral data base to be used for validation of the design simulation tools.

Front Range Forest Health Partnership Phase 1 feasibility study

Energy Technology Data Exchange (ETDEWEB)

Volkin, P

1998-09-01

The Front Range Forest Health Partnership is an alliance of individuals, citizen groups, federal, state, private, and nonprofit organizations that formed to promote forest health restoration and reduce fire risks on Colorado's Front Range. The partnership promotes selective thinning to restore forest health and supports economically feasible end uses for wood waste materials. The Phase I study was initiated to determine the environmental and economic feasibility of using wood wastes from forested and urban areas for the production of fuel-grade ethanol.

Economics of nuclear desalination: New developments and site specific studies. Final results of a coordinated research project 2002-2006

International Nuclear Information System (INIS)

2007-07-01

Following successive General Conference Resolutions since the mid-eighties, the IAEA has continued to promote nuclear desalination and has been providing its Member States with the publication of guidebooks, technical documents and computer programs on nuclear desalination as well as the provision of technical assistance through the framework of technical cooperation programs. In 1997, the IAEA launched the International Nuclear Desalination Advisory Group (INDAG), with well known experts from 16 participating Member States. INDAG has not only been successful in its advisory role in all aspects dealing with nuclear desalination, but has also been extremely efficient in promoting exchange of information and creating contacts between technology providers and its end-users. A number of technical cooperation projects have assessed the feasibility of particular nuclear desalination projects. Under the IAEA inter-regional technical cooperation (TC) framework, several international collaboration activities were completed. For example: between China and Morocco; the Republic of Korea and Indonesia; France and Tunisia; and in Pakistan. TC national projects for the United Arab Emirates, Algeria and Jordan, for the techno-economic feasibility studies of nuclear desalination plants, are currently being considered. The Coordinated Research Project (CRP1) on Optimization of the Coupling of Nuclear Reactors and Desalination Systems was completed in 2003 with the participation of 11 Member States. The results of the CRP were published as IAEA-TECDOC-1444 (2005). Following recommendations from INDAG, a second CRP (CRP2) on Economic Research on, and Assessment of, Selected Nuclear Desalination Projects and Case Studies with the participation of ten Member States. It was started in 2002 and was completed in 2006. The scope of CRP2 was to enable the Member States to dispose of precise and well validated methods for desalination cost evaluations and to contribute to the IAEA's efforts

Pre-feasibility study template for nZEB pilot projects development

OpenAIRE

Crespo Sánchez, Eva

2015-01-01

This document corresponds to Task 5.2 NZEB pilot projects development, Deliverable 5.2 Basic project conceptual design with feasibility analysis for eight pilot project of the SUSTAINCO project and should present a structure of pre-feasibility studies for eight NZEB projects implementation. It aims to give an overview of how SUSTAINCO project implementation is to be prepared and which technical and financial parameters to concern.

Important considerations for feasibility studies in physical activity research involving persons with multiple sclerosis: a scoping systematic review and case study.

Science.gov (United States)

Learmonth, Yvonne C; Motl, Robert W

2018-01-01

Much research has been undertaken to establish the important benefits of physical activity in persons with multiple sclerosis (MS). There is disagreement regarding the strength of this research, perhaps because the majority of studies on physical activity and its benefits have not undergone initial and systematic feasibility testing. We aim to address the feasibility processes that have been examined within the context of physical activity interventions in MS. A systematic scoping review was conducted based on a literature search of five databases to identify feasibility processes described in preliminary studies of physical activity in MS. We read and extracted methodology from each study based on the following feasibility metrics: process (e.g. recruitment), resource (e.g. monetary costs), management (e.g. personnel time requirements) and scientific outcomes (e.g. clinical/participant reported outcome measures). We illustrate the use of the four feasibility metrics within a randomised controlled trial of a home-based exercise intervention in persons with MS. Twenty-five studies were identified. Resource feasibility (e.g. time and resources) and scientific outcomes feasibility (e.g. clinical outcomes) methodologies were applied and described in many studies; however, these metrics have not been systematically addressed. Metrics related to process feasibility (e.g. recruitment) and management feasibility (e.g. human and data management) are not well described within the literature. Our case study successfully enabled us to address the four feasibility metrics, and we provide new information on management feasibility (i.e. estimate data completeness and estimate data entry) and scientific outcomes feasibility (i.e. determining data collection materials appropriateness). Our review highlights the existing research and provides a case study which assesses important metrics of study feasibility. This review serves as a clarion call for feasibility trials that will

Standardization and Economics of Nuclear Spacecraft, Final Report, Phase I, Sense Study

Energy Technology Data Exchange (ETDEWEB)

1973-03-01

Feasibility and cost benefits of nuclear-powered standardized spacecraft are investigated. The study indicates that two shuttle-launched nuclear-powered spacecraft should be able to serve the majority of unmanned NASA missions anticipated for the 1980's. The standard spacecraft include structure, thermal control, power, attitude control, some propulsion capability and tracking, telemetry, and command subsystems. One spacecraft design, powered by the radioisotope thermoelectric generator, can serve missions requiring up to 450 watts. The other spacecraft design, powered by similar nuclear heat sources in a Brayton-cycle generator, can serve missions requiring up to 21000 watts. Design concepts and trade-offs are discussed. The conceptual designs selected are presented and successfully tested against a variety of missions. The thermal design is such that both spacecraft are capable of operating in any earth orbit and any orientation without modification. Three-axis stabilization is included. Several spacecraft can be stacked in the shuttle payload compartment for multi-mission launches. A reactor-powered thermoelectric generator system, operating at an electric power level of 5000 watts, is briefly studied for applicability to two test missions of divers requirements. A cost analysis indicates that use of the two standardized spacecraft offers sizable savings in comparison with specially designed solar-powered spacecraft. There is a duplicate copy.

Socioeconomic impacts: study of a conceptual nuclear energy center at Green River, Utah

International Nuclear Information System (INIS)

Weaver, R.; Taylor, J.; Burnett, K.; Greenberg, B.

1982-02-01

This document constitutes a segment of a feasibility study investigating the ramifications of constructing a nuclear energy center (NEC) in an arid western region. In this phase of the study, the impacts on socioeconomic conditions in the surrounding communities and possible ways of financing and mitigating these impacts were examined. The general conclusion reached is that the socioeconomic impacts of a nuclear energy center in the Green River area of Southeastern Utah would not impose an absolute bar to NEC development. The economy of the NEC impact area would be substantially transformed by the NEC. In particular, Green River city itself would change from its current status as a relatively stable rural economy with an agricultural, mining, and recreation base to a major city with over 20,000 permanent relatively high income residents. The NEC, by itself, would provide a tax base more than adequate to finance required expansion of public facilities and public human service provisions

Socioeconomic impacts: study of a conceptual nuclear energy center at Green River, Utah

Energy Technology Data Exchange (ETDEWEB)

Weaver, R.; Taylor, J.; Burnett, K.; Greenberg, B.

1982-02-01

This document constitutes a segment of a feasibility study investigating the ramifications of constructing a nuclear energy center (NEC) in an arid western region. In this phase of the study, the impacts on socioeconomic conditions in the surrounding communities and possible ways of financing and mitigating these impacts were examined. The general conclusion reached is that the socioeconomic impacts of a nuclear energy center in the Green River area of Southeastern Utah would not impose an absolute bar to NEC development. The economy of the NEC impact area would be substantially transformed by the NEC. In particular, Green River city itself would change from its current status as a relatively stable rural economy with an agricultural, mining, and recreation base to a major city with over 20,000 permanent relatively high income residents. The NEC, by itself, would provide a tax base more than adequate to finance required expansion of public facilities and public human service provisions.

Active Treatment for Idiopathic Adolescent Scoliosis (ACTIvATeS): a feasibility study.

Science.gov (United States)

Williams, Mark A; Heine, Peter J; Williamson, Esther M; Toye, Francine; Dritsaki, Melina; Petrou, Stavros; Crossman, Richard; Lall, Ranjit; Barker, Karen L; Fairbank, Jeremy; Harding, Ian; Gardner, Adrian; Slowther, Anne-Marie; Coulson, Neil; Lamb, Sarah E

2015-07-01

The feasibility of conducting a definitive randomised controlled trial (RCT) evaluating the clinical effectiveness and cost-effectiveness of scoliosis-specific exercises (SSEs) for adolescent idiopathic scoliosis (AIS) is uncertain. The aim of this study was to assess the feasibility of conducting a large, multicentre trial of SSE treatment for patients with AIS, in comparison with standard care, and to refine elements of the study design. The objectives were to (1) update a systematic review of controlled trials evaluating the efficacy of SSE in AIS; (2) survey UK orthopaedic surgeons and physiotherapists to determine current practice, patient populations and equipoise; (3) randomise 50 adolescents to a feasibility trial of either usual care or SSE interventions across a range of sites; (4) develop, document and assess acceptability and adherence of interventions; (5) assess and describe training requirements of physiotherapists; and (6) gain user input in all relevant stages of treatment and protocol design. Multicomponent feasibility study including UK clinician survey, systematic literature review and a randomised feasibility trial. The randomised feasibility study involved four secondary care NHS trusts providing specialist care for patients with AIS. The randomised feasibility study recruited people aged 10-16 years with mild AIS (Cobb angle of physiotherapy SSE programme supported by a home exercise plan. Our choice of intervention was informed by a systematic review of exercise interventions for AIS. The main outcome was feasibility of recruitment to the randomised study. Other elements were to inform choice of outcomes for a definitive trial and included curve severity, quality of life, requirement for surgery/brace, adverse events, psychological symptoms, costs and health utilities. A UK survey of orthopaedic consultants and physiotherapists indicated a wide variation in current provision of exercise therapy through physiotherapy services. It also found

Bond Feasibility Study. Project Identification Committee Report.

Science.gov (United States)

Wichita Public Schools, KS.

A committee, appointed by the Board of Education, was requested to make a comprehensive study of the school building needs of Unified School District No. 259. In an attempt to determine the feasibility of a general bond election to upgrade the public schools, the specific charge to the committee was to evaluate the needs for physical plant…

Status of Korean nuclear industry and Romania-Korea cooperation in the field of nuclear power

International Nuclear Information System (INIS)

Lee, Myung Key

2005-01-01

The Kyoto Protocol on climate change has urged the world to explore ways of cutting down the greenhouse emissions, and it also boosted a number of nuclear power projects that is so-called the renaissance of nuclear power. Nuclear power has proven to be the cleanest energy source and one of the cheapest types of energies, compared with other energy sources. Korea began developing its nuclear power projects from the early 1970's. Since the first nuclear power plant Kori Unit 1, started commercial operation in 1978, Korea has continuously promoted the development of nuclear power projects, and today it operates 20 nuclear power units (17,716 MW), including 4 units of CANDU plants. Korea ranked No. 6 in the world in terms of installed capacity of nuclear power plants, and 40% of its domestic electricity generation comes from nuclear power plants. The average plant capacity factor was 95.5% in 2005, which is about 16% than the world average of around 79%. All the Korean nuclear power projects are led and implemented by Korea Hydro and Nuclear Power Co. (KHNP) which is the sole state-owned nuclear power project company spun off from Korea Electric Power Corporation (KEPCO) in 2001 as part of the government's program for electric industry restructuring. The cooperation between Romania and Korea in the nuclear power field began in March 2001. At industrial level a technical agreement between the Romanian Company Nuclearelectrica S.A. (SNN) and KHNP was signed in July 2003 for cooperation in Cernavoda NPP projects. The joint development of the Cernavoda NPP unit 3 was one of the major topics. Heavy water produced by Romanian Heavy Water plant at Drobeta Turnu Severin was supplied to KHNP (16 tones in 2001 and another 16 tones in 2004). The feasibility study for units 3 and 4 is being performed in two phases under leadership of SNN in cooperation with KHNP, AECL, ANSALDO and Deloitte and Touche as a financial advisor in Phase 2. It is expected that the appropriate securities

IAEA's role in nuclear desalination

International Nuclear Information System (INIS)

Khamis, I.; )

2010-01-01

Currently, several Member States have shown interest in the utilization of the nuclear energy for seawater desalination not only because recent studies have demonstrated that nuclear desalination is feasible, but also economical and has been already demonstrated in several countries. Therefore, the article will provide a highlight on sea water desalination using nuclear energy as a potential for a sustainable development around the world and the IAEA role in this regards. Special emphasis is placed on past, present, and future nuclear desalination experience in various IAEA Member States. The International Atomic Energy Agency (IAEA) role could be summarized in facilitating cutting-edge developments in the area of seawater desalination using nuclear energy, and establishing a framework for facilitating activities in Member States through information exchange and provision of technical assistance. (author)

Preliminary feasibility study of modular reactors

International Nuclear Information System (INIS)

Yamaji, Kenji

1987-01-01

In the future, electric utilities will be required to make a switch-over to a more flexible and dynamic form of power supply due to the slowing growth of power demand, increasing uncertainty, the stagnating economy of increasing scale, the bottleneck of transmission and so on. Nuclear technology would also be required to adapt to this changing environment surrounding its development. The long term prospect of energy demand and nuclear power growth, and the evolution of commercial reactors in Japan are shown. The design of 1,300 MWe advanced LWRs has been completed, and as the reactors of next generation, the ultralarge LWRs of 1,500 - 1,800 MWe are suggested. However, there can be an alternative future for nuclear power development, and in this paper, the possibility for altering the image of conventional nuclear power technology by developing modular reactors which are economical even at small capacity, and can be sited in urban areas just like conventional thermal power plants is examined. The factors for the economical evaluation of modular reactors, learning effect and scale effect on the economy, the case study on a modular high temperature reactor designed by Interatom-GHT, and the possibility of siting in urban areas due to the system of inherent safety are reported. (Kako, I.)

Ear-EEG from generic earpieces: A feasibility study

DEFF Research Database (Denmark)

Kidmose, Preben; Looney, D; Jochumsen, Lars

2013-01-01

key patient needs (discreet, unobstrusive, user-friendly, robust) and that is low-cost and suitable for off-the-shelf use; thus promising great advantages for healthcare applications. Its feasibility is validated in a comprehensive comparative study with our established prototype, based...

Fast-mixed spectrum reactor interim report initial feasibility study

International Nuclear Information System (INIS)

Fischer, G.J.; Cerbone, R.J.

1979-01-01

The report summarizes the results of an initial four-month feasibility study of the Fast-Mixed Spectrum Reactor (FMSR). Reactor physics, fuel cycle, and thermal-hydraulic analyses were performed on a reference design. These results when coupled to a fuel and materials evaluation performed in cooperation with the Argonne National Laboratory indicate that the FMSR is feasible provided the fuels, cladding, and subassembly ducts can survive a peak fuel burnup of 15 to 20 atom percent heavy metal and peak fluences of 8 x 10 23 (nvt > 0.1 MeV). The results of this short study have also provided a basis for exploring alternative designs requiring significantly lower peak burnup and fluences for their operation

Development of human factors engineering guide for nuclear power project

International Nuclear Information System (INIS)

Wu Dangshi; Sheng Jufang

1997-01-01

'THE PRACTICAL GUIDE FOR APPLICATION OF HUMAN FACTORS ENGINEERING TO NUCLEAR POWER PROJECT (First Draft, in Chinese)', which was developed under a research program sponsored by National Nuclear Safety Administration (NNSA) is described briefly. It is hoped that more conscious, more systematical and more comprehensive application of Human Factors Engineering to the nuclear power projects from the preliminary feasibility studies up to the commercial operation will benefit the safe, efficient and economical operations of nuclear power plants in China

Longitudinal study of the feasibility of using ecological momentary assessment to study teacher stress: Objective and self-reported measures.

Science.gov (United States)

McIntyre, Teresa M; McIntyre, Scott E; Barr, Christopher D; Woodward, Phillip S; Francis, David J; Durand, Angelia C; Mehta, Paras; Kamarck, Thomas W

2016-10-01

There is a lack of comprehensive research on Ecological Momentary Assessment (EMA) feasibility to study occupational stress, especially its long-term sustainability. EMA application in education contexts has also been sparse. This study investigated the feasibility of using EMA to study teacher stress over 2 years using both objective compliance data and a self-reported feasibility survey. It also examined the influence of individual and school factors on EMA feasibility. Participants were 202 sixth through eighth grade teachers from 22 urban middle schools in the southern United States. EMA was implemented via an iPod-based Teacher Stress Diary (TSD). Teachers recorded demands, stress responses, and resources during 12 days (6 waves) over 2 years. Feasibility was assessed via compliance data generated by the TSD (e.g., entry completion) and an EMA Feasibility Survey of self-reported user-friendliness and EMA interference. The results showed high compliance regarding entry and item completion, and completion time, which was sustained over time. User-friendliness was appraised as very high and EMA interference as low. Initial difficulties regarding timing and length of assessments were addressed via EMA method refinement, resulting in improved feasibility. Teachers' ethnicity, age, marital status, grade/course taught, class size, class load, and daily workload impacted feasibility. The results supported the feasibility of using EMA to study work stress longitudinally and the value of continued feasibility monitoring. They also support EMA use to study teacher stress and inform EMA implementation in schools. Some teacher and school factors need to be taken into consideration when deciding on EMA implementation in education contexts. (PsycINFO Database Record (c) 2016 APA, all rights reserved).

LDC nuclear power: Venezuela

International Nuclear Information System (INIS)

Roche, M.

1982-01-01

Venezuela had an aggressive nuclear program when it was under a dictatorship in the 1950s, but it is currently assuming a wait-and-see stance. The country has one small research reactor, but it may have a reactor on-line in the mid-1990s. CONADIN, Venezuela's nuclear energy planning agency, has commissioned feasibility studies and requested proposals for a reactor-siting survey. A recent study for the Venezuelan state oil company suggests tha a natural-uranium, gas-cooled reactor could provide process steam to extract oil from the bituminous tar sands of the Orinoco Basin. Venezuela is also exploring for uranium reserves. 23 references, 1 figure, 2 tables

A study of feasibility, design and cost of excavations for underground siting of nuclear power plants

International Nuclear Information System (INIS)

1976-02-01

A study conducted for the State Power Board on underground siting of nuclear power plants is presented. The report is divided into two chapters, both concerning the technical aspects of large underground openings. The first chapter gives a brief general survey of the problems involved, and the second outlines the technical aspects of a PWR project at a specific site. Details are given in 8 appendices and arrangement drawings. The project differs from conventional hydroelectric excavation schemes mainly in the fact that the spherical reactor containment requires a vault of 60m free span, and the turbine hall a cylindrical vault of 45m span, both of which exceed any span hitherto built for similar purposes. This requires a comparatively wide extrapolation of tested and available experience in underground excavations for permanent civil use. To what extent and under what circumstances such extrapolation is tenable must be tested in practice, preferably in a specially controlled prototype test. However the study indicates that conventional nuclear power plants can be sited underground when the topography and rock conditions are suitable. A 1000-2000 MW conventional plant adapted for underground siting will require large span caverns, tunnels and shafts, totalling about 1.0 mill. cubic metres of underground excavation. In addition access and cooling water tunnels, depending on the location, will require 0.2-0.5 mill. cubic metres of tunnel excavations. The excavations and support work can be completed within a construction time of about 2 1/2 years at an estimated total cost of 215 mill. Norwegian kroner (1975 value). (JIW)

Quantum computation with nuclear spins in quantum dots

International Nuclear Information System (INIS)

Christ, H.

2008-01-01

The role of nuclear spins for quantum information processing in quantum dots is theoretically investigated in this thesis. Building on the established fact that the most strongly coupled environment for the potential electron spin quantum bit are the surrounding lattice nuclear spins interacting via the hyperfine interaction, we turn this vice into a virtue by designing schemes for harnessing this strong coupling. In this perspective, the ensemble of nuclear spins can be considered an asset, suitable for an active role in quantum information processing due to its intrinsic long coherence times. We present experimentally feasible protocols for the polarization, i.e. initialization, of the nuclear spins and a quantitative solution to our derived master equation. The polarization limiting destructive interference effects, caused by the collective nature of the nuclear coupling to the electron spin, are studied in detail. Efficient ways of mitigating these constraints are presented, demonstrating that highly polarized nuclear ensembles in quantum dots are feasible. At high, but not perfect, polarization of the nuclei the evolution of an electron spin in contact with the spin bath can be efficiently studied by means of a truncation of the Hilbert space. It is shown that the electron spin can function as a mediator of universal quantum gates for collective nuclear spin qubits, yielding a promising architecture for quantum information processing. Furthermore, we show that at high polarization the hyperfine interaction of electron and nuclear spins resembles the celebrated Jaynes-Cummings model of quantum optics. This result opens the door for transfer of knowledge from the mature field of quantum computation with atoms and photons. Additionally, tailored specifically for the quantum dot environment, we propose a novel scheme for the generation of highly squeezed collective nuclear states. Finally we demonstrate that even an unprepared completely mixed nuclear spin

Quantum computation with nuclear spins in quantum dots

Energy Technology Data Exchange (ETDEWEB)

Christ, H.

2008-01-24

The role of nuclear spins for quantum information processing in quantum dots is theoretically investigated in this thesis. Building on the established fact that the most strongly coupled environment for the potential electron spin quantum bit are the surrounding lattice nuclear spins interacting via the hyperfine interaction, we turn this vice into a virtue by designing schemes for harnessing this strong coupling. In this perspective, the ensemble of nuclear spins can be considered an asset, suitable for an active role in quantum information processing due to its intrinsic long coherence times. We present experimentally feasible protocols for the polarization, i.e. initialization, of the nuclear spins and a quantitative solution to our derived master equation. The polarization limiting destructive interference effects, caused by the collective nature of the nuclear coupling to the electron spin, are studied in detail. Efficient ways of mitigating these constraints are presented, demonstrating that highly polarized nuclear ensembles in quantum dots are feasible. At high, but not perfect, polarization of the nuclei the evolution of an electron spin in contact with the spin bath can be efficiently studied by means of a truncation of the Hilbert space. It is shown that the electron spin can function as a mediator of universal quantum gates for collective nuclear spin qubits, yielding a promising architecture for quantum information processing. Furthermore, we show that at high polarization the hyperfine interaction of electron and nuclear spins resembles the celebrated Jaynes-Cummings model of quantum optics. This result opens the door for transfer of knowledge from the mature field of quantum computation with atoms and photons. Additionally, tailored specifically for the quantum dot environment, we propose a novel scheme for the generation of highly squeezed collective nuclear states. Finally we demonstrate that even an unprepared completely mixed nuclear spin

Feasibility study on intersection in North Sumatera

Science.gov (United States)

Hastuty, I. P.; Sembiring, I. S.; Anas, R.; Lubis, A. S.

2018-02-01

Traffic congestion is one of the problems faced by big cities, One of them is Binjai city and Medan city in North Sumatera. One of the causes of congestion is intersection of roads with highway and roads with railroads. To ensure the smooth movement of vehicles, technical handling at the intersection is needed. Therefore, it is necessary to pre-study the feasibility of level crossing in Binjai and Medan to be able to assess the investment needs and the level of importance of road development in the region. The development of transportation infrastructure and facilities is based on the thought of improving the transportation network system. The necessity of systemical integrated transportation system handling is needed in creating a transportation efficiency. The purpose of this study is to identify and prioritize the needs of the railway crossings. The objective which we want to be achieved is to obtain a document that contains technical, economic and environmental ability indicators as a reference in the feasibility and planning studies. The methodology used is collecting the primary data, secondary data, introduction of study area as the initial analysis of the problem. From the study it can be concluded that the existence of railway interchange will move the movement through traffic so it will not interfere the movement of traffic within urban areas and it keeps the national road network performance is still good.

International Case-Control Study of Adult Brain, Head and Neck Tumours: Results of the Feasibility Study (invited paper)

International Nuclear Information System (INIS)

Cardis, E.; Kilkenny, M.

1999-01-01

The objectives of the feasibility study were to collect and analyse the information necessary to assess the feasibility of a multi-centric study of adult head and neck tumours (including brain tumours) and mobile telephones. Information was obtained on the availability and accessibility of records from companies, the prevalence of mobile telephone use over time and the expected number of tumour cases in the proposed study regions. The conclusion is that it is feasible to develop a study of the relation between mobile telephone use and brain cancer risk. The feasibility of a study of the relation between radiofrequency exposure and cancer risk is, however, unclear at present. It is unknown whether a sufficiently accurate and precise RF exposure gradient can be derived to classify adequately each subject in the proposed study. A study of the relation between mobile telephone use and risk of salivary gland tumours and acoustic neurinomas is probably feasible, but more information is required about the logistic difficulties of ascertaining these cases in the study regions. Two subcommittees have been formed to develop the exposure measurement and epidemiological aspect of the study. (author)

Feasibility study on naturally safe HTGR (NSHTR) for air ingress accident

Energy Technology Data Exchange (ETDEWEB)

Ohashi, Hirofumi, E-mail: ohashi.hirofumi@jaea.go.jp; Sato, Hiroyuki; Tachibana, Yukio; Kunitomi, Kazuhiko; Ogawa, Masuro

2014-05-01

A new design activity for an advanced reactor, referred to as a naturally safe high temperature gas-cooled reactor (NSHTR), has been launched by authors after the accident at the Fukushima Daiichi Nuclear Power Station. The concept of NSHTR is that the release of radioactive materials is kept at very low level and no harmful effect on people and the environment is ensured by only physical phenomena even in the absence of engineered safety features. At an air ingress accident, possible physical events that lead to the loss or degradation of the confinement function of the fuel-coating layers are the crack of the coatings caused by the explosion of carbon monoxide (CO) produced by the graphite oxidation and failure of the coatings by melting or sublimation caused by core heat up due to the reaction heat of the graphite oxidation. In this study, the CO concentration and the heat generated by graphite oxidation inside the circular tube were evaluated parametrically using a steady-state one-dimensional model to confirm the feasibility of NSHTR at a severe condition of the air ingress accident (i.e., a massive air ingress by simultaneous rupture of two primary pipes). It was confirmed that the CO concentration at the outlet of coolant channel can be maintained below the explosion limit due to the reaction with oxygen in the air, and the reaction heat can be removed with the decay heat by physical phenomena under certain conditions of the coolant channel geometry without any engineered safety features. The results revealed that the design of NSHTR is technically feasible in terms of the suppression of the CO explosion and the heat removal of the reaction heat at the air ingress accident.

DPC loading feasibility study report

International Nuclear Information System (INIS)

Dafoe, R.E.; Lopez, D.A.; Williams, K.L.

1997-11-01

Disposal of radioactive wastes now stored at the Idaho Chemical Processing Plant at the Idaho National Engineering and Environmental Laboratory is mandated under a ''Settlement Agreement'' between the Department of Energy and the State of Idaho. This study investigates the feasibility of using the Dry Transfer Cell facility to package waste into Dual Purpose Canisters for interim storage at the adjacent Dry Storage System comprised of an interim storage pad with NUHOMS reg-sign storage modules. The wastes would then be road-ready for eventual disposal in a permanent repository. The operating period for these activities is expected to be from 2015 to 2035

Feasibility study of networks. Progress report, July 15, 1976--December 14, 1976. [ARPANET

Energy Technology Data Exchange (ETDEWEB)

Campbell, E.J.; Kannel, M.; Saffran, K.

1976-10-15

The Laboratory for Nuclear Science continued its study of the implications of computer resource sharing via networks. This report describes the current experiments being performed on the ARPANET in collaboration with the Lawrence Berkeley Laboratory. It discusses and compares the use of mail and teleconferencing systems such as TDA and PLANET. Plans for future experiments on the ARPANET, for expansion of computer-aided communication facilities, and for investigation of networks other than the ARPANET are proposed. The conclusion reached by the study is that resource sharing via networks is both feasible and desirable, provided certain interface problems are solved. Recommendations are made for more investigation into the human factors involved in network use, methods of providing consulting help to users, and determination of the most cost-effective use of remote resource sharing. For the Laboratory for Nuclear Science, it was concluded that access to other ERDA computers via networks will meet some of the computing needs now and more in the future. However, remote resource sharing can be used only to supplement the on-site computer, not replace it. At the present time, the best method of accessing the ARPANET for Laboratory users is via the MIT Multics system. However, immediate needs for remote computing are such that network access is a viable solution as an adjunct to conventional remote job entry but not as a substitute. Therefore, it is proposed to acquire conventional remote job entry equipment on a temporary basis for a year to be used in conjunction with access to the ARPANET.

Training Endogenous Task Shifting Using Music Therapy: A Feasibility Study.

Science.gov (United States)

Lynch, Colleen; LaGasse, A Blythe

2016-01-01

People with acquired brain injury (ABI) are highly susceptible to disturbances in executive functioning (EF), and these effects are pervasive. Research studies using music therapy for cognitive improvement in this population are limited. The purpose of this study was to determine the feasibility of a Musical Executive Function Training (MEFT) intervention to address task-shifting skills in adults with ABI and to obtain preliminary evidence of intervention effect on task shifting. Fourteen participants were randomly assigned to one of three groups: a music therapy intervention group (MTG), a singing group (SG), or the no-intervention control group (CG). The SG and MTG met for one hour a day for five days. Feasibility measures included participant completion rates and intervention fidelity. Potential benefits were measured using the Trail Making Test and the Paced Auditory Serial Addition Task as a pre- and posttest measure. Participant completion rates and interventionist fidelity to the protocol supported feasibility. One-way ANOVA of the pre- and posttest group differences revealed a trend toward improvement in the MTG over the SG. Feasibility and effect size data support a larger trial of the MEFT protocol. © the American Music Therapy Association 2016. All rights reserved. For permissions, please e-mail: journals.permissions@oup.com.

Nuclear energy and nuclear technology

International Nuclear Information System (INIS)

Luescher, E.

1982-01-01

This book originated in the training courses for teachers of grammar- and secondary schools in Dillingen (Bavaria). The aim of these courses is to become informed about the latest state in one field of physics. The lectures are well-known experts in the respective fields. In the latest study (1980) of the National Academy of Sciences the experts came to the conclusion that without further development nuclear power plants the utilization of too much coal would become necessary and involve irreversible environmental damage (see chapter 6). There are two important obstacles impeding the further extension of nuclear energy. The first problem to be solved is the processing and storage of radioactive waste. This is a more technical task and can be treated in a satisfactory way. The second obstacle is less easy to take as the population has to be convinced that a nuclear power plant can be operated with almost unbelievable safety (see chapter 5) and be shut down safely in the case of incidents. The most promising possibility of controlled nuclear fusion as energy source is still many decades- if feasible at all- away from being performed (see chapter. 7). In the Soviet Union 25% of the electric energy production shall be proceed from nuclear power plants by the year 1990. (orig./GL) [de

Feasibility Study for Applicability of the Wavelet Transform to Code Accuracy Quantification

International Nuclear Information System (INIS)

Kim, Jong Rok; Choi, Ki Yong

2012-01-01

A purpose of the assessment process of large thermal-hydraulic system codes is verifying their quality by comparing code predictions against experimental data. This process is essential for reliable safety analysis of nuclear power plants. Extensive experimental programs have been conducted in order to support the development and validation activities of best estimate thermal-hydraulic codes. So far, the Fast Fourier Transform Based Method (FFTBM) has been used widely for quantification of the prediction accuracy regardless of its limitation that it does not provide any time resolution for a local event. As alternative options, several time windowing methods (running average, short time Fourier transform, and etc.) can be utilized, but such time windowing methods also have a limitation of a fixed resolution. This limitation can be overcome by a wavelet transform because the resolution of the wavelet transform effectively varies in the time-frequency plane depending on choice of basic functions which are not necessarily sinusoidal. In this study, a feasibility of a new code accuracy quantification methodology using the wavelet transform is pursued

Seawater desalination with nuclear power

International Nuclear Information System (INIS)

2005-01-01

Nuclear power helps reduce costs for energy-intensive processes such as seawater desalination. A new generation of innovative small and medium nuclear power plants could co-generate electricity and potable water from seawater, both safely and at competitive prices in today's market. The IAEA provides technical support to Member States facing water shortage problems, on assessing the viability of nuclear power in seawater desalination. The support, usually channelled through national Technical Cooperation (TC) projects, can take several forms, ranging from educational training and technical advice on feasibility studies to design and safety review of demonstration projects. The IAEA offers a software tool (DEEP) that can be used to evaluate the economics of the different desalination and heat source configurations, including nuclear and fossil options

Application study of nuclear technologies for dual use

Energy Technology Data Exchange (ETDEWEB)

Shin, Jae Gon; Chung, W. S.; Park, W. S.; Lee, K. W.; Cha, H. K.; Han, M. H.; Yoon, J. S.; Honh, D. H.; Park, J. Y.; Lee, C. H.; Yeo, J. W.; Jung, M.; Ra, G. H

2000-02-01

The projects for the joint development of technology common to the civilian and military sectors are being carried out at national level to maximize the utilization of limited resources. The technologies have been identified through a process which considered whether they are duplicates of the present military technology, whether they are necessary, and whether their realization is feasible. In addition, the problems surfaced during the identification process have been analyzed and suggestions to vitalize the military application of civilian nuclear technology are presented in the contexts of personal channel, institutional networking, R and D information exchange, and budgetary support. (author)

Second Nuclear Era

International Nuclear Information System (INIS)

Weinberg, A.M.; Spiewak, I.; Barkenbus, J.N.; Livingston, R.S.; Phung, D.L.

1984-03-01

The Institute for Energy Analysis with support from The Andrew W. Mellon Foundation has studied the decline of the present nuclear era in the United States and the characteristics of a Second Nuclear Era which might be instrumental in restoring nuclear power to an appropriate place in the energy options of our country. The study has determined that reactors operating today are much safer than they were at the time of the TMI accident. A number of concepts for a supersafe reactor were reviewed and at least two were found that show considerable promise, the PIUS, a Swedish pressurized water design, and a gas-cooled modular design of German and US origin. Although new, safer, incrementally improved, conventional reactors are under study by the nuclear industry, the complete lack of new orders in the United States will slow their introduction and they are likely to be more expensive than present designs. The study recommends that supersafe reactors be taken seriously and that federal and private funds both be used to design and, if feasible, to build a prototype reactor of substantial size. 146 references, 8 figures, 2 tables

Nuclear Design Study for Reduced Boron Concentration Operation

International Nuclear Information System (INIS)

Daing, Aung Tharn; Kim, Myung Hyun

2008-01-01

In PWR, Boron Dilution Accident (BDA) which is an inadvertent reduction of the soluble boron concentration in the primary coolant, can lead to a positive reactivity insertion and a power increase. In this study, an optimal Low Boron Concentration (LBC) core design will be developed by reducing an excess reactivity so as to possess passive inherently safety features as well as one of attentively preventive measures of BDA scenarios. The scope of the research project concerning the change of operational procedure in chemical shim system, will involve three main parts namely, nuclear design for LBC core, feasibility check on the proposed core in safety and costs, and PSA approach on design change benefits. In addition, successful system analysis of the reactivity effects due to boron dilution transients, require a full coupling between core thermal hydraulic, reactor dynamics, and the use of Computational Fluid Dynamics (CFD) codes

Nuclear Design Study for Reduced Boron Concentration Operation

Energy Technology Data Exchange (ETDEWEB)

Daing, Aung Tharn; Kim, Myung Hyun [Kyung Hee University, Yongin (Korea, Republic of)

2008-10-15

In PWR, Boron Dilution Accident (BDA) which is an inadvertent reduction of the soluble boron concentration in the primary coolant, can lead to a positive reactivity insertion and a power increase. In this study, an optimal Low Boron Concentration (LBC) core design will be developed by reducing an excess reactivity so as to possess passive inherently safety features as well as one of attentively preventive measures of BDA scenarios. The scope of the research project concerning the change of operational procedure in chemical shim system, will involve three main parts namely, nuclear design for LBC core, feasibility check on the proposed core in safety and costs, and PSA approach on design change benefits. In addition, successful system analysis of the reactivity effects due to boron dilution transients, require a full coupling between core thermal hydraulic, reactor dynamics, and the use of Computational Fluid Dynamics (CFD) codes.

A feasibility study of thyroid cancer among patients treated with I-131

International Nuclear Information System (INIS)

Anderson, T.W.

1984-04-01

This study examined the feasibility of conducting a Canada-wide follow-up study of persons receiving I-131 before 1970, to see if current estimates of induction of thyroid cancer are well founded. It is concluded that such a study is not feasible due to the widespread destruction of old records, and the limited quantity of personal identifying information on those records that do still exist

Feasibility study for private-sector treatment services for alpha-contaminated low-level mixed wastes

International Nuclear Information System (INIS)

Bloom, R.R.; Rodriguez, R.R.

1995-01-01

Rust Federal Services, under contract to the United States Department of Energy (DOE), Idaho Operations Office, performed a study to develop and evaluate the feasibility of a suggested private sector solution for the treatment of alpha-contaminated low-level mixed waste (ALLMW) stored or produced at the Idaho National Engineering Laboratory (INEL). The feasibility study is an initial step in the potential procurement of privatized treatment services for these wastes. Rust's derived objective of the feasibility study was to define an optimal treatment system and analyze the feasibility of that system for accomplishing the processing objectives specified by DOE. All aspects of the selected treatment system were addressed in the feasibility study, including technical, regulatory, public involvement, and financial considerations. Two central elements of the study were a technology screening task to select the optimal treatment system and an analysis of the institutional, business, financial, and contractual issues that are likely to accompany the privatization of treatment services for DOE

Introduction of nuclear desalination. A guidebook

International Nuclear Information System (INIS)

2000-01-01

Interest in using nuclear energy for producing potable water has been growing worldwide in the past decade. This has been motivated by wide varieties of reasons, inter alia, from economic competitiveness of nuclear energy to energy supply diversification, from conservation of limited fossil fuel resources to environmental protection, and by nuclear technology in industrial development. IAEA feasibility studies, which have been carried out with participation of interested Member States since 1989, have shown that nuclear desalination of seawater is technically and economically viable in many water shortage regions. In view of its perspectives, several Member States have, or are planning to launch, demonstration programmes on nuclear desalination. This guidebook has been prepared for the benefit of such Member States so that the development could be facilitated as well as their resources could be shared among such interested Member States. This guidebook comprises three major parts: Part I - Overview of nuclear desalination, Part II - Special aspects and considerations relevant to the introduction of nuclear desalination, and Part III - Steps to introduce nuclear desalination. In Part I, an overview of relevant technologies and pertinent experience accumulated in the past is presented. The global situation of the freshwater problem is reviewed and incentives for utilizing nuclear energy to contribute to solving the problems are briefly set forth. State-of-the-art relevant technologies and experience with them are summarized. Part II identifies special aspects to be considered in decision making process concerning nuclear desalination. There are technical, safety and environmental and economical aspects as well as national requirements. In Part III necessary steps to be taken once nuclear desalination has been selected are elaborated. Policy issues are discussed, and project planning is summarized. This point also elaborates on project implementation aspects, which

Relativity damps OPEP in nuclear matter

International Nuclear Information System (INIS)

Banerjee, M.K.

1998-06-01

Using a relativistic Dirac-Brueckner analysis the OPEP contribution to the ground state energy of nuclear matter is studied. In the study the pion is derivative-coupled. The author finds that the role of the tensor force in the saturation mechanism is substantially reduced compared to its dominant role in a usual nonrelativistic treatment. He shows that the damping of derivative-coupled OPEP is actually due to the decrease of M * /M with increasing density. He points out that if derivative-coupled OPEP is the preferred form of nuclear effective lagrangian nonrelativistic treatment of nuclear matter is in trouble. Lacking the notion of M * it cannot replicate the damping. He suggests an examination of the feasibility of using pseudoscalar coupled πN interaction before reaching a final conclusion about nonrelativistic treatment of nuclear matter

Fundamental aspects of nuclear physics

International Nuclear Information System (INIS)

Haxton, W.C.

1987-01-01

I am pleased to be able to attend this symposium in honor of D. Allan Bromley and to see the new accelerator of the Yale University Nuclear Structure Laboratory. My talk on symmetry tests seems appropriate for this occasion: so much of the progress in this field depends on detailed knowledge of nuclear structure. The nuclear ''tricks'' that are played to filter and amplify interactions are possible because the nuclear spectroscopists have cataloged nuclear levels and determined their properties. I will describe how such nuclear structure studies may help to provide a window on physics beyond the standard model. My talk is not a summary of this subfield of nuclear physics. There is simply too much happening today to make a summary talk feasible. Instead, I have chosen four topics that I hope are representative of the field as a whole: parity mixing of nuclear states, time-reversal-odd nuclear moments, the Mikheyev-Smirnov enhancement of solar neutrino oscillations, and a nuclear experiment to monitor the long-term rate of stellar collapse in the galaxy. 39 refs., 5 figs., 1 tab

A study on the nuclear foreign policy

International Nuclear Information System (INIS)

Lee, Byungwook; Lee, H. M.; Ko, H. S.; Ryu, J. S.; Noh, B. C.

2008-12-01

This study addresses four arenas to effectively assist national nuclear foreign policies under international nuclear nonproliferation regimes and organizations. Firstly, this study analyzes the trends of the international nuclear non-proliferation regime, which includes the Treaty on the Non-proliferation of Nuclear Weapons (NPT), the international nuclear export control regime, and proposals for assurance of nuclear fuel supply. Secondly, this study analyzes the trends of international nuclear organizations, which include the IAEA as a central body of international nuclear diplomacy and technical cooperation and the OECD/NEA as a intergovernmental organization to consist of nuclear advanced countries. Thirdly, this study predicts the nuclear foreign policy of Obama Administration and reviews U. S.-India nuclear cooperation. Lastly, this study analyzes the nuclear issues of North Korea and current issues for regulation of nuclear materials.

Comparative analysis of public's perception of economic feasibility and reality for selected energy sources in Korea

Energy Technology Data Exchange (ETDEWEB)

Roh, Seungkook; Jeong, Ik; Lee, Kibog [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Kim, Dongwook [KAIST, Daejeon (Korea, Republic of); Kim, Hyunjin [Korea Nuclear Energy Agency, Seoul (Korea, Republic of)

2016-10-15

Controversy on nuclear energy has persisted ever since, but nuclear energy has maintained around 30% of electricity generation in Korea. This is because Korean wants to secure energy security and diversity of energy sources, but the most rational driver behind nuclear energy is the economic feasibility. Looking at the actual prices of electricity traded in the Korean Power Exchange, the price of electricity generated by nuclear energy is 39.1 Korean won per kWh, which is lower than that of other sources: 58.9 (bituminous coal), 221.8 (oil), 158.6 (gas), 170.9 (hydropower), 162.8 (wind) and 463.1 (photovoltaic). However only experts, regulators and people from electricity generation industry are aware of this fact and the public does not seem to be perceiving this correctly. This research, therefore, will compare the economic feasibility of energy sources and how it is perceived by the public in general. This research was able to identify the large gap between public's perception on and reality of economic feasibility of energy sources. There are two possible reasons for the gap. Firstly, the electricity price paid by the public is agnostic of energy sources. Therefore, it is difficult for the public to be aware that the electricity from nuclear energy is benefiting them and hence the public would be indifferent to the real economic feasibility. Secondly, public's awareness of nuclear reactor decommissioning and spent fuel processing along with easier access to relevant information the media would have played a role. In fact, number of press and media has questioned the economic feasibility of nuclear energy. However, the price of electricity generated by nuclear energy includes costs for future activities such as decommissioning, radioactive waste disposal and spent fuel disposal. The public seems to be not aware of such fact and therefore favoring the media. Such analysis leads to two major policy implications. Most importantly, the government should

Deschutes estuary feasibility study: hydrodynamics and sediment transport modeling

Science.gov (United States)

George, Douglas A.; Gelfenbaum, Guy; Lesser, Giles; Stevens, Andrew W.

2006-01-01

Continual sediment accumulation in Capitol Lake since the damming of the Deschutes River in 1951 has altered the initial morphology of the basin. As part of the Deschutes River Estuary Feasibility Study (DEFS), the United States Geological Survey (USGS) was tasked to model how tidal and storm processes will influence the river, lake and lower Budd Inlet should estuary restoration occur. Understanding these mechanisms will assist in developing a scientifically sound assessment on the feasibility of restoring the estuary. The goals of the DEFS are as follows. - Increase understanding of the estuary alternative to the same level as managing the lake environment.

400-MWe Consolidated Nuclear Steam System (CNSS). 1200-MWt Phase 2A interim studies

International Nuclear Information System (INIS)

1978-09-01

The Phase 2A interim studies of the Consolidated Nuclear Steam System (CNSS) consisted of a number of separate task studies addressing the design concepts developed during the Phase 1 study reported in BAW--1445. The purpose of the interim studies was to better establish overall concept feasibility from both a hardware and economic standpoint, to make modification and additions to the design where appropriate, and to understand and reduce the technical risks in critical areas of the design. The work on these task studies included input from Barberton, Mt. Vernon, and the Alliance Research Center as well as United Engineers and Constructors (UE and C). The UE and C work was carried out under a separate DOE contract

A Feasibility Study of Youth Apprenticeship in Arkansas.

Science.gov (United States)

Jobs for the Future, Inc., West Somerville, MA.

A study assessed the feasibility and attractiveness of youth apprenticeship in Arkansas in over 80 interviews with employers in 5 key Arkansas industries and occupations. They were allied health, food processing (equipment repair and maintenance and lab technician/quality control), information services, metalworking, and self-employment and…

Mindfulness and Climate Change Action: A Feasibility Study

Directory of Open Access Journals (Sweden)

Maggie Grabow

2018-05-01

Full Text Available Pro-environmental behaviors and the cultural shifts that can accompany these may offer solutions to the consequences of a changing climate. Mindfulness has been proposed as a strategy to initiate these types of behaviors. In 2017, we pilot-tested Mindful Climate Action (MCA, an eight-week adult education program that delivers energy use, climate change, and sustainability content in combination with training in mindfulness meditation, among 16 individuals living in Madison, WI. We collected participant data at baseline and at different times across the study period regarding household energy use, transportation, diet, and health and happiness. This pilot study aimed to evaluate the feasibility of the various MCA study practices including measurement tools, outcome assessment, curriculum and related educational materials, and especially the mindfulness-based climate action trainings. MCA was well-received by participants as evidenced by high adherence rate, high measures of participant satisfaction, and high participant response rate for surveys. In addition, we successfully demonstrated feasibility of the MCA program, and have estimated participant’s individual carbon footprints related to diet, transportation, and household energy.

Technical Analysis Feasibility Study on Smart Microgrid System in Sekolah Tinggi Teknik PLN

Science.gov (United States)

Suyanto, Heri

2018-02-01

Nowadays application of new and renewable energy as main resource of power plant has greatly increased. High penetration of renewable energy into the grid will influence the quality and reliability of the electricity system, due to the intermittent characteristic of new and renewable energy resources. Smart grid or microgrid technology has the ability to deal with this intermittent characteristic especially if these renewable energy resources integrated to grid in large scale, so it can improve the reliability and efficiency of the grid. We plan to implement smart microgrid system at Sekolah Tinggi Teknik PLN as a pilot project. Before the pilot project start, the feasibility study must be conducted. In this feasibility study, the renewable energy resources and load characteristic at the site will be measured. Then the technical aspect of this feasibility study will be analyzed. This paper explains that analysis of ths feasibility study.

Methodology study: Co-generation feasibility at sawmills

International Nuclear Information System (INIS)

Host, J.

1991-01-01

This report discussed the various factors that should be studied and evaluated before establishing a cogeneration plant. The results of three case studies and a survey of energy needs in smaller and medium size sawmills are also presented. In general, cogeneration is feasible for supplying electric energy required for processing logs using fuelbark and other residues from the manufacturing process. A rebuilt turbine-generator unit is an initial cost saving alternative that is advantageous throughout the life of the operation

Nuclear power strategy: requirements for technology

International Nuclear Information System (INIS)

Orlov, V.V.; Rachkov, V.I.

2001-01-01

The possible role of nuclear power in sustainable development demands answers to at least three questions: Is large-scale nuclear power essential to future development? - Is it feasible to have modern nuclear power transformed for large-scale deployment? - When will large-scale nuclear power be practically needed? The questions are analysed with the requirements to be fulfilled concerning present-day technologies

Defining Feasibility and Pilot Studies in Preparation for Randomised Controlled Trials: Development of a Conceptual Framework.

Directory of Open Access Journals (Sweden)

Sandra M Eldridge

Full Text Available We describe a framework for defining pilot and feasibility studies focusing on studies conducted in preparation for a randomised controlled trial. To develop the framework, we undertook a Delphi survey; ran an open meeting at a trial methodology conference; conducted a review of definitions outside the health research context; consulted experts at an international consensus meeting; and reviewed 27 empirical pilot or feasibility studies. We initially adopted mutually exclusive definitions of pilot and feasibility studies. However, some Delphi survey respondents and the majority of open meeting attendees disagreed with the idea of mutually exclusive definitions. Their viewpoint was supported by definitions outside the health research context, the use of the terms 'pilot' and 'feasibility' in the literature, and participants at the international consensus meeting. In our framework, pilot studies are a subset of feasibility studies, rather than the two being mutually exclusive. A feasibility study asks whether something can be done, should we proceed with it, and if so, how. A pilot study asks the same questions but also has a specific design feature: in a pilot study a future study, or part of a future study, is conducted on a smaller scale. We suggest that to facilitate their identification, these studies should be clearly identified using the terms 'feasibility' or 'pilot' as appropriate. This should include feasibility studies that are largely qualitative; we found these difficult to identify in electronic searches because researchers rarely used the term 'feasibility' in the title or abstract of such studies. Investigators should also report appropriate objectives and methods related to feasibility; and give clear confirmation that their study is in preparation for a future randomised controlled trial designed to assess the effect of an intervention.

Defining Feasibility and Pilot Studies in Preparation for Randomised Controlled Trials: Development of a Conceptual Framework.

Science.gov (United States)

Eldridge, Sandra M; Lancaster, Gillian A; Campbell, Michael J; Thabane, Lehana; Hopewell, Sally; Coleman, Claire L; Bond, Christine M

2016-01-01

We describe a framework for defining pilot and feasibility studies focusing on studies conducted in preparation for a randomised controlled trial. To develop the framework, we undertook a Delphi survey; ran an open meeting at a trial methodology conference; conducted a review of definitions outside the health research context; consulted experts at an international consensus meeting; and reviewed 27 empirical pilot or feasibility studies. We initially adopted mutually exclusive definitions of pilot and feasibility studies. However, some Delphi survey respondents and the majority of open meeting attendees disagreed with the idea of mutually exclusive definitions. Their viewpoint was supported by definitions outside the health research context, the use of the terms 'pilot' and 'feasibility' in the literature, and participants at the international consensus meeting. In our framework, pilot studies are a subset of feasibility studies, rather than the two being mutually exclusive. A feasibility study asks whether something can be done, should we proceed with it, and if so, how. A pilot study asks the same questions but also has a specific design feature: in a pilot study a future study, or part of a future study, is conducted on a smaller scale. We suggest that to facilitate their identification, these studies should be clearly identified using the terms 'feasibility' or 'pilot' as appropriate. This should include feasibility studies that are largely qualitative; we found these difficult to identify in electronic searches because researchers rarely used the term 'feasibility' in the title or abstract of such studies. Investigators should also report appropriate objectives and methods related to feasibility; and give clear confirmation that their study is in preparation for a future randomised controlled trial designed to assess the effect of an intervention.

A real-time computer simulation of nuclear simulator software using standard PC hardware and linux environments

International Nuclear Information System (INIS)

Cha, K. H.; Kweon, K. C.

2001-01-01

A feasibility study, which standard PC hardware and Real-Time Linux are applied to real-time computer simulation of software for a nuclear simulator, is presented in this paper. The feasibility prototype was established with the existing software in the Compact Nuclear Simulator (CNS). Throughout the real-time implementation in the feasibility prototype, we has identified that the approach can enable the computer-based predictive simulation to be approached, due to both the remarkable improvement in real-time performance and the less efforts for real-time implementation under standard PC hardware and Real-Time Linux envrionments

Pre-feasibility study of 80mw onshore wind farm

International Nuclear Information System (INIS)

Almas, M.S.

2014-01-01

This paper discusses a pre-feasibility study of 80MW onshore wind farm in the KPK (Khyber Pakhtunkhwa) province previously known as NWFP (North West Frontier) Province of Pakistan. The realistic data of wind speed is collected from Laboratory of Meteorology and Climatology (University of the Punjab) to study the feasibility of wind farm. Detailed analysis of wind turbines from four different manufacturers is carried out together with justifications of selecting a particular wind turbine. Issues related to site selection, wind farm civil foundation, recommendations for a particular choice of tower along with environmental effects are presented. Wind data analysis is carried out by using WINDROSE PRO software to determine the resultant direction of wind at the selected site for wind farm layout. The wind distribution at hub height of the wind turbine is calculated and is used to compute annual power production by the wind farm using power curves of the wind turbine. Electrical network integration issues of wind farm to the external grid are studied and the optimum point of connection is proposed. Finally, economic analysis of the whole wind farm project depending upon the LCC (Life Cycle Cost Analysis) is presented and the feasibility of the project from the investor's point of view is identified. The study concludes that the cost per kilowatt hour of electricity generated by this wind power plant will be 10.4 PKR/kWh and the payback period for the whole project is about 11.2 years. (author)

Necessity of long term nuclear data development for various applications needing nuclear data

International Nuclear Information System (INIS)

Fukahori, Tokio

2001-01-01

Necessity of long term nuclear data development for accelerator-driven system target design, high-energy radiation shielding, medical application, space and astrophysical applications, etc. is described in this paper. For each application field needing nuclear data, considered were importance of nuclear data in determining the success or failure of the application, important gaps remaining in the nuclear data and feasibility of filling the gaps with a modest research effort. It can be concluded much more international discussions are required. (author)

A Study on the Nuclear Foreign Policy

International Nuclear Information System (INIS)

Lee, Byung Wook; Lee, H. M.; Ko, H. S.; Ryu, J. S.; Oh, K. B.; Yang, M. H.; Lee, K. S.

2007-12-01

This study approaches the international trends related to nuclear non-proliferation in four aspects. First, this study analyzes the trend of the international nuclear non-proliferation regime, which includes the Treaty on the Non-proliferation of Nuclear Weapons (NPT), the international nuclear export control regime and proposals for assurance of nuclear fuel supply. Second, this study analyzes the trend of international nuclear organizations, which includes the International Atomic Energy Agency (IAEA), a central body of development of nuclear technology and international nuclear diplomacy, and the Organization for Economic Co-operation and Development/Nuclear Energy Agency (OECD/NEA), a intergovernmental organization to consist of a group of nuclear advanced countries. Third, this study analyzes the trends of the U.S.'s nuclear foreign policies, particularly nuclear non-proliferation. Fourth, this study analyzes the nuclear issues of North Korea and Iran as they cause serious concerns to a international society

A Study on the Nuclear Foreign Policy

Energy Technology Data Exchange (ETDEWEB)

Lee, Byung Wook; Lee, H. M.; Ko, H. S.; Ryu, J. S.; Oh, K. B.; Yang, M. H.; Lee, K. S

2007-12-15

This study approaches the international trends related to nuclear non-proliferation in four aspects. First, this study analyzes the trend of the international nuclear non-proliferation regime, which includes the Treaty on the Non-proliferation of Nuclear Weapons (NPT), the international nuclear export control regime and proposals for assurance of nuclear fuel supply. Second, this study analyzes the trend of international nuclear organizations, which includes the International Atomic Energy Agency (IAEA), a central body of development of nuclear technology and international nuclear diplomacy, and the Organization for Economic Co-operation and Development/Nuclear Energy Agency (OECD/NEA), a intergovernmental organization to consist of a group of nuclear advanced countries. Third, this study analyzes the trends of the U.S.'s nuclear foreign policies, particularly nuclear non-proliferation. Fourth, this study analyzes the nuclear issues of North Korea and Iran as they cause serious concerns to a international society.

Theoretical studies in nuclear reactions and nuclear structure

International Nuclear Information System (INIS)

1992-05-01

Research in the Maryland Nuclear Theory Group focusses on problems in four basic areas of current relevance. Hadrons in nuclear matter; the structure of hadrons; relativistic nuclear physics and heavy ion dynamics and related processes. The section on hadrons in nuclear matter groups together research items which are aimed at exploring ways in which the properties of nucleons and the mesons which play a role in the nuclear force are modified in the nuclear medium. A very interesting result has been the finding that QCD sum rules supply a new insight into the decrease of the nucleon's mass in the nuclear medium. The quark condensate, which characterizes spontaneous chiral symmetry breaking of the late QCD vacuum, decreases in nuclear matter and this is responsible for the decrease of the nucleon's mass. The section on the structure of hadrons contains progress reports on our research aimed at understanding the structure of the nucleon. Widely different approaches are being studied, e.g., lattice gauge calculations, QCD sum rules, quark-meson models with confinement and other hedgehog models. A major goal of this type of research is to develop appropriate links between nuclear physics and QCD. The section on relativistic nuclear physics represents our continuing interest in developing an appropriate relativistic framework for nuclear dynamics. A Lorentz-invariant description of the nuclear force suggests a similar decrease of the nucleon's mass in the nuclear medium as has been found from QCD sum rules. Work in progress extends previous successes in elastic scattering to inelastic scattering of protons by nuclei. The section on heavy ion dynamics and related processes reports on research into the e + e - problem and heavy ion dynamics

Economic consideration for Indonesia's nuclear power program

International Nuclear Information System (INIS)

Ahimsa, D.; Sudarsono, B.

1987-01-01

Indonesia experienced relatively high economic growth during the 1970s and the energy supply system was strained to keep up with demand. Several energy studies were thus carried out around 1980, including a nuclear power planning study and a nuclear plant feasibility study. During the 1980s, economic growth rates were subtantially lower, but surprisingly electricity demand remained fairly high. In 1984 it was therefore decided to update previous nuclear power studies. This effort was completed in 1986. Using energy projections and cost estimates developed during the updating of previous nuclear power studies, the paper discusses the economic justification for a nuclear power program in Indonesia. Results of the update, including computer runs of MAED and WASP models supplied by the IAEA, will be presented along with appropriate sensitivity analysis. These results are then analyzed in the light of 1986 developments in international oil price. Preparations for the forthcoming nuclear power program are described, including the construction of a multi-purpose reactor and associated laboratories in Serpong, near Jakarta. (author)