WorldWideScience
1

News from the world; Echos du monde  

Energy Technology Data Exchange (ETDEWEB)

This document gathers a series of very short articles concerning nuclear industry around the world. Areva company is investing 30 million euros in its Chalon-Saint-Marcel plant, it is the consequence of the extension of service life of nuclear power plants in the Usa. Areva holds 40% of the American market concerning the replacement of steam generators and 50% of that concerning the replacement of closure heads. The Obrigheim nuclear power plant was definitely closed down on may 2004, this decommissioning is a step forward in the German policy of progressively stepping out of nuclear energy. Chinese authorities are willing to construct 40 nuclear reactors in 15 years, despite that, the contribution of nuclear energy to the generation of electricity will reach only 4% in 2020. In 2007 Cea will begin the construction works of a new research reactor (Jules Horowitz reactor) in the Cadarache site. Prices of ...

2005-04-01

5

Investigation of thermohydraulic processes in steam generators for nuclear power stations equipped with VVER reactors  

British Library Electronic Table of Contents (United Kingdom)

The results obtained from experimental investigations and mathematical simulation of horizontal steam generators are considered. Recommendations for continuing these works are given.

2006-01-01

6

Core power distribution measurement and data processing in Daya Bay Nuclear Power Station  

International Nuclear Information System (INIS)

For the first time in China, Daya Bay Nuclear Power Station applied the advanced technology of worldwide commercial pressurized reactors to the in-core detectors, the leading excore six-chamber instrumentation for precise axial power distribution, and the related data processing. Described in this article are the neutron flux measurement in Daya Bay Nuclear Power Station, and the detailed data processing.

7

International Space Station Overview - NASA  

Science.gov (United States)

(accumulates & stores brine for disposal). Separator. (separates water from purge gases). ? Purge pump periodically vent ... Reactor Health. Sensor. ( verifies reactor is operating w/n limits) ... Waste and Hygiene Compartment ...

8

Alteration in reactor installation (addition of Unit 2) in the Sendai Nuclear Power Station of Kyushu Electric Power Co., Inc  

International Nuclear Information System (INIS)

The deliveration by the Nuclear Safety Commission was commenced on the alteration in reactor installation, as it had been inquired by the Ministry of International Trade and Industry. The alteration is the additional installation of the reactor No. 2 in the Sendai Nuclear Power Station, Kyushu Electric Power Co., Inc. It is a PWR power plant with thermal output of about 2,660 MW (electric output of 890 MW), to be installed, adjoining to the reactor No. 1 of the same type and capacity under construction. In the examination by MITI, it was confirmed that the technological capabilities for its construction and operation and the radiation protection measures in power generation are both sufficient. The contents of the examination include the siting conditions, the location and construction of reactor facilities, etc. (J.P.N.).

1980-01-01

9

Alteration in reactor installation (addition of Unit 2) in the Sendai Nuclear Power Station of Kyushu Electric Power Co. , Inc  

Energy Technology Data Exchange (ETDEWEB)

The deliberation by the Nuclear Safety Commission was initiated on the alteration in reactor installation, as was required by the Ministry of International Trade and Industry. The alteration is the additional installation of the reactor No. 2 in the Sendai Nuclear Power Station, Kyushu Electric Power Co., Inc. It is a PWR power plant with thermal output of about 2,660 MW (electric output of 890 MW), to be installed, adjoining to the reactor No. 1 of the same type and capacity under construction. In the examination by MITI, it was confirmed that the technological capabilities for its construction and operation and the radiation protection measures in power generation are both sufficient. The contents of the examination include the siting conditions, the location and construction of reactor facilities, etc.

1980-10-01

10

Cordoba and Wolsung Projects: A Progress Report.  

Science.gov (United States)

The Cordoba and Wolsung projects mark the entry into the international sales arena of the standardized Canadian 600 MWe CANDU-PHW reactor design. The Cordoba station experienced a setback in the early stages when severe inflation in Argentina led to a ren...

1977-01-01

11

Consideration of field experience in developing new projects of steam generators for nuclear power stations equipped with VVER reactors  

British Library Electronic Table of Contents (United Kingdom)

The main problems encountered during the operation of horizontal steam generators are considered. Design features of the new PGV-1000MK and PGV-1500 steam generators are analyzed.

2006-01-01

12

Study of dose rates and radionuclides contributing to dose rates in India's 540 MWe pressurised heavy water reactors  

International Nuclear Information System (INIS)

Tarapur Atomic Power Station Unit-3 and 4 (TAPS -3 and 4) are the 540 MWe reactors. Unit-4 attained first criticality on 06th March 2005 and operated for about 230 effective full power days (EFPD). Unit-3 attained first criticality on 21st May 2006 and operated for about 20 EFPD. With the reactor operation radiation field increases on the Primary Heat Transport system equipments, Moderator system equipments and auxiliary system equipments due to deposition of fission products and activation products in different reactor systems. These dose rates significantly contributes to the external exposure and stations collective dose during reactor operation, refueling operation and maintenance activities. A study was undertaken at TAPS 3 and 4 to identify the system equipments showing the significant dose rates and identify the radionuclides present in the primary heat ...

2006-11-13

13

Support required from Canada in the operation and maintenance of CANDU stations overseas  

International Nuclear Information System (INIS)

The long-term support required from Canada in the operation and maintenance of overseas CANDU nuclear generating stations after commercial operation has commenced is described, with reference entirely to the KANUPP reactor. This includes: technical support to station staff to increase plant reliability and maintainability; assistance with plant improvements; procurement of spares and consumables; and assistance with training programmes. This technical support may be provided by a small number of Canadian staff actually resident at the power station; by short-term visits of Canadian specialists to site and by technical and procurement services provided from Canada. Examples of technical problems experienced are given, showing typical services required from Canada.

14

Modeling of a horizontal steam generator for the submerged nuclear power station concept  

Energy Technology Data Exchange (ETDEWEB)

A submerged nuclear power station has been proposed as an alternative power station with a relatively low environmental impact for use by both industrialized and developing countries. The station would be placed 10 m above the seabed at a depth of 30--100 m and a distance of 10--30 km from shore. The submerged nuclear power station would be manufactured and refueled in a central facility, thus gaining the economies of factoryfabrication and the flexibility of short-lead-time deployment. To minimize the size of the submerged hull, horizontal steam generators are proposed for the primary-to-secondary heat transfer, instead of the more traditional vertical steam generators. The horizontal steam generators for SNPS would be similar in design to the horizontal steam generators used in the N-Reactors except the tube orientation is horizontal (the tube's inlet and outlet ...

1993-01-01

15

Modeling of a horizontal steam generator for the submerged nuclear power station concept  

Energy Technology Data Exchange (ETDEWEB)

A submerged nuclear power station has been proposed as an alternative power station with a relatively low environmental impact for use by both industrialized and developing countries. The station would be placed 10 m above the seabed at a depth of 30--100 m and a distance of 10--30 km from shore. The submerged nuclear power station would be manufactured and refueled in a central facility, thus gaining the economies of factoryfabrication and the flexibility of short-lead-time deployment. To minimize the size of the submerged hull, horizontal steam generators are proposed for the primary-to-secondary heat transfer, instead of the more traditional vertical steam generators. The horizontal steam generators for SNPS would be similar in design to the horizontal steam generators used in the N-Reactors except the tube orientation is horizontal (the tube`s inlet and outlet connection points ...

1993-05-01

16

Modeling of a horizontal steam generator for the submerged nuclear power station concept  

International Nuclear Information System (INIS)

A submerged nuclear power station has been proposed as an alternative power station with a relatively low environmental impact for use by both industrialized and developing countries. The station would be placed 10 m above the seabed at a depth of 30--100 m and a distance of 10--30 km from shore. The submerged nuclear power station would be manufactured and refueled in a central facility, thus gaining the economies of factoryfabrication and the flexibility of short-lead-time deployment. To minimize the size of the submerged hull, horizontal steam generators are proposed for the primary-to-secondary heat transfer, instead of the more traditional vertical steam generators. The horizontal steam generators for SNPS would be similar in design to the horizontal steam generators used in the N-Reactors except the tube orientation is horizontal (the tube's inlet and outlet connection points ...

1993-07-06

17

Steam generator tube failures: experience with water-cooled nuclear power reactors during 1976  

International Nuclear Information System (INIS)

A survey was conducted of experience with steam generator tubes at nuclear power stations during 1976. Failures were reported at 25 out of 68 water-cooled reactors. The causes of these failures and the repair and inspection procedures designed to cope with them are summarized. Examination of the data indicates that corrosion was the major cause of steam generator tube failures. Improvements are needed in steam generator design, condenser integrity and secondary water chemistry control. (author).

1994-10-18

18

Atoms at work  

International Nuclear Information System (INIS)

This illustrated booklet describes the fission process; the use of uranium to produce power in nuclear power stations (and a brief explanation of the differences between the principal types of reactor); the formation of plutonium and fission products; radioactive wastes and their management; nuclear fusion and a conceptual fusion reactor; alpha, beta and gamma radiations; radioisotopes and their applications. (U.K.).

19

A computer program for estimating decommissioning costs for light water reactors  

Energy Technology Data Exchange (ETDEWEB)

This report discusses a desk-top computer program has been developed for estimating the costs, waste volumes, and occupational radiation exposures associated with decommissioning light-water reactor power stations. Cost categories and cost algorithms used in the program are discussed and a brief description of the user interface is given.

1993-02-01

20

Design modifications in 540 MWe and its impact on the dose rates  

International Nuclear Information System (INIS)

Exposure control at the operating Nuclear Power Station is a major concern. TAPS Unit-4 is the first Pressurized Heavy Water Reactor of 540 MWe electrical capacity. This unit was made critical on March 6, 2005. In-depth review of radiation safety was done to identify the impact of design modification on dose rates at various locations and on the equipment's. Problems encountered in controlling the dose rates in 220 MWe electrical are eliminated by appropriate design modifications. Due to higher capacity of the unit there are design changes in major systems such as reactor core, primer heat transport system, moderator system, reactor regulation and protection systems. Reactor operations and maintenance activities during shut down contributes to exposure of the employees. Based on the experience gained in the operation of 220 MWe, design modifications incorporated in TAPS unit-4 and ...

2005-11-23

21

Steam turbines  

International Nuclear Information System (INIS)

The author gives the historical development of steam-turbine construction in Europe since the turn of the century, and the technical further development of conventional turbines due to the increases in the steam parameters and per-unit outputs in the increases in the steam parameters and per-unit outputs in Europe and the USA. Marginal conditions for the development of turbines in nuclear power stations with light-water reactors are mentioned. The rise in the per-unit capacities of the turbosets constructed in Germany and the USA for nuclear power stations is discussed. Longitudinal sections through typical turbines are shown. The future development of turbines with high output is dealt with. (orig.).

22

Regulatory aspects about the licensing of the improved technical specifications for the CNLV  

International Nuclear Information System (INIS)

The Operation Technical Specifications is a document that is attached to the Operation License of a nuclear power station and its are applicable since the first load of fuel begins in the reactor core. This document is normative and with its application it is assured the safe operation of the nuclear power station. For the case of the Laguna Verde Nucleo electric Central this is documented in the Condition No. 5 of the License of Operation. Any modification to the ETOs is subject to the evaluation by part of the regulator organism. This work describes the regulator frame and the evaluation process of the Improved Technical Specifications on the part of the regulator organism. It is also indicated the implementation process of the improved ETOs and the main characteristics and benefits that are obtained of these processes to maintain the safety of the nuclear power stations. (Author)

2007-07-01

23

Alteration of installation of reactors (alteration of No. 1 and No. 2 reactor facilities) in the Sendai Nuclear Power Station, Kyushu Electric Power Co. , Inc  

Energy Technology Data Exchange (ETDEWEB)

The Nuclear Safety Commission presented the report to the Minister of International Trade and Industry on April 5, 1984, after the careful investigation and deliberation on the alteration of installation of No.1 and No.2 reactor facilities in the Sendai Nuclear Power Station. The technical capability of Kyushu Electric Power Co., Inc., was recognized to be adequate. It was judged that the safety after this alteration of installation of the reactor facilities can be ensured. The main items of examination were as follows. The mechanical, nuclear and thermo-hydraulic designs of 17 x 17 B-type fuel assemblies were regarded as adequate. The coexistence of A-type and B-type fuel assemblies does not cause any problem about the safety. The safety at the time of abnormal transient change and accident in the mixed fuel assembly core was confirmed. In No.2 reactor, the degree of enrichment of the fuel for ...

1984-08-01

24

Study on tritium activity build-up in moderator and primary heat transport systems in 540 MWe reactor  

International Nuclear Information System (INIS)

Tarapur Atomic Power Station unit-4 is first 540 MWe pressurized heavy water reactor. Heavy water is used as the coolant and moderator. With reactor operation tritium is formed by absorption of neutron by Deuterium atoms. Experience in the 220 MWe indicates that tritium is main contributor to the internal dose of radiation workers. Study on Tritium build up in Primary Heat Transport (PHT) and Moderator (MOD) system was carried out at the initial stage of the operation of the unit-3 and 4. This paper brings out tritium activity buildup in the PHT and MOD systems and its comparison with 220 MWe reactors. This paper helps in estimation of the internal dose contribution to the radiation workers at TAPS 3 and 4. (author)

2006-11-13

25

Study on tritium activity build-up in moderator and primary heat transport (PHT) systems in 540 MWe reactor  

International Nuclear Information System (INIS)

Tarapur Atomic Power Station unit-4 is first 540 MWe pressurized heavy water reactor. Heavy water is used as the coolant and moderator. With reactor operation tritium is formed by absorption of neutron by deuterium atoms. Experience in the 220 MWe indicates that tritium is main contributor to the internal dose of radiation workers. Study on tritium build up in Primary Heat Transport (PHT) and Moderator (MOD) system was carried out at the initial stage of the operation of the unit-4. This paper brings out tritium activity buildup in the PHT and MOD systems and its comparison with 220 MWe reactors. This paper helps in estimation of the internal dose contribution to the radiation workers at TAPS 3 and 4. (author)

2005-11-23

26

Advanced Neutron Source: Plant Design Requirements  

Energy Technology Data Exchange (ETDEWEB)

The Advanced Neutron Source will be a new world-class facility for research using hot, thermal, cold, and ultra-cold neutrons. The heart of the facility will be a 330-MW (fission), heavy-water cooled and heavy-water moderated reactor. The reactor will be housed in a central reactor building, with supporting equipment located in an adjoining reactor support building. An array of cold neutron guides will fan out into a large guide hall, housing about 30 neutron research stations. Appropriate office, laboratory, and shop facilities will be included to provide a complete facility for users. The ANS is scheduled to begin operation at the Oak Ridge National Laboratory early in the next decade. This PDR document defines the plant-level requirements for the design, construction, and operation of ANS. It also defines and provides input to the individual System Design Description (SDD) ...

1990-07-01

27

Standardization/improvement and technical development of light water reactor power station in Japan(BWR)  

Energy Technology Data Exchange (ETDEWEB)

In order to realize improve of reliability and economy by duplicate production, rapid supply of repair parts from standardized storage, such were expected as to have continuous order of standardized plant, to ignore site condition, to avoid expansion of regulatory requirement. Standardization program was planned to limitedly promote standardization of safety-related design concept, major specification and basic system composition of reactor and primary systems. The area of standardization had been tried to expand to BOP such as general arrangement and rad-waste system.

1985-07-01

28

A review of the behaviour of alloy 800 in liquid sodium  

International Nuclear Information System (INIS)

Although there is service experience of Alloy 800 as tubing for superheaters in conventional and nuclear (HTR) power stations and in PWR heat exchangers, there is no corresponding service experience in sodium-cooled fast reactor steam generators. However, some limited experimental studies have been made of corrosion behaviour, and of possible structure modifications and effects on mechanical properties which occur during exposure of this material to a high temperature sodium environment, and these are summarised in the paper. It is concluded that further work needs to be done before Alloy 800 can be confidently endorsed for use as tubing in fast reactor steam generators. (author).

29

Cooling of nuclear power stations with high temperature reactors and helium turbine cycles  

International Nuclear Information System (INIS)

On nuclear power stations with high temperature reactors and helium turbine cycles (HTR-single circuits) the residual heat from the energy conversion process in the primary and intermediate coolers is removed from cycled gas, helium. Water, which is circulated for safety reasons through a closed circuit, is used for cooling. The primary and intermediate coolers as well as other cooling equipment of the power plant are installed within the reactor building. The heat from the helium turbine cycle is removed to the environment most effectively by natural draught cooling towers. In this way a net plant efficiency of about 40% is attainable. The low quantities of residual heat thereby produced and the high (in comparison with power stations with steam turbine cycles) cooling agent pressure and cooling water reheat pressure in the circulating coolers enable an economically favourable design of the overall ...

30

Results of third regular inspection of No. 2 plant in Sendai Nuclear Power Station, Kyushu Electric Power Co. , Inc  

Energy Technology Data Exchange (ETDEWEB)

The third regular inspection of No.2 plant in Sendai Nuclear Power Station was carried out from December 27, 1988 to May 25, 1989. The parallel operation was resumed on April 28, 1989, 123 days after the parallel off. The facilities which were the object of inspection were the reactor proper, reactor cooling system, measurement and control system, fuel facilities, radiation control facilities, waste facilities, reactor containment installation and emergency electric power generation system. On the facilities which were the object of inspection, the appearance, disassembling, leak, function, performance and other inspections were carried out. As the results, significant in indication was observed in 8 bolts for fixing the flow-changing vanes of primary coolant pumps, and broken valve spindles were found, but other abnormality was not found. The works related to this regular inspection were accomplished ...

1990-03-01

31

Results of second regular inspection of No.2 plant in Sendai Nuclear Power Station, Kyushu Electric Power Co., Inc  

International Nuclear Information System (INIS)

The second regular inspection of No.2 plant in Sendai Nuclear Power Station was carried out from October 5, 1987 to January 8, 1988. the parallel operation was resumed on December 8, 1987, 65 days after the parallel off. The facilities as the object of inspection were the reactor proper, reactor cooling system, measurement and control system, fuel facilities, radiation control facilities, waste facilities, reactor containment installation, and emergency power generation system. On these facilities as the object of inspection, the appearance, disassembling, leak, function, performance and other inspections were carried out, and abnormality was not found at all. The works related to this regular inspection were accomplished within the range of allowable dose based on the relevant laws. The main reconstruction works carried out during the period of this regular inspection were the change of the degree of ...

1988-01-01

32

Results of second regular inspection of No. 2 plant in Sendai Nuclear Power Station, Kyushu Electric Power Co. , Inc  

Energy Technology Data Exchange (ETDEWEB)

The second regular inspection of No.2 plant in Sendai Nuclear Power Station was carried out from October 5, 1987 to January 8, 1988. the parallel operation was resumed on December 8, 1987, 65 days after the parallel off. The facilities as the object of inspection were the reactor proper, reactor cooling system, measurement and control system, fuel facilities, radiation control facilities, waste facilities, reactor containment installation, and emergency power generation system. On these facilities as the object of inspection, the appearance, disassembling, leak, function, performance and other inspections were carried out, and abnormality was not found at all. The works related to this regular inspection were accomplished within the range of allowable dose based on the relevant laws. The main reconstruction works carried out during the period of this regular inspection were the change of the degree of ...

1988-08-01

33

Research and implementation of stretch-out operation in Daya Bay Nuclear Power Station  

International Nuclear Information System (INIS)

Stretch-out operation mode can deepen the reactor burnup when the boron concentration is near 0 mg/L, in which the additional reactivity is introduced by the reducing of the moderator temperature and the decreasing of the load. Stretch-out is used in many nuclear power plants all over the world. The first stretch-out operation has been used for the first time in China. As a specific operation mode, which outruns the original reactor core design, the related and specialized design argument and safety analysis is required. As a consequence of the continuous or stepwise reduction of load and moderator temperature, the neurotic measurement system and the reactor control and protection system parameters should be modified specially. Based on the schedule of the electricity production, the first stretch-out operation had been carried out from March 12 to March 21 2003. It successfully avoided the overlapping between 209 and 109 ...

2006-02-01

34

Safety evaluation report related to the operation of Grand Gulf Nuclear Station, Units 1 and 2. Dockets Nos. 50-416 and 50-417, Mississippi Power and Light Company; Middle South Energy, Inc. , South Mississippi Electric Power Association  

Energy Technology Data Exchange (ETDEWEB)

Supplement 2 to the Safety Evaluation Report for Mississippi Power and Light Company, et. al, joint application for licenses to operate the Grand Gulf Nuclear Station, Units 1 and 2, located on the east bank of the Mississippi River near Port Gibson, in Claiborne County, Mississippi, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status of certain items that had not been resolved at the time of publication of the Safety Evaluation Report.

1982-06-01

35

Fingerprint testing of contaminated ventilation extract filter systems at Sizewell B  

International Nuclear Information System (INIS)

Sizewell B is Nuclear Electric's latest power station, and the Pressurised Water Reactor (PWR) design on which it is based represents a ''first'' for the UK. One of the integral components of the plant is the heating, ventilation and air-conditioning (HVAC) system, which performs a contamination control and gaseous waste management function for the site. During the commissioning of Sizewell B Power Station the extract systems of the HVAC plant underwent a procedure known as ''fingerprinting''. This entailed the characterisation of the facilities provided to test the filtration plant during its lifetime. The assessment of their adequacy was then used to identify necessary modifications and/or to propose the manner in which future in situ performance testing would be carried out. The paper outlines the basic principles and procedure that was used to ''fingerprint'' test systems during the commissioning of Sizewell B. A ...

36

On important matters (fire protection) related to No. 3 plant in the Hamaoka Nuclear Power Station, Chubu Electric Power Co., Inc., No. 2 plant in the Tsuruga Power Station, Japan Atomic Power Co., and No. 2 plant in the Sendai Nuclear Power Station, Kyushu Electric Power Co., Inc  

International Nuclear Information System (INIS)

The Nuclear Safety Commission acknowledged the policy of the Agency of Natural Resources and Energy to cope with these important matters on August 8, 1984. The main contents of the investigation and deliberation were as follows, As to the prevention of the occurrence of fires, the prevention of the leak and spread of inflammable liquid and gas, the installation of protective relays and so on, the use of incombustible materials and aseismatic design and the installation of lightning arresters. As to the detection of fires and fire fighting, the proper selection and arrangement of fire detectors and extinguishers, the extinguishers which do not harm the safety function of structures and equipment, and the extinguishers which are not affected by natural phenomena. As to the reduction of the effect of fires, the proper installation of fire walls and extinguishers, and the high temperature shut off of nuclear reactors which is never hampered by any fire. (Kako, I.).

1985-01-01

37

The behavior of fission products during nuclear rocket reactor tests  

Energy Technology Data Exchange (ETDEWEB)

The experience base regarding fission product behavior developed during the Rover program, the nuclear rocket development program of 1955--1972, will be useful in planning a renewed nuclear rocket program. During the Rover program, 20 reactors were tested at the Nuclear Rocket Development Station in Nevada. Nineteen of these discharged effluent directly into the atmosphere; the last reactor tested, a non-flight-prototypic, fuel-element-testing reactor called the Nuclear Furnace (NF-1) was connected to an effluent cleanup system that removed fission products before the hydrogen coolant (propellant) was discharged to the atmosphere. In general, we are able to increase both test duration and fuel temperature during the test series. Therefore fission product data from the later part of the program are more interesting and more applicable to future reactors. We have collected fission ...

1991-01-01

38

Highlights of design and construction of Sendai Nuclear Power Station Unit No.2  

International Nuclear Information System (INIS)

As for No.2 plant in Sendai Nuclear Power Station, which is the fourth nuclear power generation facilities in Kyushu Electric Power Co., Inc., all works have been completed, and at present, the final trial operation is under way. In No.2 plant, many new techniques for raising the reliability and safety, improving the maintainability and reducing radiation exposure were introduced on the basis of the operation experience of PWRs obtained so far, similarly to No.1 plant. In this paper, the main items of the new techniques related to the design and construction of the plant are reported. No. 2 plant is a first improved and standardized plant having the thermal output of 2660 MW for standard three-loop PWRs, and the rated power output was set at 890 MW. As for the turbine, TC6F-40 in was adopted. As the improved design, a large reactor containment vessel, 17 x 17 type 9-grid fuel, improved steam generators, a reactor vessel ...

1985-01-01

39

A pilot application of risk-based methods to establish in-service inspection priorities for nuclear components at Surry Unit 1 Nuclear Power Station  

International Nuclear Information System (INIS)

As part of the Nondestructive Evaluation Reliability Program sponsored by the US Nuclear Regulatory Commission, the Pacific Northwest Laboratory is developing a method that uses risk-based approaches to establish in-service inspection plans for nuclear power plant components. This method uses probabilistic risk assessment (PRA) results and Failure Modes and Effects Analysis (FEMA) techniques to identify and prioritize the most risk-important systems and components for inspection. The Surry Nuclear Power Station Unit 1 was selected for pilot applications of this method. The specific systems addressed in this report are the reactor pressure vessel, the reactor coolant, the low-pressure injection, and the auxiliary feedwater. The results provide a risk-based ranking of components within these systems and relate the target risk to target failure probability values for individual components. These results will be used to guide ...

40

On the threshold of the 21st Century in the Soviet Union  

International Nuclear Information System (INIS)

In the last 30 years the production of electricity in the USSR has increased 14-fold, probably attaining 1540 billion kWH in 1985. Nuclear generation will provide the bulk of future increases of consumption, using both water-cooled and uranium/graphite reactors; stations of up to 1.5 million kW are in service. The USSR is also in the fore-front of attempts to exploit thermonuclear power. The USSR is also conducting experiments with renewable sources of energy such as solar, geothermal, wind and wave power and with magnetohydrodynamic generation. (D.A.J.).

41

Nuclear design analysis of wolsung-1 CANDU-PHW nuclear generating station  

International Nuclear Information System (INIS)

A combination of computer codes such as LATREP, HWRAXAV and CITATION is utilized in an attempt to analyze the nuclear design characteristics of the CAXDU-PHWR of the Wolsung Unit 1. The major nuclear properties to be computed are the lattice properties of CANDU fuel channel and the core channel power distribution. The computed results are compared with the preliminary safety reports documentation for the Wolsung reactor. The observed discrepancies between our computations and the preliminary safety reports values are discussed in terms of incomplete information on the description of the core configuration in the preliminary safety reports and the different calculation methods. (author).

1978-01-01

42

FORTUM Participation in BARCOM Round Robin pre-test simulation: mid-term analysis  

Energy Technology Data Exchange (ETDEWEB)

In the study a preliminary mid-term analysis of the BARCOM test model is presented. The BARCOM test model is a 1:4 scale of an existing pressurized heavy water reactor (PHWR) pre-stressed concrete inner containment of 540 MW Tarapur Atomic Power Station 3 and 4 units in India. The goal of this midterm analysis is to illustrate the modeling approach and achieve a prediction of the failure mode. The analysis was carried out using ABAQUS/CAE and ABAQUS/EXPLICIT version 6.7-EF1 software

2009-07-01

43

The estimation of lifetime distribution of Alloy 800 steam generator tubing  

Energy Technology Data Exchange (ETDEWEB)

Alloy 800 has been used for steam generator (SG) tubing for more than 30 years, primarily in CANDU reactors worldwide and in reactors in Germany. Extensive laboratory testing and in-service experience suggest that the Alloy 800 tubing has excellent resistance to corrosion-related degradation under appropriate operating conditions. In planning refurbishment of nuclear plants stations, a key concern is the longevity of existing SGs up to the 60-year lifetime of the refurbished plant. The paper reviews an existing methodology based on the concept of the improvement factor, and refines its estimation based on data specific to CANDU operating conditions. The paper presents a more advanced Bayesian probabilistic approach to estimate the degradation free lifetime distribution of Alloy 800 tubing, which is used to quantify the probability of degradation during the service life and to evaluate the impact of potential occurrences of ...

2009-10-15

44

The estimation of lifetime distribution of Alloy 800 steam generator tubing  

International Nuclear Information System (INIS)

Alloy 800 has been used for steam generator (SG) tubing for more than 30 years, primarily in CANDU reactors worldwide and in reactors in Germany. Extensive laboratory testing and in-service experience suggest that the Alloy 800 tubing has excellent resistance to corrosion-related degradation under appropriate operating conditions. In planning refurbishment of nuclear plants stations, a key concern is the longevity of existing SGs up to the 60-year lifetime of the refurbished plant. The paper reviews an existing methodology based on the concept of the improvement factor, and refines its estimation based on data specific to CANDU operating conditions. The paper presents a more advanced Bayesian probabilistic approach to estimate the degradation free lifetime distribution of Alloy 800 tubing, which is used to quantify the probability of degradation during the service life and to evaluate the impact of potential occurrences of ...

2009-10-01

45

Development of barcode system for internal dose monitoring  

International Nuclear Information System (INIS)

In Tarapur Atomic Power Station unit-3 and 4, which is 540 MWe pressurized heavy water reactor, tritium is produced in primary heat transport system and moderator system. Tritium is a major contributor to the internal dose. Internal dose contributes about 30% of the collective dose. Internal dose monitoring and its control are important to control the collective dose. Estimation of internal dose is done by analysis of bioassay samples of radiation workers. In a month, about 7000 bioassay samples are analysed for the internal dose assessment during normal operation, and about 12000 during the biennial shut down of the reactor. To enhance the sample preparation and counting performance, minimize the entry errors and reduce the processing time, barcode based label generation system was developed for the internal dose monitoring. This paper discusses about the use of barcode system in the internal dose monitoring at TAPS 3 and ...

2008-11-19

46

A probabilistic approach to the estimation of lifetime distribution of Alloy 800 SG tubing  

Energy Technology Data Exchange (ETDEWEB)

Alloy 800 has been used for steam generator (SG) tubing for more than 30 years, primarily in CANDU reactors and in reactors in Germany. Extensive laboratory testing and in-service experience suggest that the Alloy 800 tubing has excellent resistance to corrosion-related degradation under specified and appropriate operating conditions. In planning refurbishment of CANDU stations, a key concern is the longevity of existing SGs up to the 60 year lifetime of the refurbished plant. The paper reviews an existing methodology based on the concept of the improvement factor, and estimates it based on experimental data specific to CANDU operating conditions. The paper presents a more advanced probabilistic approach to estimate the degradation free lifetime distribution of Alloy 800 tubing, which is used to quantify the probability of degradation during the service life and to evaluate the impact of potential occurrences of degradation ...

2008-07-01

47

A probabilistic approach to the estimation of lifetime distribution of Alloy 800 SG tubing  

International Nuclear Information System (INIS)

Alloy 800 has been used for steam generator (SG) tubing for more than 30 years, primarily in CANDU reactors and in reactors in Germany. Extensive laboratory testing and in-service experience suggest that the Alloy 800 tubing has excellent resistance to corrosion-related degradation under specified and appropriate operating conditions. In planning refurbishment of CANDU stations, a key concern is the longevity of existing SGs up to the 60 year lifetime of the refurbished plant. The paper reviews an existing methodology based on the concept of the improvement factor, and estimates it based on experimental data specific to CANDU operating conditions. The paper presents a more advanced probabilistic approach to estimate the degradation free lifetime distribution of Alloy 800 tubing, which is used to quantify the probability of degradation during the service life and to evaluate the impact of potential occurrences of degradation ...

2008-06-01

48

MINIMARS: An attractive small tandem mirror fusion reactor  

International Nuclear Information System (INIS)

Through the innovative design of a novel end plug scheme employing octopole MHD stabilization, the authors present the conceptual design of ''MINIMARS'', a small commercial fusion reactor based on the tandem mirror principle. The current baseline for MINIMARS has a net electric output of 600 MWe and they have configured the design for short construction times, factory-built modules, inherently safe blanket systems, and multiplexing in station sizes of #approx =# 600-2400 MWe. They demonstrate that the compact octopole end cell provides a number of advantages over the more conventional quadrupole (yin-yang) end cell encountered in the MARS tandem mirror reactor study, and enables ignition to be achieved with much shorter central cell lengths. Accordingly, being economic in small sizes, MINIMARS provides an attractive alternative to the more conventional larger conceptual fusion reactors encountered to ...

49

Advanced Neutron Source: Plant Design Requirements. Revision 4  

Energy Technology Data Exchange (ETDEWEB)

The Advanced Neutron Source will be a new world-class facility for research using hot, thermal, cold, and ultra-cold neutrons. The heart of the facility will be a 330-MW (fission), heavy-water cooled and heavy-water moderated reactor. The reactor will be housed in a central reactor building, with supporting equipment located in an adjoining reactor support building. An array of cold neutron guides will fan out into a large guide hall, housing about 30 neutron research stations. Appropriate office, laboratory, and shop facilities will be included to provide a complete facility for users. The ANS is scheduled to begin operation at the Oak Ridge National Laboratory early in the next decade. This PDR document defines the plant-level requirements for the design, construction, and operation of ANS. It also defines and provides input to the individual System Design Description (SDD) ...

1990-07-01

50

Study of radionuclide contributing to dose rates in 540 MWe plant environment  

International Nuclear Information System (INIS)

Tarapur Atomic Power Station Unit-4 is first 540 MWe pressurized heavy water reactor in India. It achieved criticality on 06th March 2005 and then operated at full power i.e 500 MWe. Radiation workers during the normal operation and reactor shutdown are exposed to radiation field. The control of dose rates and the collective dose of the radiation workers is most important for the best performance of the reactor. Experience gained during the operation of the 220 MWe reactors has shown that the Moderator system, primary heat transport system, annulus gas system and moderator cover gas system are the main systems contributing to the dose rate and collective dose. In order to identify the radio nuclides contributing to the radiation field, study was undertaken at TAPS Unit-4. Various samples from the Moderator, primary heat transport system, annulus gas system and moderator cover gas ...

2005-11-23

51

Radiological safety aspects associated with the handling, storage and disposal of self power neutron detectors in TAPS - 3 and 4  

International Nuclear Information System (INIS)

At Tarapur Atomic Power Station 3 and 4, 540 MWe Pressurised Heavy Water Reactors, core being large in size requires a continuous in core monitoring for local flux disturbances. Nearly 200 Self Powered Neutron Detectors (SPNDs) of the Straight Individually Replaceable (SIR) type are distributed in the reactor core. For purpose of reactor regulation and protection, cobalt SPNDs that have a prompt response for changes in power is used for in-core flux mapping, vanadium SPNDs that provide accurate measure of neutron flux, even though having slow response is used In core SPNDs are placed in Vertical Flux Units (VFU) and Horizontal Flux Units (HFUs). These SPNDs were to be replaced at regular intervals to meet the design intent. Cobalt SPNDs have dose rates of the order of 1000 Gy/h and the Mineral Insulated (MI) cables of Vanadium SPNDs have dose rates of the order of 100 Gy/h. So far 3 Cobalt SPNDs were ...

2006-11-13

52

Kinetic aspects of the photolysis of in-station airborne methyl iodide  

International Nuclear Information System (INIS)

A method for converting organic iodides to elemental iodine would be advantageous in improving the performance of charcoal filters for the removal of radio iodines from reactor off gases. A photochemical method has been developed. The HAVCHM code was used to establish the relevant process time scales on a complete set of rate equations describing the primary and secondary reactions occurring in a plug-flow reactor containing low levels of elemental iodine and methyl iodide in air, which is irradiated by intense u.v. light. These simulations were used to justify the contraction of the complete set of reactions to the most significant elementary processes. The contracted set of rate equations are then solved analytically to render the concentration-time profiles of methyl iodide, total inorganic iodine and total oxidized organics, consistent with the achievement of a desirable radioiodine decontamination factor. For the short contact times ...

53

Applicability of leak-before-break criteria  

Energy Technology Data Exchange (ETDEWEB)

On February 1, 1984, the US Nuclear Regulatory Commission issued Generic Letter 84-04 on the subject of postulated pipe breaks in pressurized water reactor (PWR) primary coolant loops, opening the way for pipe-whip restraint exemptions. The letter substitutes the leak-before-break (LBB) criteria for the double-ended guillotine break regarding PWR primary reactor coolant system (RCS) piping and asymmetric blowdown loads. The LBB criterion refers to the fact that a piping flaw will leak before it breaks. The current requirement to provide pipe-whip restraints is applied within the plant to all high-energy piping with a potential for damaging structures, systems, and components essential to safe reactor shutdown. This includes primary RCS piping 30 in. and larger as well as smaller piping systems. A study was performed to evaluate the applicability of the LBB criteria proposed in NUREG-1061 to the latter set. The costs and ...

1986-01-01

54

TEENET Cleaner Production Databases  

Wastenet

...of stations and a number of components, and meta information on air quality monitoring networks and stations. Access the database Producer Europe Environment Agency Content ...of stations and a number of components, and meta information on air quality monitoring networks and stations. Coverage National (Europe) Number of records...

56

Thermal analysis of spent fuel in shuttle station during dry transfer under abnormal cooling conditions for TAPS - 4  

International Nuclear Information System (INIS)

A pair of bundles is placed in a shuttle tube, which is enclosed by a carriage tube kept inside the Shuttle Transfer Station (STS). It takes about 90 minutes for the spent fuel bundles to travel from the reactor channel to Transfer Magazine (TM). Subsequently, the dry transfer operation takes about 4 minutes. An emergency air cooling flow rate of 600 m3/hr is supplied to cool the spent fuel bundles after they reach the STS, following lapse of 4 minutes of spent fuel dry transfer, in case the bundles are not submerged in the light water in STS. A thermal and hydraulic safety analysis has been done to estimate the maximum sheath temperature, if the spent fuel bundles are stuck at a location of 30 mm below the normal location aligned to the TM port. This position of the spent fuel will have least cooling from the emergency cooling airflow. At the same time, the shuttle tube carrying the spent fuel bundle is just above the water. From the analysis ...

2006-11-13

57

Leak-before-break strategy for CANDU primary piping systems  

Energy Technology Data Exchange (ETDEWEB)

Recent advances in elastic-plastic fracture mechanics have made it possible to assess the stability of cracks in ductile piping systems. These technological developments have been used by Ontario Hydro as the nucleus of an approach for demonstrating that CANDU primary heat transport piping systems will not break catastrophically; at worst they would leak at a detectable rate. This leak-before-break approach has been taken on the Darlington nuclear generating station as a design stage alternative to the provision of pipe whip restraints on large diameter, primary heat transport system piping. Positive conclusions reached via this approach are considered sufficient to exclude the requirement to provide protective devices, such as pipe whip restraints. In arriving at the proposed leak-before-break approach a review of current and proposed leak-before-break licensing positions of other jurisdictions (particularly those in the United States and the Federal Republic of ...

1986-01-01

58

Electrical grid stability and its impact on nuclear power generating stations  

Energy Technology Data Exchange (ETDEWEB)

Electrical power is generated by steam turbines (steam being produced by coal, oil, gas or nuclear reactors), hydro units, gas turbines, internal combustion engines, jet engines, and pumped storage plants. Nuclear Power Plants generate only 15% of the total electrical power in the US. Nuclear Power Plants being cheaper to run are generally base loaded. The pumped-storage and gas turbine plants have ideal characteristics for peaking duty. In the pumping mode, pumped storage plants are used to provide additional system load and in the generating mode, they supply reactive power during peak load demands. Gas turbine plants have higher running costs, but are used as peaking units with a fast start capability. Fossil power plants need a minimum of 1 hour to stabilize expansion in the boiler and turbine generator. Due to a more competitive power supply market due to deregulation, most of the utilizes plan generation only for the next three years. This paper discusses the ...

1997-12-31

59

Analysis of dose rate build-up in Tarapur Atomic Power Station unit-4  

International Nuclear Information System (INIS)

Tarapur Atomic Power Station Unit-4 was made critical on 6th March 2005. Since radiation field builds up with the power level due to formation of fission products and activation products in different systems. Radiation dose rates were recorded from different areas using Area Radiation Monitors (ARMs) installed at different areas. These monitors are connected to Radiation Data Acquisition System (RADAS). The trend of radiation field build-up was also analyzed by making survey of different plant areas at various power levels and comparison was made with RADAS readings. The results obtained were compared with 220 MWe dose rates. This study discusses about the dose rates observed at accessible area, shut down accessible area and hotspots observed during the early stage of operation of the reactor. The attempt was also made to find the contributing factors of the high dose rates. It was found that the finding of the study was utilized for the ...

2005-11-23

60

Station Crew Wishes Buzz Aldrin Luck On 'Dancing'  

National Aeronautics and Space Administration (NASA)

International Space Station astronauts Jeff Williams and T.J. Creamer wish Buzz Aldrin luck on

2010-03-17

61

Analysis of log rate noise in Ontario's CANDU reactors  

Energy Technology Data Exchange (ETDEWEB)

In the fall of 2003, the operators noticed that in the recently-refurbished Bruce A Shutdown System no. 1 (SDS1) the noise level in Log Rate signals were much larger than before. At the request of the Canadian Nuclear Safety Commission (CNSC), all Canadian CANDU reactors took action to characterize their Log Rate noise. Staff of the Inspection and Maintenance Services division of Ontario Power Generation (OPG) has collected high-speed high-accuracy noise data from nearly all 16 Ontario reactors, either as part of routine measurements before planned outages or as a dedicated noise recording. This paper gives the results of examining a suitable subset of this data, with respect to the characteristics and possible causes of Log Rate noise. The reactor and instrumentation design is different at each station: the locations of the moderator injection nozzles, the location of the ion chambers for each system, ...

2007-07-01

62

Updating of the program for simulation of Darlington shutdown and regulation systems. Research report No. INFO-0309  

Energy Technology Data Exchange (ETDEWEB)

Description of the current status of the developments of a simulation of the Darlington Nuclear Generating Station shutdown and regulating systems, DARSIM. The DARSIM program simulates the spatial neutron dynamics, the regulations of the reactor power, and shutdown system 1 and shutdown system 2 software. The DARSIM program operates in the interactive simulation (INSIM) program environment. DARSIM was installed on the APOLLO computer at the Atomic Energy Control Board (AECB) and a version for an IBM-PC was also provided for the exclusive use of the AECB. Shutdown system software was updated to incorporate the latest revisions in the functional specifications. Additional developments were provided to assist in the use and interpretation of the DARSIM results.

1988-01-01

63

Pre-test report on international round robin analysis of BARC containment (BARCOM) test model  

International Nuclear Information System (INIS)

BARC has organized an international round robin analysis program to carry out the ultimate load capacity assessment of BARC containment (BARCOM) test model. The test model located in BARC facilities Tarapur, is a 1:4 scale representation of 540 MWe pressurized heavy water reactor (PHWR) pre-stressed concrete inner containment structure of Tarapur Atomic Power Station (TAPS) unit 3 and 4. The features of the BARCOM test model and the constitutive data for the pre-test analysis along with the comparison of the results submitted by various participants are described in this pre-test report of the round robin analysis of BARCOM test model

2009-01-01

64

Estimating pressurized water reactor decommissioning costs: A user`s manual for the PWR Cost Estimating Computer Program (CECP) software. Draft report for comment  

Energy Technology Data Exchange (ETDEWEB)

With the issuance of the Decommissioning Rule (July 27, 1988), nuclear power plant licensees are required to submit to the US Regulatory Commission (NRC) for review, decommissioning plans and cost estimates. This user`s manual and the accompanying Cost Estimating Computer Program (CECP) software provide a cost-calculating methodology to the NRC staff that will assist them in assessing the adequacy of the licensee submittals. The CECP, designed to be used on a personnel computer, provides estimates for the cost of decommissioning PWR plant stations to the point of license termination. Such cost estimates include component, piping, and equipment removal costs; packaging costs; decontamination costs; transportation costs; burial costs; and manpower costs. In addition to costs, the CECP also calculates burial volumes, person-hours, crew-hours, and exposure person-hours associated with decommissioning.

1993-10-01

65

Advanced resin cleaning system  

International Nuclear Information System (INIS)

Novel and unprecedented ion exchange resin cleaning system, for use in BWR plants and featuring a vibration separator and basic design factors of Radiological Solutions, Inc., had been delivered to Tokai No. 2 Power Station, Japan Atomic Power Company, in October 2005. This compactly-designed system effectively separates crud and resin fines from ion exchange resins, with no clogging of separation screens. It generates minimized waste liquid and has a specially designed over-pack cleaning tank. The system has been in operation for about 2 years and half now and favorable operational data, such as crud and sulfate concentration decrease in feed water and reactor water respectively, and evaluation results have been reported from Japan Atomic Power Company and so on. (author)

2008-07-01

66

Wolsung-1 NPP - electrictal systems  

International Nuclear Information System (INIS)

... power reactors pressure tube reactors reactors THERMAL REACTORS.

1980-06-18

67

Omega process for the use of substitute fuels; Waste energy: Omega-Verfahren zur Verwertung von Ersatzbrennstoffen  

Energy Technology Data Exchange (ETDEWEB)

Only about 25% of residue accumulating in the Federal Republic of Germany is currently used for the purposes of energy. This residue will be converted into fuel for power stations by the Omega process when the dumping of waste with a calorific value in excess of 5 MJ/kg is prohibited with effect from 2005. This oxygen melting process is suitable for the local use of substitute fuels. Waste is converted into a high-quality synthesis gas with a wide range of uses. The Omega process combines drying, thermal decomposition, gasification and melting of the material used in a single-stage process. This is now technologically possible for the first time by combining a metallurgical cupola furnace with a traditional gas producer. The highly-calorific synthesis gas produced by the Omega process can be used in block heat and power stations or as an industrial fuel gas, instead of natural gas. It is also suitable as a starting material for synthesising ...

2003-03-01

68

Long-term optimization of fuel loading pattern using genetic algorithms and simulated annealing  

International Nuclear Information System (INIS)

This paper describes Automatic Refueling Planning System (ARPS) for a nuclear power station using Genetic Algorithms (GA) and a Simulated Annealing (SA). ARPS has been developed and verified by applying to the Fugen nuclear power station (NPS), which is a 165MWe, heavy water-moderated, boiling light water-cooled, pressure tube-type reactor developed by JNC utilizing mainly uranium and plutonium mixed oxide (MOX) fuel. Fuel loading patterns have been managed independently in the Fugen NPS since the initial core. A planning of an adequate fuel loading pattern on each operational cycle needs one to two months even for expert core management engineers, for the reason that it has multi-objective optimization and nonlinear problems. In order to achieve the optimum fuel loading pattern and a fuel cost reduction, ARPS has been developed by JNC and CRC Solutions Corporation for the last five years. ARPS firstly generates several ...

2003-04-20

69

Experience in complying with quality assurance requirements for cask lifting devices  

International Nuclear Information System (INIS)

The Nuclear Assurance Corporation (NAC) owns and operates four NAC-1 truck casks. These casks are used to ship spent reactor fuel assemblies and radioactive reactor-core components. The casks have been loaded or unloaded at a total of fifteen nuclear facilities in the United States. In addition, NAC has used another large, overweight-truck cask to ship radioactive reactor core components from a reactor to a waste burial site. There are many individual differences in the cask handling facilities at each of the reactor stations, nuclear research facilities and the storage and burial sites serviced. Various types of auxiliary lifting and handling devices for on-site cask operations have been required. The quality assurance requirements for the equipment used in interfacing casks with nuclear power plant facilities have become more stringent. This paper presents ...

71

Integrity assessment of 37 element fuel bundle of TAPS 3 and 4 reactor under beyond design basis accident condition  

International Nuclear Information System (INIS)

Tarapur Atomic Power Station 3 and 4 is a 540 MWe Pressurized Heavy Water Reactor. It uses 37 - element natural Uranium dioxide (UO_2) fuel pellets encapsulated inside the cylindrical sheath and are welded to the end plate at each end. During an postulated accident in which part of the fuel bundle are exposed to very high temperature (no means of heat removal) and other are at lower temperature (coolant temperature) possibility of failure of end plate weld due of thermal stresses developed by these relative temperature cannot be ruled out. In this report an attempt is made to study behaviour of fuel bundle under different temperature loading. Modelling of 37 element fuel bundle was done in ANSYS FEM. System was analysed for various sets of temperature loading. The system was analysed for plasticity and creep as material nonlinearity. The total strain, creep strain and stress increase as the temperature increases in upper portion of fuel bundle ...

2005-12-01

72

An overview of AECL's participation in the Korean Wolsung Tritium Removal Facility Project (WTRF)  

International Nuclear Information System (INIS)

Full text: In heavy-water-moderated power reactors, tritium is primarily produced by neutron capture in deuterium nuclei in the moderator and coolant. For CANDU 6 reactors, the estimated steady-state values are #approx# 3 TBq#centre dot#kg"-"1 D_2O in the moderator and #approx# 74 GBq#centre dot#kg"-"1 D_2O in the coolant. Tritium removal is one option available to reactor operators for use in their heavy water and tritium management strategies. The WTRF is designed to remove tritium from tritiated heavy water in each of the four CANDU units at the Wolsung Site, to immobilize the tritium and to store it on site. The detritiation process is based on three steps: the first one (front-end) involves the transfer of tritium from heavy water to deuterium gas; the second one (enrichment) concentrates the tritium in a cryogenic distillation system to produce essentially pure D_2 and T_2 streams; and in the third step the tritium is ...

2007-11-07

73

central sports - NASA  

Science.gov (United States)

11 matches ... 04.17.2002. International Space Station Sports a New Truss + More Details. 04.17 .2002. International Space Station Sports a New Truss ...

74

Target stations and beam dumps for the CERN SPS  

International Nuclear Information System (INIS)

The design of the absorber blocks for internal and external dumping of the SPS proton beam is discussed. In addition, the external target stations for slow and fast extracted proton beams are described.

1977-03-16

75

Robonaut 2 Makes First Motions on Station  

National Aeronautics and Space Administration (NASA)

Robonaut 2 goes through a series of tests aboard the International Space Station, including its first motions on the orbital outpost. n

2011-10-14

76

Previous - Global Change Master Directory (GCMD)  

Science.gov (United States)

The automatic weather stations at the Australian stations (Casey, Davis, ... This metadata record describes Simone Ingham's survey of vegetation sampling ...

77

Monthly electricity usage at Australian Antarctic Stations - NASA  

Science.gov (United States)

Record Search Query: Science Keywords>HUMAN DIMENSIONS>INFRASTRUCTURE> ELECTRICITY. Monthly electricity usage at Australian Antarctic Stations ...

78

Deep subsurface structure modeling based on microtremor and earthquake observation. Applicability of microtremor array measurements at the Kashiwazaki-Kariwa Nuclear Power Station  

International Nuclear Information System (INIS)

During the 2007 Niigataken Chuetsu-oki earthquake, strong ground motion with the peak acceleration of 680 cm/s/s which was larger than that of the empirical prediction was recorded at the base mat of the No.1 reactor building of Kashiwazaki-Kariwa Nuclear Power Station (NPS). Furthermore, in the Kashiwazaki-Kariwa NPS, over twice difference of 680 vs. 322 cm/s/s of peak acceleration between the No.1 and the No.6 reactor buildings was observed on the base mat. From the results of recent research, it is suggested that the deep sedimentary layers can be one of the important factors to elucidate these phenomena. In this study, at first, the applicability of microtremor array measurements for estimation of deep S-wave velocity structure (#approx#Vs=3 km/s layer) are discussed. Vertical microtremors were observed in three arrays at the Kashiwazaki-Kariwa NPS with the maximum station spacings of 3.04 km, 1.49 ...

2010-05-01

79

The Daya Bay reactor neutrino experiment  

CERN Document Server

The Daya Bay reactor neutrino experiment

2008-01-01

80

NASTRAN nonlinear dynamic transient accident analysis for FFTF reactor component  

International Nuclear Information System (INIS)

... computer calculations fftf reactor nonlinear problems reactor accidents reactor

1976-11-14

81

Fuel cycle of reactor SVBR-100  

International Nuclear Information System (INIS)

... fast reactors fbr type reactors fuels liquid metal cooled reactors materials nuclear

82

The development of ABWR  

International Nuclear Information System (INIS)

The first Advanced Boiling Water Reactor (ABWR) started commercial operation as Tokyo Electric Power Company's (TEPCO) Kashiwazaki-Kariwa Nuclear Power Station Unit No.6 (K-6) in November 1996 and its sister Unit No.7 (K-7) in July 1997. The ABWR was developed to achieve higher reliability and safety margin while improving overall operability and economics. To achieve these goals, the optimal Boiling Water Reactor (BWR) technologies had been studied, tested and were finally adopted into the ABWR design. These technologies were called 'First of a Kind' and include the Reactor Internal Pump (RIP), Fine Motion Control Rod Drive (FMCRD), Reinforced Concrete Containment Vessel (RCCV), and integrated digital Instrumentation and Control System (I and C). Intensive development study, confirmation tests and verification tests were conducted by the plant equipment suppliers, electric utilities, and government ...

1999-12-01

83

Study of the origin of elements of the uranium-235 family observed in excess in the vicinity of the experimental nuclear EL4 reactor under dismantling. Lessons got at this day and conclusions; Etude de l'origine des elements de la famille de l'uranium-235 observes en exces dans les environs du reacteur nucleaire experimental EL4 en cours de demantelement. Enseignements retires a ce jour et conclusion  

Energy Technology Data Exchange (ETDEWEB)

This study resumes the discovery of an excess of actinium 227 found around by EL4 nuclear reactor actually in dismantling. The search for the origin of this excess revealed a real inquiry of investigation during three years. Because a nuclear reactor existed in this area a particular attention will have concerned this region. The doubt became the line of conduct to find the answer to the human or natural origin of this excess. Finally and against any evidence, it appears that the origin of this phenomenon was natural, consequence of the particular local geology. The detail of the different investigations is given: search of a possible correlation with the composition of elevations constituent of lanes, search (and underlining) of new sites in the surroundings of the Rusquec pond and the Plouenez station, study of the atmospheric deposits under winds of the nuclear power plant and in the east direction, search of a possible ...

2007-07-01

84

Experience with the austenite materials 1.4541 and 1.4550 in German boiling water reactors; Erfahrungen mit den austenitischen Werkstoffen 1.4541 und 1.4550 in deutschen Siedewasserreaktoren  

Energy Technology Data Exchange (ETDEWEB)

Stabilized austenitic steels can suffer intercrystalline stress corrosion cracking under BWR water conditions. This experience of the last three years, which is important for German nuclear power station technology, has resulted from the discovery of cracks, which were detected in pipework made from titanium-stabilized 1.4541 charged with hot reactor water in six boiling water reactors and in core components made from niobium-stabilized 1.4550 of one BWR plant. Remedies to the pipework have been found by applying optimized materials and fabrication procedures and also by improving water chemistry conditions. (orig.) [Deutsch] Stabilisierte austenitische Staehle koennen unter SWR-Reaktorwasser-Bedingungen interkristalline Spannungsrisskorrosion (IKSpRK) erleiden. Diese fuer die deutsche Kernkraftwerkstechnik bedeutsame Erfahrung der letzten drei Jahre ergab sich aus Rissbefunden, die in mit heissem Reaktorwasser ...

1996-10-01

85

Environmental mitigation for SCC initiation of BWR core internals by hydrogen injection during start-up  

Energy Technology Data Exchange (ETDEWEB)

Hydrogen injection into the reactor water has been applied to many BWR power stations. Since hydrogen injected accelerates recombination of oxidant generated by water radiolysis, oxidant concentration, such as dissolved oxygen concentration in reactor water can be reduced. As the result of the reduction of oxidant concentration, Electrochemical Corrosion Potential (ECP) at the surface of structural material can be lowered. Lowered ECP moderates Stress Corrosion Cracking (SCC) sensitivity of structural materials, such as stainless steels. As usual, hydrogen injection system begins to work after the plant start-up is finished, when the condition of normal operation is established. Accordingly, Hydrogen Water Chemistry (HWC) does not cover all the period of plant operation. As far as SCC crack growth is considered, loss of HWC during plant start-up does not result in significant crack growth, because of duration of plant ...

2004-07-01

86

Enhancement of efficacy of process water monitors in detecting heavy water leak in steam generator blow down lines  

International Nuclear Information System (INIS)

The Steam Generator (SG) serves as an interface between primary and secondary cycle in Pressurized Heavy Water Reactor (PHWR). Failure of steam generator tubes result in leaking of active heavy water in the secondary closed loop. In Tarapur Atomic Power Station-3 and 4 (TAPS- 3 and 4), Scintillator detectors are provided to detect on line heavy water leakages in SG and moderator heat exchangers by monitoring Nitrogen-16 (16N) and Oxygen-19 (19O) activities. Efficacy of detection of these activities at designed detector position on SG blow down line in presence of background radiation field is analysed theoretically. The count rate of 19O and 16N estimated at the detector position inside Reactor Building (RB) shows that detectors only respond to very high leak rates due to presence of high ambient radiation level even though sensitivity is appreciably good. For detector position in RB in the accessible areas and out side the ...

2006-11-13

87

Analysis of efficacy of process water monitors in detecting heavy water leak in steam generator blow down lines  

International Nuclear Information System (INIS)

The Steam Generator (SG) serves as an interface between primary and secondary cycle in Pressurized Heavy Water Reactor (PHWR). Failure of steam generator tubes result in leaking of active heavy water in the secondary closed loop. In Tarapur Atomic Power Station-3 and 4 (TAPS- 3 and 4), Scintillator detectors are provided to detect on line heavy water leakages in SG and moderator heat exchangers by monitoring Nitrogen-16 ("1"6N) and Oxygen-19 ("1"90) activities. Efficacy of detection of these activities at designed detector position on SG blow down line in presence of background radiation field is analysed theoretically. The count rate of "1"9O and "1"6N estimated at the detector position inside Reactor Building (RB) shows that detectors only respond to very high leak rates due to presence of high background even though sensitivity is appreciably good. For detector position out side the RB containment, the travel time for ...

2005-11-23

89

The characteristic and relevant fault analysis for the microgovernor synchronization of Daya Bay Nuclear Power Station and Ling'ao Nuclear Power Station  

International Nuclear Information System (INIS)

In Daya Bay and Ling'ao Nuclear Power Station, the Microgovernor has the control functions such as synchronization, block loading etc. The control principle of the Microgovernor is right described by sequence diagram for the first time. That the fault occurred in the synchronization process of Daya Bay Nuclear Power Station unit 1 is also analyzed and illustrated. (author)

2005-09-01

91

ISS Update - Oct. 19, 2011  

National Aeronautics and Space Administration (NASA)

The International Space Station video update for Oct. 19, 2011.

2011-10-19

92

ISS Update - Oct. 18, 2011  

National Aeronautics and Space Administration (NASA)

The International Space Station video update for Oct. 18, 2011.

2011-10-18

93

ISS Update - Oct. 17, 2011  

National Aeronautics and Space Administration (NASA)

The International Space Station video update for Oct. 17, 2011.

2011-10-17

94

ISS Update - Oct. 14, 2011  

National Aeronautics and Space Administration (NASA)

The International Space Station video update for Oct. 14, 2011.

2011-10-14

95

ISS Update - Oct. 13, 2011  

National Aeronautics and Space Administration (NASA)

The International Space Station video update for Oct. 13, 2011. n

2011-10-13

100

From Daya Bay to Ling Ao. The benefits of a duplication policy  

International Nuclear Information System (INIS)

Over the past 15 years, the People's Republic of China has experienced very rapid economic growth of annual average 8%, which must be supported by fast expanding energy production, notably of electricity. China has the considerable amount of coal resources, but most of these resources are located in the north of the country, and the vast hydroelectric potential in Southwestern China is difficult to develop. Therefore, in the coastal provinces of Southeast China, where economic expansion is greatest, nuclear power has been chosen to meet the need. The Qinshan No. 1 PWR with 300 MWe output is the first Chinese nuclear power facility, and started the operation in 1992. Two 985 MWe PWRs have been operated since 1994 at Daya Bay. The construction of Qinshan No. 2 and 3 PWRs of 600 MWe each are in progress, and are expected to start the operation in 2001. These plants were designed by China based on the Framatome technology. Two more 985 MWe plants will be constructed on Ling Ao site, and ...

1996-10-01

101

Probabilistic safety analysis of transportation of spent fuel  

International Nuclear Information System (INIS)

The report presents the results of the study carried out to estimate the accident risk involved in the transport of spent fuel from Rajasthan Atomic Power Station near Kota to the fuel reprocessing plant at Tarapur. The technique of probabilistic safety analysis is used. The fuel considered is the Indian pressurised heavy water reactor fuel with a minimum cooling period of 485 days. The spent fuel is transported in a cuboidal, naturally-cooled shipping cask over a distance of 822 km by rail. The Indian rail accident statistics are used to estimate the basic rail accident frequency. The possible ways in which a release of radioactive material can occur from the spent fuel cask are identified by the fault tree analysis technique. The release sequences identified are classified into eight accident severity categories, and release fractions are assigned to each. The consequences resulting from the release are estimated by the computer code RADTRAN ...

1977-09-05

102

Individual monitoring of internal exposure to uranium oxides in two fuel fabrication plants. La surveillance individuelle de l'exposition interne aux oxydes d'uranium dans deux usines de fabrication du combustible  

Energy Technology Data Exchange (ETDEWEB)

Individual monitoring of personal exposure to inhalation of uranium oxides throughout the manufacture of fuel for pressurized water reactor (PWR) includes lung gamma-spectrometry, fecal analysis and urine analysis. Examination of the results shows the following: internal exposure is the consequence of repeated intake incidents as revealed by early peaks of urinary and particularly fecal elimination; a shift is often observed with the results of aerosol concentration measured through air collectors; the measured variations of uranium lung incorporations are relatively fast (apparent mean period 165 d). Correct evaluation of the effective dose equivalent from inhalation requires further information concerning the aerosol size distribution at work stations, the physico-chemical characteristics of the product leading to an estimate of its actual biological solubility, and the measurement of the fraction of aerosol liable to intake with an ...

1989-01-01

103

Hardware-oriented reliability centered maintenance for the diesel generators of Wolsung unit 1  

Energy Technology Data Exchange (ETDEWEB)

The DGs (Diesel Generators) in NPP (Nuclear Power Plant) has been used for the emergency electric power source to shot down the nuclear reactor safety in case of station blackout. The RCM (Reliability Centered Maintenance) has been applied to DGs for increasing the safety of NPP. The structured defects of DG were not remedied by the improvement of maintenance method. As the first stage of RCM, to find the structured defect, its failure= models were searched and analyzed through the ten year maintenance information. The structured defects such as the air compressor, the lubricating oil pressure, and the insufficient load were the root causes of main failures. The air reservoir reinstallation, the lubricating oil tube modification, the load bank installation, and the qualitative instrumentation were the solutions for the hardware oriented RCM of DGs. There remains the software oriented RCM such as the rejection of useless maintenance, the ...

1997-05-01

104

Experiences with applications of PSA results for optimization/revision of technical specifications for operation of nuclear power plants  

International Nuclear Information System (INIS)

Over the past few years, NPCIL has performed comprehensive Level-1 Probabilistic Safety Assessment (PSA) for a 220 MWe Pressurised Heavy Water Reactor (PHWR) at Kakrapar Atomic Power Station (KAPS) and for the first 540 MWe PHWR at Tarapur Atomic Power Project (TAPP- 3 and 4). The major objective of these PSAs was to present an integrated picture of the safety of the plant to identify and understand key plant vulnerabilities. As a result of the availability of these PSAs, there is a desire to use them to operate the plants in the most efficient manner practicable. In recent years, the operation of Indian Nuclear Power Plants has been characterized by improved availability/capacity factors and reduced forced outages. Frequency of planned outages is also being reduced. In order to achieve this, the PSAs are now being used as an engineering tool for optimization of Technical Specifications with regard to Allowed Outage Time (AOT) and Surveillance ...

2005-12-01

105

Annual report 2005-2006  

International Nuclear Information System (INIS)

Research and development and other activities of the various constituent units of Department of Atomic Energy (DAE) and also of the institution aided by DAE for the year 2005-2006 are reported. The various constituents units of DAE consist of nuclear research centres, nuclear power stations, fuel reprocessing and heavy water plants, nuclear fuel fabrication facilities, electronic and instrumentation production organisations, atomic mineral processing units and other nuclear installations. The activities of DAE cover the whole gamut of nuclear fuel cycle, research and development in nuclear science and reactor technology, applications of radiation and radioisotopes, radiation protection, research and development in front line areas such as robotics, lasers, mathematics and computational sciences. International research collaborations like CERN-DAE collaboration were completed by BARC. These activities are described broadly under: executive ...

106

Multivariate statistics in the identification of unknown nuclear material  

International Nuclear Information System (INIS)

The identification, and hence origin determination, of unknown nuclear material that might be found undeclared away from designated locations in the nuclear fuel cycle, is an important task in the frame of nuclear forensics. Material with forensic importance can be found at the microscopic level as particles in environmental samples indicating possible clandestine production of fissile material, and as bulky samples in the case of illicit trafficking of nuclear material. The objective of this work is to present, at a theoretical level, an isotopic finger-printing methodology which would determine the origin of unknown nuclear material with forensic importance. This is demonstrated for the case when the unknown nuclear material is spent nuclear fuel. The methodology is based on multivariate statistics, such as cluster and factor analysis, complemented by spent fuel isotopic composition simulations using the zero-dimensional depletion computer code ORIGEN2. A major source of error in the ...

2004-10-25

107

Water resources data for Texas, water year 1993. Volume 3. Colorado River basin, Lavaca River basin, Guadalupe River basin, Nueces River basin, Rio Grande basin, and intervening coastal basins. Water-data report (Annual), 1 October 1992-30 September 1993  

Energy Technology Data Exchange (ETDEWEB)

Water-resources data for the 1993 water year for Texas are presented in four volumes, and consist of records of stage, discharge, and water quality of streams and canals; and stage, contents, and water quality of lakes and reservoirs; and water levels and water quality of ground-water wells. Volume 3 contains records for water discharge at 134 gaging stations; stage only at 1 gaging stations; stage and contents at 13 lakes and reservoirs; water quality at 81 gaging stations; and data for 30 partial-record and 4 flood-hydrograph partial-record stations. Also included are lists of discontinued surface-water discharge or stage-only stations and discontinued surface-water-quality stations; crest-stage and flood-hydrograph partial-record stations, reconnaissance partial-record stations, and low-flow partial-record ...

1994-03-01

108

Identification of water quality and benthos characteristics in Daya Bay, China, from 2001 to 2004  

British Library Electronic Table of Contents (United Kingdom)

Physicochemical and benthos data were collected from 12 marine monitoring stations in Daya Bay, during 2001-2004. 12 stations in Daya Bay could be grouped into three clusters: cluster I consisted of stations in the southern part of Daya Bay (stations S1, S2 and S6); cluster II consisted of stations in the cage culture areas (stations S3, S4, S5 and S8); cluster III consisted of stations in the southwest, the middle and the northeast of the Bay (stations S7, S9, S10, S11 and S12). Calculation with bivariate correlations between benthos and major physicochemical factors showed that the density of benthos in all stations correlated positively with temperature, DO, pH, NH4-N, SiO3-Si, SiO3-Si /PO4-P and chlorophyll a and was negatively correlated with salinity, Secchi, COD, NO3-N, NO2-N, TIN, ...

2011-01-01

109

Significant Treatment: An Assessment of Issues-Programs List Availability in Missouri Radio Station Public Inspection Files  

British Library Electronic Table of Contents (United Kingdom)

Over the past three decades, rising competition from television and other new media prompted the FCC to ease the responsibilities of radio stations to maintain extensive records of issues programming, while retaining the responsibility of stations to provide ready public access to records. This study investigated the availability of Issues-Programs Lists in nearly 100 Missouri radio station Public Files. One in five randomly sampled stations failed to produce access to Lists upon demand as required under federal law. Noncompliance themes include: Inability to access Public Files within 20 minutes of face-to-face requests; station personnel with limited or no knowledge of Files; denial of access to Files and Lists (i.e., verbal refusals, locked studio doors); and incomplete Files. The rate ...

2007-01-01

110

Control Centre operations as the focus for building station teamwork - issues and resource impacts  

Energy Technology Data Exchange (ETDEWEB)

Effective teamwork among station work groups is essential for plant production and safety in all phases of plant operation. To achieve effective teamwork, all contributing work groups must have ongoing access to and share a common perspective on station work priorities, and recognize how their individual contributions fit with and support the contributions of other groups in support of the larger station goals. Achieving and maintaining this alignment in perspective across all workgroups can be a challenge in large organizations. This paper discusses the experience at Darlington in building and maintaining station teamwork among the station workgroups in support of day-to-day plant operations. The issues encountered and the resource impacts of specific teamwork supporting practices adopted are outlined. (author)

2006-07-01

111

Open test assembly (OTA) shear demonstration testing work/test plan  

Energy Technology Data Exchange (ETDEWEB)

This document describes the development testing phase associated with the OTA Shear activity and defines the controls to be in place throughout the testing. The purpose of the OTA Shear Program was to provide equipment that is needed for the processing of 40 foot long, sodium wetted, irradiated core components previously used in the FFTF reactor to monitor fuel and materials tests. There are currently 15 of these OTA test stalks located in the Test Assembly Conditioning Station (TACS) inerted vault. These need to be dispositioned for a shutdown mission to eliminate this highly activated, high dose inventory prior to turnover to the ERC since they must be handled by remote operations. These would also need to be dispositioned for a restart mission to free up the vault they currently reside in. The waste handling and cleaning equipment in the J33M Cell was designed and built for the handling of reactor components up to the ...

1998-07-16

112

A model for the calculation of vent clearing transients in pressure suppression systems  

International Nuclear Information System (INIS)

For the layout of a pressure suppression system of a light water cooled reactor (boiling water reactor) it is important to know the time dependent behavior of the vent clearing transient after a loss-of-coolant accident for two main reasons: time of the end of the vent clearing transient influences strongly the pressure and temperature maxima in the drywell and wetwell. Time-dependent behavior of the vent clearing transient influences pressure loads in the condensation pool of the wetwell and therefore pressure induced stresses to the structure. The time-dependent behavior of the water masses in the vent pipes and wetwell are described by the basic equations for a nonstationary incompressible friction flow: momentum equation, continuity equation and a correlation for the variation of the state of the gas volume in the wetwell above the water level. After many algebraic operations and integrations along the flow path, a single ordinary nonlinear ...

1975-09-01

113

Multiplication measurements for initial startup with the mockup core for the FFTF  

International Nuclear Information System (INIS)

... fftf reactor mockup multiplication factors reactivity worths reactor cores reactor

1974-10-27

114

Survey of Flue Gas Desulfurization Systems: Bruce Mansfield Station, Pennsylvania Power Co.  

Science.gov (United States)

This report gives the results of a survey of operational flue gas desulfurization (FGD) systems on coal-fired utility boilers in the United States. The FGD systems installed on Units 1 and 2 at the Bruce Mansfield Station of the Pennsylvania Power Company...

1979-01-01

115

Peter Frampton Talks to Station Crew  

National Aeronautics and Space Administration (NASA)

Rocker Peter Frampton and his band are introduced by astronaut Ron Garan to Commander Mike Fossum and Flight Engineers Satoshi Furukawa and Sergei Volkov aboard the International Space Station during a visit to Mission Control in Houston.

2011-10-17

116

Design and construction progress on Gentilly 2, Cordoba, Point Lepreau, and Wolsung projects  

International Nuclear Information System (INIS)

Gentilly 2, Point Lepreau, Cordoba and Wolsung are the first 600 MW CANDU nuclear generating stations to be built. Progress in their construction and in the remaining design work for these stations is discussed. (LL).

1980-06-18

117

Chalk Point Cooling Tower Project: Chalk Point Meteorological Station Report. Volume II.  

Science.gov (United States)

This report documents the operation, maintenance, calibration, data acquisition and data reduction at the Chalk Point Meteorological Station for the period November 15, 1978 through November 15, 1979. Climatological data summaries for each month and calib...

1979-01-01

118

Astronaut Jeff Williams Answers Your Questions  

National Aeronautics and Space Administration (NASA)

Expedition 22 Commander Jeff Williams, aboard the International Space Station 220 miles above Earth, responds to questions posted on YouTube concerning the station's orientation, life in space and the recent butterfly experiment.

2010-03-10

119

CORE OF FAST BREEDER REACTOR  

J-STORE (Japan)

Full Text Available

2006-06-02

120

Weekly ISS Recap - Oct. 10-14, 2011  

National Aeronautics and Space Administration (NASA)

The weekly International Space Station video recap for Oct. 10-14, 2011.

2011-10-14

125

Analysis and evaluation for little branch of Daya Bay Nuclear Power Station based on vibration test result  

International Nuclear Information System (INIS)

During the operation of Daya Bay Nuclear Power Station, some little branches of secondary system were with great vibration and even some of them cracked due to the great vibration that may cause some effect on the safety of the power station. This paper performed analysis and evaluation to the eight systems of Daya Bay Nuclear Power Station based on the vibration test results from the examination of the safety during ten years, and the list of the sensitive piping and suggestion for modification were presented based on the analysis results. (authors)

2007-06-01

126

Low-Cost Hydrogen Distributed Production System Development  

Science.gov (United States)

H{sub 2}Gen, with the support of the Department of Energy, successfully designed, built and field-tested two steam methane reformers with 578 kg/day capacity, which has now become a standard commercial product serving customers in the specialty metals and PV manufacturing businesses. We demonstrated that this reformer/PSA system, when combined with compression, storage and dispensing (CSD) equipment could produce hydrogen that is already cost-competitive with gasoline per mile driven in a conventional (non-hybrid) vehicle. We further showed that mass producing this 578 kg/day system in quantities of just 100 units would reduce hydrogen cost per mile approximately 13% below the cost of untaxed gasoline per mile used in a hybrid electric vehicle. If mass produced in quantities of 500 units, hydrogen cost per mile in a FCEV would be 20% below the cost of untaxed gasoline in an HEV in the 2015-2020 time period using EIA fuel cost projections for natural gas and untaxed gasoline, and 45% ...

2011-03-10

127

Stretch-out operation and extended low power operation in Daya Bay Nuclear Power Station  

International Nuclear Information System (INIS)

Stretch-Out and Extended Low Power Operation is two particular operating modes applied for nuclear electricity generation. The relevant safety analysis and the impacts on plant operation are well illustrated, as well as some operation experiences earned in Daya Bay nuclear power station. The safety analysis and plant practice show that Stretch-Out operation and Extended Low Power Operation are operable in Daya Bay nuclear power station

2002-10-01

128

Station set residual : event classification using historical distribution of observing stations.  

Science.gov (United States)

Analysts working at the International Data Centre in support of treaty monitoring through the Comprehensive Nuclear-Test-Ban Treaty Organization spend a significant amount of time reviewing hypothesized seismic events produced by an automatic processing system. When reviewing these events to determine their legitimacy, analysts take a variety of approaches that rely heavily on training and past experience. One method used by analysts to gauge the validity of an event involves examining the set of stations involved in the detection of an event. In particular, leveraging past experience, an analyst can say that an event located in a certain part of the world is expected to be detected by Stations A, B, and C. Implicit in this statement is that such an event would usually not be detected by Stations X, Y, or Z. For some well understood parts of the world, the absence of one or more 'expected' ...

2010-04-01

129

Perspectives on energy storage wheels for space station application  

Energy Technology Data Exchange (ETDEWEB)

Several of the issues of the workshop are addressed from the perspective of a potential Space Station developer and energy wheel user. Systems considerations are emphasized rather than component technology. The potential of energy storage wheel (ESW) concept is discussed. The current status of the technology base is described. Justification for advanced technology development is also discussed. The study concludes that energy storage in wheels is an attractive concept for immediate technology development and future Space Station application.

1984-11-01

130

Introduction to the RCS thermal-hydraulic model of the full scope simulator of Daya Bay Nuclear Power Station  

International Nuclear Information System (INIS)

Both the accuracy and real-time are quite strictly required for the RCS thermal-hydraulic model of the simulation of nuclear power station. So, a large amount of reasonable simplifications should be carried on. The author introduces the RCS thermal-hydraulic model of the full scope simulator of Daya Bay Nuclear Power Station, and emphasizes on the fundamental hypotheses and computation method of its kernel part--DEFI programme.

131

In-core reload design for Daya Bay Nuclear Power Station  

International Nuclear Information System (INIS)

The in-core reload design procedure, computer codes, design contents and comparison between expected design values and measured values for Daya Bay Nuclear Power Station are presented. The in-core reload design for Daya Bay Nuclear Power Station performed by Nuclear Power Institute of China satisfies the requirements of safety and economy. The expected design values are fit well with measured values

2000-12-05

132

Fuel management study on 18 months fuel cycle for Daya Bay Nuclear Power Station  

International Nuclear Information System (INIS)

The fuel management study on 18-months fuel cycle project is introduced for Daya Bay Nuclear Power Station. Station from the selection of the objective of fuel management for 18-months cycle, the method used and the analysis done are explained in detail to reach the final loading pattern chosen

2002-10-01

133

Exploration and practice on contract management of Daya Bay Nuclear Power Station  

International Nuclear Information System (INIS)

In the market economy, Daya Bay Nuclear Power Station needs to out source or allow to suppliers among industries, while concentrating its core competitive capability, for safely and stable operation. By evaluating the features of contract management in Daya Bay Nuclear Power Station, set up the organization and process of the supply management

2002-02-01

134

Electrical equipment of the Marchtrenk power station on the river Traun  

Energy Technology Data Exchange (ETDEWEB)

By way of introduction, the author describes the electrical equipment of the power station on the River Traun and then lists the main features of the electrical systems such as generators, transformers, the power transmission systems as, e.g., the generator leads, the 8 kV switch plant, the 110 kV oil-filled cable as well as the station-service, control, protection and monitoring systems. The control of the headwater level and of the mechanical systems of the barrage is described in detail.

1982-03-01

135

Cause trending analysis for licensing operational events in Daya Bay Nuclear Power Station  

International Nuclear Information System (INIS)

The human causal factors for all human error licensing operational events on Daya Bay nuclear power station since 1993 to 2003 are categorized, the trend of these causal factors is analyzed. The emphasis is placed on analyzing the deficiencies on complying with and executing regulations and procedures. The results provide directional reference for nuclear power station to improve human performance. (author)

2005-09-01

136

Water resources data for Minnesota, water year 1993. Volume 2. Upper Mississippi and Missouri River basins. Water-data report (Annual), 1 October 1992-30 September 1993  

Energy Technology Data Exchange (ETDEWEB)

Water-resources data for the 1993 water year for Minnesota consists of records of stage, discharge and water quality of streams; stage, contents, and water quality of lakes and reservoirs; and water levels and water quality in wells and springs. This volume contains discharge records for 58 gaging stations; stage and contents for 9 lakes and reservoirs; water quality 15 stream stations, 1 lakes station, 1 precipitation station, and water levels for 15 observation wells. Also included are 61 high-flow partial-record stations. Additional water data were collected at various sites, not part of the systematic data collection program and are pulished as miscellaneous measurements.

1994-07-01

137

Water resources data for Minnesota, water year 1991. Volume 2. Upper Mississippi and Missouri River Basins. Water-data report (Annual), 1 October 1990-30 September 1991  

Energy Technology Data Exchange (ETDEWEB)

Water-resources data for the 1991 water year for Minnesota consist of records of stage, discharge and water quality of streams; stage, contents, and water quality of lakes and reservoirs; and water levels and water quality in wells and springs. The volume contains discharge records for 60 gaging stations; stage and contents for 9 lakes and reservoirs; water quality for 18 stream stations, 1 lake station, 22 partial-record sites, 1 precipitation station, 108 wells; and water levels for 119 observation wells. Also included are 59 high-flow partial-record stations. Additional water data were collected at various sites, not part of the systematic data collection program and are published as miscellaneous measurements or low-flow investigations.

1992-09-01

138

Design modifications in radiation monitoring system at Tarapur Atomic Power Station 3 and 4  

International Nuclear Information System (INIS)

Inputs on radiological conditions forms the basis of implementation of effective exposure control to plant personnel in nuclear power station. Radiation monitoring system provides this input to the plant operator as well as to health physics group. Several design modifications have been incorporated in the Radiation Monitoring System at Tarapur Atomic Power Station (TAPS 3 and 4) over the similar systems at Kakrapar Atomic Power Station (KAPS) and Kaiga Generating Station (KGS). The radiological monitoring systems installed at TAPS unit 3 and 4 includes on line Radiation Data Acquisition System (RADAS), Emergency sampling system, effluent monitoring system and environmental monitoring system. The design changes and the versatile use of these systems are presented in this paper. (author)

2006-11-13

139

Cost and sensitivity analysis for photovoltaic station in Kuwait  

Energy Technology Data Exchange (ETDEWEB)

A full analysis is shown in this paper for the cost of kWh generated from photovoltaic station located in Kuwait. By using a 21 years weather data for Kuwait, the yearly generated energy was found by proposing the PV station capacity with known panels tilt angle. The cost of kWh generated from PV station was compared with the kWh generated from conventional units in the country. A sensitivity analysis was done to some factors, capital cost per installed PV peak watt, discount rate, and operating peak hours, which affect the cost of kWh production from both PV and conventional units. If the PV station is proposed to be installed in Kuwait, the capital cost per PV installed peak watt must be less than today`s prices. (author)

1996-05-01

140

Analysis of work-environment data from three army field stations  

Energy Technology Data Exchange (ETDEWEB)

Data from a detailed evaluation of environment conditions in three U.S. Army field stations are presented. Three field stations were evaluated: Kunia, Augsburg, and Berlin. Results from a questionnaire administered to over 600 people at all sites in three job types (operator, analyst, and administrative/other) are given which indicate major concerns with conditions such as temperature, lighting, space, furniture, equipment functioning, and general environmental quality. Physical data obtained from measurements of over 270 work stations indicated the presence of cold temperatures, low light levels, reduced VDT screen contrast, glare, and distracting noises. The report provides the basic data that support the concerns expressed by Headquarters; namely, that field-station personnel perform their jobs under conditions likely to impair their effectiveness. Suggestions for improving conditions are given in a ...

1988-10-01

141

Safe operation of research reactors and critical assemblies code of practice and annexes  

CERN Document Server

Safe operation of research reactors and critical assemblies

1984-01-01

142

Investigation of Destruction Mechanisms in Reactor Steels  

International Science & Technology Center (ISTC)

Investigation of Destruction Mechanisms in Reactor Steels and Alloys under Cycling Deformation

143

Chemical Reactor Diagnostics  

International Science & Technology Center (ISTC)

Development of Methods and Apparatus for Processes Diagnostics in Plasma Reactors at the Neutralization of Chemical Herbiside and Pestiside

144

Comparison Between Active and Passive Techniques for Radon Gas and Working Level measurements, El-Allouga Mine, Sinai, Egypt  

International Nuclear Information System (INIS)

Two different techniques were used for measuring Rn-gas concentrations and Working Level (WL) in U-exploration galleries at El-Allouga Mine, Sinai, Egypt. The active techniques used EDA(RDA-200) with calibrated Lucas cell and Tri-Met-372 instruments and passive techniques used four different types of SSNTD. Twenty eight (28) stations inside the studied tunnels were located covering the different environmental conditions. The measurements were carried out during summer time, in the ventilated sector (16 stations), the average tunnel air temperature was 24.4 #+-# 2.2 degree C and relative humidity 38%. In the non-ventilated sector (12 stations), the average tunnel air temperature was 22.2#+-#0.4 degree C and relative humidity 70%. The Rn-gas concentrations using EDA(RDA-200) and calibrated Lucas cell, in the ventilated sector averaged 11.966 p Ci/l, while in the non-ventilated stations averaged 786.21 p ...

2007-04-22

145

The Decommissioning of the Trino Nuclear Power Plant  

Energy Technology Data Exchange (ETDEWEB)

Following a referendum in Italy in 1987, the four Nuclear Power Plants (NPPs) owned and operated by the state utility ENEL were closed. After closing the NPPs, ENEL selected a ''safestore'' decommissioning strategy; anticipating a safestore period of some 40-50 years. This approach was consistent with the funds collected during plant operation, and was reinforced by the lack of both a waste repository and a set of national free release limits for contaminated materials in Italy. During 1999, twin decisions were made to privatize ENEL and to transform the nuclear division into a separate subsidiary of the ENEL group. This group was renamed Sogin and during the following year, ownership of the company was transferred to the Italian Treasury. On formation, Sogin was asked by the Italian government to review the national decommissioning strategy. The objective of the review was to move from a safestore strategy to a prompt decommissioning strategy, with ...

2002-02-27

146

PSAD-a monitoring and aid to diagnosis system participating in saving on maintenance and operation costs and for plant life extension  

International Nuclear Information System (INIS)

Monitoring nuclear plants components enable to save on operation and maintenance costs by reducing incidents gravity and casual plant stoppages thank to early detection and fast diagnosis. Improving the knowledge of the behaviour of the plant will also allow to optimize maintenance and to increase plant life. In order to improve monitoring and diagnosis capabilities in nuclear power plants. Electricite de France (EDF) is extending the existing data processing chains towards automatic aided interpretation and diagnosis. Therefore, EDF has designed an integrated monitoring and diagnosis assistance system: PSAD-Poste de Surveillance et d'Aide au Diagnostic, including several monitoring functions of the main components. It integrates on-line monitoring, off-line diagnosis and knowledge based systems. PSAD stations provide homogeneous aids to diagnosis which enable plant personnel to pinpoint the mechanical behaviour of plant equipment. The objective of PSAD is to ...

1997-04-14

147

On the development of the METAR family of inspection tools  

Energy Technology Data Exchange (ETDEWEB)

Since 1998, Hydro Quebec Research Centre (IREQ), in collaboration with Gentilly-2, has been working on the development of inspection devices for the feeder tubes of CANDU power plants. The first tool to come out of this work was the Metar bracelet, now used throughout the CANDU utilities, consisting of 14 ultrasonic probes held in place in a rigid bracelet to measure the thickness of the pipes and moved around manually along the pipe. Following the success of the Metar, a motorized version, i.e. the Crawler, has been developed to inspect beyond the operator arm's reach to access hard to reach place or further down the pipes in the reactor. This new system has been tested at 3 different stations and will be commercially available soon. Finally, the same technology was used to develop a motorized 2-axis crack detection device to answer new concerns about the feeder. Other configurations, depending on the demands from the industry, could ...

2003-07-01

148

Mitigating aging in CANDU plants  

Energy Technology Data Exchange (ETDEWEB)

Aging degradation is a phenomenon we all experience throughout life, both on a personal basis and in business. Many industries have been successful in postponing the inevitable impact on their related systems and components through programs to maintain long-term reliability, maintainability and safety. However, this has not always been the case for nuclear power. While all power plants are experiencing the world trend of increasing operating costs with age, few (if any) have been able to fully define the parameters that solve the aging equation, particularly in relation to major components. Inspection and preventive maintenance have not been effective in predicting life-limiting degradation and failure. In CANDU nuclear plants, utilities are taking a comprehensive approach in dealing with the aging problem. Programs have been established to identify the current condition and degradation mechanisms of critical components, the failure of which would impact negatively on ...

1995-07-01

149

Full L.A. treatment  

Energy Technology Data Exchange (ETDEWEB)

The high-purity-oxygen activated sludge process will be used to expand secondary treatment capacity and improve water quality in Santa Monica Bay. The facility is operated by the city of Los Angeles Department of Public Works` Bureau of Sanitation. The overall Hyperion Full Secondary Project is 30% complete, including a new headworks, a new primary clarifier battery, an electrical switch yard, and additional support facilities. The upgrading of secondary facilities is 50% complete, and construction of the digester facilities, the waste-activated sludge thickening facility, and the second phase of the three-phase modification to existing primary clarifier batteries has just begun. The expansion program will provide a maximum monthly design capacity of 19,723 L/s(450 mgd). Hyperion`s expansion program uses industrial treatment techniques rarely attempted in a municipal facility, particularly on such a large scale, including: a user-friendly intermediate pumping ...

1993-09-01

150

Aquatic macroinvertebrates and water quality of Sandia Canyon, Los Alamos National Laboratory, December 1992--October 1993. Status report  

International Nuclear Information System (INIS)

In the summer of 1990, an accidental spill from the TA-3 Power Plant Environment Tank released more than 3,785 liters of sulfuric acid into upper Sandia Canyon. The Biological Resource Evaluation Team (BRET) of EM-8 at Los Alamos National Laboratory (LANL) has collected aquatic samples from the stream within Sandia Canyon since then. These field studies gather water quality measurements and collect macroinvertebrates from permanent sampling sites. An earlier report by Bennett (1994) discusses previous BRET aquatic studies in Sandia Canyon. This report updates and expands Bennett's initial findings. During 1993, BRET collected water quality data and aquatic macroinvertebrates at five permanent stations within the canyon. The substrates of the upper three stations are largely sands and silts while the substrates of the two lower stations are largely rock and cobbles. The two upstream stations are located ...

2004-06-01

151

Evaluating the water quality of the microbasins, La Laucha La Lejia and La Rastrojera using macroinvertebrates as biomarkers, Durania municipality, Norte de Santander Department, Colombia  

International Nuclear Information System (INIS)

From June to September 2004 a water research was carried out in six stations that are located at the following microbasins: La Laucha (S1), La Lejia (S2, S3 and S6) and La Rastrojera (S4 and S5). Those microbasins are localized at the Durania municipality in Norte de Santander Department. This study was carried out in order to evaluate water quality at the microbasins above mentioned using macroinvertebrates as bioindicators. For physical, chemical and microbiological parameters a sample was taken at each station. The results were correlated with biologic parameters and it may be concluded that the station 5 closer to the town of Durania is the most polluted by organic matter and that those stations that belong to the ritral zone are less contaminated. The final result showed that the stations 1. 2. 3. 4 and 6 have conditions that can be classified as very clear to clear water and ...

2008-06-01

152

To Possibility of Usage of FMW Plasma Heating Scenarios in the ICR Frequency Range in the Torsatron Reactor  

International Nuclear Information System (INIS)

The problem of fast wave plasma heating in reactor-torsatron at the ICRF range in scenarios, optimal for fusion reactor, is numerically studied.

2006-01-01

153

Status of reactor physics in Japan  

International Nuclear Information System (INIS)

Recent achievements and tendency on reactor physics activities in Japan are reviewed according to topics published in journals or discussed at the Japan Research Committee on Reactor Physics.

1988-09-18

154

Power spectral density measurements with "2"5"2Cf for a mockup of the FFTF  

International Nuclear Information System (INIS)

... californium 252 fftf reactor mockup power density reactor cores reactor noise

1975-06-08

155

Navy Nuclear-Powered Surface Ships: Background, Issues ...  

Science.gov (United States)

... and support cost, and post-retirement disposal cost) of ... from reactors, and the reactors and other ... the ship's hull and reactor compartment enough to ...

2010-06-10

156
157

A bibliography of AECL publications on reactor safety  

International Nuclear Information System (INIS)

AECL Publications on Reactor Safety in CANDU Reactors are listed in this bibliography. The listing is chronological and the accompanying index is by subject. The bibliography will be brought up to date annually. (auth).

1995-05-08

158

Water resources data for Oklahoma, water year 1992. Volume 2. Red River Basin. Water-data report (Annual), 1 October 1991-30 September 1992  

Energy Technology Data Exchange (ETDEWEB)

Volume 2 of the water resources data for the 1992 water year for Oklahoma consists of record of stage, discharge, and water quality of streams; stage, contents, and water quality of lakes or reservoirs; and water levels of ground-water well. The report contains discharge records for 136 gaging stations; stage and contents for 31 lakes or reservoirs; water quality for 50 gaging stations. Also included are 61 partial-record or miscellaneous streamflow stations and 28 ground-water sites.

1993-04-01

159

The full scope simulator hardware I/O realization in Daya bay nuclear power station  

International Nuclear Information System (INIS)

The full scope simulator in Daya Bay Nuclear Power Station is imported from THOMSON-CSF company in France. It is a large facility, using digital simulation technology, that simulate the main control room of Daya Bay Nuclear Power Station with the high fidelity. It is used for training operators; system analyzing including operation procedure verification. The input output interface system of the simulator is the bridge of the information exchange between instrumentation and the computer. From the point of view of data transfer, this paper discusses the operation principle of the I/O interface system.

160

Redox potential measurement in the power station  

Energy Technology Data Exchange (ETDEWEB)

By its very nature redox potential measurement is suitable for determining the concentration ratio of a stable redox pair through its interaction with a chemically inert electrode surface but not the absolute concentration of a material. The measured redox potentials agree only rarely with those which are easily calculable theoretically. No individual defined stable redox pair is available in power station water. It is therefore not simply possible to measure definable mixed potentials more precisely. For these reasons redox potential measurement in the power station, as also with other types of water, can no longer be regarded as an indicator, by which it can be established whether oxidizing or reducing materials predominate in the water.

1983-01-01

161

Redox potential measurement in the power station  

International Nuclear Information System (INIS)

By its very nature redox potential measurement is suitable for determining the concentration ratio of a stable redox pair through its interaction with a chemically inert electrode surface but not the absolute concentration of a material. The measured redox potentials agree only rarely with those which are easily calculable theoretically. No individual defined stable redox pair is available in power station water. It is therefore not simply possible to measure definable mixed potentials more precisely. For these reasons redox potential measurement in the power station, as also with other types of water, can no longer be regarded as an indicator, by which it can be established whether oxidizing or reducing materials predominate in the water. (orig.).

162

Elemental concentration analysis in some plant samples by EDXRF at Trabzon  

International Nuclear Information System (INIS)

The elemental analysis of some plant samples have been carried out in Trabzon region (Turkey) using energy-dispersive X-ray fluorescence (EDXRF) spectrometry. We have analyzed plant samples for nine stations using 1.85 GBq 55Fe radioactive sources. We have found that potassium and calcium within 0.3-1.4% and 0.3-2.8% were present in concentration in plants for every station, respectively. The concentration of Cl and Ti generally changed according to the plant species and the sampling station.

2006-12-01

163

Air Shower Events of High-Energy Cosmic Rays Measured at Seoul, South Korea  

Science.gov (United States)

The COsmic ray Research and Education Array (COREA) collaboration has installed an array of six detector stations at two high schools in and near Seoul, Korea for measurement of air-shower events from high-energy cosmic rays. Three stations are installed at each site, where each station consists of four plastic scintillation detectors covering an area of 2m2. In this presentation, we report the currenst status of the COREA project, describing the experimental equipment and measurement of coincident events.

2011-09-01

164

Worldwide Report, Telecommunications Policy, Research and ...  

Science.gov (United States)

... 80 Briefs New Television Transmitter 81 Matadi Satellite Earth Station Inaugurated (Kinshasa AZAP, various dates) 82 Ramazani Marks Opening ...

1985-12-31

165

Waste Food Storage at Fortress Rocks  

Science.gov (United States)

... of waste food generated at McMurdo Station. Some of the difficulties of disposing of waste food ... change waste generation or management at the site? Yes. This will be a temporary waste management ...

166

Underground reservoirs for high-head pumped-storage stations  

Science.gov (United States)

The advantages of using heads of around 1000 m in conjunction with underground location of the lower reservoirs for pumped storage plants are described, and the possible layouts, equipment, and construction methods are discussed.

1973-03-01

167

The Deep Space Network Progress Report 42-39 - NASA Technical ...  

Science.gov (United States)

C. Learning Curve. The learning curve concept has long been recognized and ...... F4. TERMIA. S - STATION EQUIPMENT. V - VLBI VALIDATION EQUIPMENT ...

168

Sun rises on station era - Johnson Space Center - NASA  

Science.gov (United States)

Dec 4, 1998 ... throwing a single switch to as complex as the Spartan deploy and retrieve. ...... The camera, called the Acousto-Optic ...

169

SPACE STATION INTEGRATED WALL DESIGN AND PENETRATION  

Science.gov (United States)

screens of fine wire was placed between the gun barrel and the panel to determine whether the gun performance was repeatable. The transducers were placed ...

170

Rim of the Pacific (RIMPAC). Programmatic Environmental ...  

Science.gov (United States)

... Air Station, Oahu, Kahuku Training Area ... K-Pier, Hawaii, Bradshaw Army Airfield, Hawaii (R&S ... impact area); Makua Military Reservation, Oahu (R&S ...

2002-06-01

172

NASA Sets Launch Dates for Remaining Space Shuttle Missions  

Science.gov (United States)

Jul 7, 2008 ... HOUSTON -- Following a detailed, integrated assessment, NASA selected ... in the center that provides a 360-degree view around the station. ...

173

NASA - Archive  

Science.gov (United States)

equipping the trio of SPHERES on the space station with a Nexus(tm) S handset made by Samsung Electronics and powered by Google's Android(tm) platform. graphic for the NASA mobile...

2011-08-19

174

Metronome to Coordinate the Breaths and Cardiac Compressions Delivered by Minimally-Trained Caregivers During Two-Person CPR  

Science.gov (United States)

Astronaut crew medical officers (CMO) aboard the International Space Station (ISS) receive 40 hours

2005-01-01

175

Johnson News - NASA  

Science.gov (United States)

Nov 21, 2003... for the European Space Agency's Automated Transport Vehicle, a new, uncrewed station cargo vehicle targeted for launch late next year. ...

176

Direct Detection Optical Intersatelllte Link at 220 Mbps Using ...  

Science.gov (United States)

on this technology has beenproposedas a payload on SpaceStation Freedom to be launched in the near future [1]. Direct detection 4-ary pulse position modula- ...

177

Classes of KWU steam turbines  

International Nuclear Information System (INIS)

For the conversion of thermal energy into electric energy in modern condenser power plants, according to the way of steam generation, two different types of power stations are built: power stations for fossile fuels and nuclear power stations. Also two classes of steam turbines were developed, corresponding to the two power station types, whose steam conditions, by experience and extensive calculations of economy, were determined so that a minimum of power generating cost will result. The two classes, the HMN and the SN series, are composed according to the modular system and designed in such a manner that with a small number of standard components, steam turbines for the power range between 100 and 2,500 MW can be built. (orig.).

178

Alternative Fuel Stations | Department of Energy  

Science.gov (United States)

2011 Department of Energy Investments in Carbon Capture Technologies 2010 Smart Meter Installations DOE Recovery Field Projects and State Memos Advanced Vehicle...

2011-10-08

179

Air pollution in Berlin and its surroundings in 1989. Luftverschmutzung in Berlin und Umgebung im Jahr 1989  

Energy Technology Data Exchange (ETDEWEB)

The report presents details of the distributions of air pollution in the Berlin area and the developments of the past 20 years. Highly polluted areas are indicated in which air pollution reduction measures are particularly urgent. The report therefore intends not only to inform but also to point out the deficiencies of air pollution abatement measures, so that political consequences can be derived and measures can be taken. In all, data were recorded by 39 measuring stations in West Berlin, 16 in East Berlin, and 7 in Potsdam and Frankfurt/Oder. In most stations, sulphur dioxide and airborne dust were measured; 14 stations in West Berlin and one in East Berlin measured carbon monoxide and nitric oxides; 8 stations in West Berlin recorded ozone concentrations. (orig./KW).

1990-10-01

180

54 - IGS  

Science.gov (United States)

Eight units (low-power model Z-12's) were purchased, all for installation at continuously- operating stations in the Los Angeles prototype Dense GPS ...

182

FFTF reactor assembly system technology  

Science.gov (United States)

An overview is presented of the FFTF reactor and plant together with descriptions of core components, core internals, core system, primary and secondary control rod system, reactor instrumentation, reactor vessel and closure head, and supporting test programs. (DG)

1975-11-13

183

FFTF reactor assembly system technology  

International Nuclear Information System (INIS)

An overview is presented of the FFTF reactor and plant together with descriptions of core components, core internals, core system, primary and secondary control rod system, reactor instrumentation, reactor vessel and closure head, and supporting test programs.

1976-03-13

185

The Cordoba and Wolsung projects: a progress report  

International Nuclear Information System (INIS)

Progress on construction of the Cordoba reactor in Argentina and the Wolsung reactor in Korea is described. (E.C.B.).

1977-06-01

187

MR-6 Type Fuel Elements Cooling in Natural Convection Conditions after Reactor Shutdown  

International Nuclear Information System (INIS)

... Natural convection cooling of the channel type reactor performed with the fuel

1992-08-03

188

Fluidic shut-down system for a nuclear reactor  

International Nuclear Information System (INIS)

... fluid poison control fluidic control devices reactors scram scram rods control

189

CRC handbook of nuclear reactors calculations. Vol. II  

International Nuclear Information System (INIS)

This handbook breaks down the complex field of nuclear reactor calculations into major steps. Each step presents a detailed analysis of the problems to be solved, the parameters involved, and the elaborate computer programs developed to perform the calculations. This book bridges the gap between nuclear reactor theory and the implementation of that theory, including the problems to be encountered and the level of confidence that should be given to the methods described. Volume II: Monte Carlo Calculations for Nuclear Reactors. In-Core Management of Four Reactor Types. In-Core Management in CANDU-PHW Reactors. Reactor Dynamics. The Theory of Neutron Leakage in Reactor Lattices. Index.

190

Annual report, 1979-1980  

Energy Technology Data Exchange (ETDEWEB)

Information is presented concerning reactor research activities; isotope geology; NERC radiocarbon laboratory; teaching activities; and reactor operation.

1980-01-01

191

Analysis of the MEX-15 multipurpose reactor using SRAC code system  

Energy Technology Data Exchange (ETDEWEB)

The MEX-15 is a conceptual design of a Multipurpose Reactor with thermal power of 15 MW and this reactor is pool type with fuel plates U{sub 3}0{sub 8}-Al of low enrichment uranium. This report presents the static calculation for the MEX-15 reactor using SRAC code system and was developed under the collaboration agreement between ININ-JAERI in Research Reactor Technology Development Division of Department of Research Reactor in Tokai Research Establishment. (Author)

1992-12-15

192

The environmental impacts of a large gas-fired combined cycle power station  

Energy Technology Data Exchange (ETDEWEB)

The paper discusses the potential environmental impacts associated with the operation of a large, say 350 MWe, gas-fired combined cycle power station. It concludes that if appropriate control methods are introduced at the design stage of the plant, environmental impacts are minimal and can be considered acceptable. (author).

1991-11-01

193

The computerized management for individual monitoring data in Daya Bay Nuclear Power Station  

International Nuclear Information System (INIS)

The authors report the individual monitoring data management system (IDOSE) at Daya Bay Nuclear Power Station. The components of the individual monitoring system, the design requirements of IDOSE, the characteristics and application of this computerized management system are mainly presented. Its application shows that IDOSE meets the requirements of the concerning occupational standards of the state and matches with the requirements of IAEA/ISOE.

194

The Atomic Energy Control Board criteria for identification and evaluation of fire hazards in nuclear power stations  

International Nuclear Information System (INIS)

This report presents criteria for the identification and evaluation of fire hazards in nuclear power stations. The report presents criteria that are consistent with the existing regulatory approach in Canada, and outlines engineering tools and analytical techniques currently available to deterministically analyse fire. The criteria presented cover the topics which should be included in a fire hazard analysis and provide details of each topic so that the accuracy of an analysis may be evaluated.

2000-12-10

195

Survey of Flue Gas Desulfurization Systems: Will County Station, Commonwealth Edison Co.  

Science.gov (United States)

The report gives results of a second survey of the flue gas desulfurization (FGD) system on Unit 1 of Commonwealth Edison Co.'s Will County Station. The FGD system, started up in February 1972, uses a limestone slurry in two parallel scrubbing trains. Eac...

1978-01-01

196

Survey of Flue Gas Desulfurization Systems: La Cygne Station, Kansas City Power and Light Co.  

Science.gov (United States)

The report gives results of a second survey of the flue gas desulfurization (FGD) system on Unit 1 of Kansas City Power and Light Co.'s La Cygne Station. The FGD system, first started up in February 1973 and commercially available in June 1973, uses a lim...

1978-01-01

197

Survey of Flue Gas Desulfurization Systems: Cholla Station, Arizona Public Service Co.  

Science.gov (United States)

The report gives results of a second survey of the flue gas desulfurization (FGD) system on Unit 1 of Arizona Public Service Co.'s Cholla Station. The FGD system, commercially available in December 1973, uses a limestone slurry in two parallel scrubbing m...

1978-01-01

198

Survey of Flue Gas Desulfurization Systems, Lawrence Power Station, Kansas Power and Light Co.  

Science.gov (United States)

The report gives results of a survey of the flue gas desulfurization (FGD) systems at Kansas Power and Light Co.'s Lawrence Power Station. The systems utilize boiler injection of pulverized limestone, followed by tail-end wet scrubbing: unit 4, with a net...

1975-01-01

199

Survey of Flue Gas Desulfurization Systems Hawthorn Station, Kansas City Power and Light Co.  

Science.gov (United States)

The report gives results of a survey of the flue gas desulfurization (FGD) systems at Kansas City Power and Light Co.'s Hawthorn Power Station. The FGD systems on Hawthorn boilers 3 and 4 were designed to operate by injection of dry limestone in the boile...

1975-01-01

200

Supported soft material compensators for combined gas and steam turbine power stations. Gestuetzte Weichstoff-Kompensatoren fuer Gas-Dampfturbinen-Kombi-Block-Kraftwerke  

Energy Technology Data Exchange (ETDEWEB)

In combined cycle turbine power stations, soft material compensators are used which, if the full pressure fails, also withstand a small external pressure. Innovative forms of construction which guarantee useful life, are presented in relation to the design. Damaging effects, which limit the life of these special soft material compensators, are discussed. (orig.)

1994-09-01

201

Round Cell batteries in Class 1E applications  

International Nuclear Information System (INIS)

The AT and T Round Cell has recently become a viable alternative to the conventional, rectangular, lead acid storage batteries in Class 1E applications at US nuclear generating stations. This paper discusses the qualification of the Round Cell for nuclear generating stations, its principal design attributes, the types of Class 1E applications most suited for the Round Cell, and industry experience related to its installation and operation.

1996-04-09

202

Practice of radiation source control at Daya Bay Nuclear Power Station  

International Nuclear Information System (INIS)

Daya Bay Nuclear Power Station has made a series of tries and efforts on radiation source control and benefited from them since it was put into commercial operation. Some of them were introduced from experience feedbacks of foreign nuclear power industry and others came from our own good practices

2004-05-01

203

Improved control of fuel crushing in coal-fired power stations  

Energy Technology Data Exchange (ETDEWEB)

With the frequent load changes to which a hard coal power station is subjected in the middle and peak load range, great demands are linked with the transient behaviour of the steam generator. Due to the serial connection of the crusher and boiler, the strongly delaying transient behaviour of the crusher compounds entirely with the transient behaviour of the steam generator. Therefore, a suggestion is to be made here as to the improvement of the dynamics of the crusher.

1988-01-01

204

Guangdong Daya Bay nuclear power station project  

International Nuclear Information System (INIS)

Daya Bay Nuclear Power Station is the largest joint-venture project which is also the largest commercial nuclear power plant currently under construction in China mainland. Organized and executed strictly in accordance with international standards, the Daya Bay project is seen as the first step taken by China in the development programme of large-capacity commercial nuclear power units.

1994-04-01

205

Far East combined-cycle update  

Energy Technology Data Exchange (ETDEWEB)

Korea Electric Power Corporation (Kepco) of South Korea has awarded Asea Brown Boveri Switzerland, a member of the ABB Group, a contract to supply the main equipment for two gas-fired combined-cycle power stations. News of the contract followed an announcement last year that Kepco will build a series of gas-fired power stations in the early 1990s to supply electricity to new housing and commercial areas being built in the Seoul-Incheon connurbation. (author).

1991-03-01

206

Environmental #gamma# dose rate monitoring system around Guangdong Daya Bay Nuclear Power Station  

International Nuclear Information System (INIS)

This article introduces the composition, monitoring methods and working principles of environmental #gamma# dose rate continuous monitoring system at Guangdong Daya Bay Nuclear Power Station. The #gamma# dose rate monitoring status after modification of measurement conditions is introduced too.

207

Daya Bay Nuclear Power Station outdoors electrical equipment pollution status analysis and improving  

International Nuclear Information System (INIS)

According to the practice operation experience of the outdoors electrical equipment in Guangdong Daya Bay Nuclear Power Station, following to the engineering technical standard applied in China, by analysis and assessment of pollution classes, it is considered that the class four is reasonable. And indicated the voltage distance should be more than 3.5 cm/kV. Some improvements had been executed and effects are good. And further suggest some improving comments

2002-06-01

208

Cause analysis of cracks in circulating water culvert of Daya Bay Nuclear Power Station  

International Nuclear Information System (INIS)

In view of the widespread cracks discovered in the reinforced-concrete circulating water culvert of Daya Bay Nuclear Power Station, cause analysis for the cracks is made in terms of construction and design. It is concluded that the cracks mainly resulted from shrinkage and temperature. Corresponding countermeasures are put forward thereafter for reference of similar projects

2000-06-01

209

Calculation of fission product behaviour in a station blackout accident of Daya Bay Nuclear Power Plant  

International Nuclear Information System (INIS)

The early accident Sequence of the Station Blackout accident is simulated for Daya Bay Nuclear Power Plant, using MELCOR code. The radioactivity of main fission products was derived after calculating the source term in containment. The data will be used for Daya Bay NPP PSA analysis

2002-12-01

210

Assessment of internal contamination due to gamma emitters at nuclear power stations of Tarapur  

International Nuclear Information System (INIS)

Personal monitoring and dose assessment of all radiation workers is an essential regulatory requirement as per radiation safety procedures of AERB and operating stations. The occupational workers of TAPS 1 and 2 and TAPS 3 and 4 are monitored for internal contamination due to high energy gamma emitters by whole body counting

2010-02-03

211

Aquatic macroinvertebrates and water quality in Sandia Canyon  

International Nuclear Information System (INIS)

In 1990, field studies of water quality and stream macroinvertebrate communities were initiated in Sandia Canyon at Los Alamos National Laboratory. The studies were designed to establish baseline data and to determine the effects of routine discharges of industrial and sanitary waste. Water quality measurements were taken and aquatic macroinvertebrates sampled at three permanent stations within the canyon. Two of the three sample stations are located where the stream regularly receives industrial and sanitary waste effluents. These stations exhibited a low diversity of macroinvertebrates and slightly degraded water quality. The last sample station, located approximately 0.4 km (0.25 mi) downstream from the nearest wastewater outfall, appears to be in a zone of recovery where water quality parameters more closely resemble those found in natural streams in the Los Alamos area. A large increase in ...

2005-09-01

212

Transportation for reprocessing of the spent nuclear fuel (SNF) of TVR ITEP research reactor and proposals for SNF management plans for the RA reactor  

International Nuclear Information System (INIS)

The TVR heavy water research reactor was deployed at Moscow Institute of Theoretical and Experimental Physics. In 1990, the final batch of the spent nuclear fuel from this reactor was shipped to Production Association (PA) 'Mayak' for reprocessing. The SNF removal was a stage of the reactor decommissioning activities. The designs of the TVR reactor and its fuel elements are similar to the RA reactor designs. Two ways of the RA reactor SNF transportation to PA 'Mayak' have been considered: in aluminum barrels and in additional canisters using respectively TUK-32 and TUK-19 shipping casks. The practical experience and the equipment used to prepare for the TVR reactor SNF removal can be helpful to the RA reactor personnel in finding the best way to perform these engineering operations. (author)

2003-03-09

213

Nuclear Power Reactors in the World. 2009 Ed  

International Nuclear Information System (INIS)

This is the twenty-ninth edition of Reference Data Series No. 2, Nuclear Power Reactors in the World, which is published once per year, and presents the most recent reactor data available to the IAEA. It contains the following summarized information: - General information as of the end of 2008 on power reactors operating or under construction, and shut down; - Performance data on reactors operating in the Agency's Member States, as reported to the IAEA. The IAEA's Power Reactor Information System (PRIS) is a comprehensive data source on nuclear power reactors in the world. It includes specification and performance history data of operating reactors as well as reactors under construction or reactors being decommissioned. PRIS data are collected by the IAEA through the designated national ...

214

The operating experience for Wolsung Unit 3 commissioning  

International Nuclear Information System (INIS)

This is a slide-based oral presentation given to the COG/IAEA: Fifth technical committee meeting on 'Exchange of operating experience of pressurized heavy water reactors' held in Mangalia, Romania on 7-10 September 1998. Since energization of Wolsung Unit 3 station service transformer on July 12, 1996 a line of initial test program was conducted as follows: 1. ILRT/SIT; 2. Pre-operational and Hot Functional testing with a Light Water and without Fuel in Systems; 3. Load D_2O in Moderator System; 4. Initial fuel loading; 5. Load D_2O in PHT System; 6. Hot Functional Testing with Heavy Water and Fuel in Systems; 7. Criticality and Low Power Physics Testing; 8. Power Ascension Test and, then finally, phase-D test; the plant acceptance test was accomplished after having a Mini-Overhaul to prepare for Commercial Operation. These documents contain not only both overall introduction of commissioning and the first TBN rolling and Synchronization test ...

1998-09-07

215

Radioactivity of people in Finland after the Chernobyl accident in 1986  

International Nuclear Information System (INIS)

After the reactor accident at Chernobyl on April 26, 1986 radioactive fallout was carried by air currents to most parts of Europe. The radioactive air currents reached Finland on April 27. Immediately after the arrival of such air in Finland, contamination of people by radioactive nuclides began via inhalation of this air. The ingestion route become important later, when radionuclides were transported via different foodchains to man. To determine the level of radionuclides in the body and to estimate the internal radiation doses caused by the Chernobyl accident, whole-body counting measurements were performed. The results of whole-body counting of six different groups of Finnish people measured during 1986 after the accident at Chernobyl are reported. Three were reference groups measured routinely once or twice annually, two groups were comprised of workers at nuclear power stations and one group consisted of 262 persons not belonging to any ...

2004-02-01

216

One-piece removal of JRR-3 reactor block  

Energy Technology Data Exchange (ETDEWEB)

JRR-3 is a research reactor of 10 MWt output, which attained the criticality in 1962. All the design, manufacture, installation and others of this reactor were carried out by Japanese technologies, except the fuel and heavy water as the moderator and coolant, therefore it is nicknamed Home-made No.1 Reactor. Recently, due to the change in the state of utilizing research reactors and the rise of quality in the utilization, JRR-3 has become to be unable to meet sufficiently the needs of users. The plan of reconstructing the JRR-3 was considered under such situation, and in order to reuse the reactor building, the reactor proper is removed, and an entirely new, high performance, versatile reactor is to be constructed. In this paper, as to the removal works of the JRR-3 reactor proper, the method of execution, design, the ...

1987-07-01

217

Development of the Regulation Concept for a Fusion Reactor  

International Nuclear Information System (INIS)

Fusion energy has been studied in many countries such as U.S., France, Japan, Korea etc. Because it would provide much more energy for a given weight of fuel than any technology currently in use, and the fuel itself (primarily deuterium) exists abundantly in the Earth's ocean. Nuclear fusion reactor uses tritium and deuterium as fuel while nuclear fission reactor uses uranium and plutonium as fuel. Besides, inherent design characteristics and driving condition of nuclear fusion reactor is different from those of nuclear fission reactor. Therefore, we cannot apply the regulation rules of nuclear fission reactor to nuclear fusion reactor without change and thus it is needed to development of the safety regulation concept which reflects the characteristics of nuclear fusion reactor. Safety regulation of nuclear fusion ...

2010-10-01

218

CRC handbook of nuclear reactors calculations. Vol. III  

International Nuclear Information System (INIS)

This handbook breaks down the complex field of nuclear reactor calculations into major steps. Each step presents a detailed analysis of the problems to be solved, the parameters involved, and the elaborate computer programs developed to perform the calculations. This book bridges the gap between nuclear reactor theory and the implementation of that theory, including the problems to be encountered and the level of confidence that should be given to the methods described. Volume III: Control Rods and Burnable Absorber Calculations. Perturbation Theory for Nuclear Reactor Analysis. Thermal Reactors Calculations. Fast Reactor Calculations. Seed-Blanket Reactors. Index.

219

Comprehensive report to Congress Clean Coal Technology Program: Warren Station EFCC Demonstration Project  

Energy Technology Data Exchange (ETDEWEB)

One of the five projects selected for funding within the Clean Coal Technology Program is a project proposed by the Pennsylvania Electric Company (Penelec) of Johnstown, Pennsylvania. Penelec proposes to enter into a cooperative agreement with DOE to design, construct and operate a 600 ton-per-day, 66-megawatt (MWe), coal-fueled, externally-fired combined cycle (EFCC) electric power generation facility. The EFCC is an emerging technology with promise for operating highefficiency combined gas- and steam-turbine cycles on coal. The central feature of EFCC is its coupling of the gas turbine to an external, atmospheric-pressure, coal combustor via a hightemperature ceramic heat exchanger (CerHx{reg_sign}) developed by Hague International. The EFCC technology is attractive because, unlike competing combined cycles such as Integrated Gasification (IGCC) and Pressurized Fluidized Bed Combustion (PFBC), it eliminates the need for a costly gas cleanup system to protect the gas turbine ...

1994-06-01

220

The results of investigations in connection with development of methods for integrated optimization of fast reactors parameters  

International Nuclear Information System (INIS)

The results for development of methods and computer programs for integrated optimization of parameters of perspective fast reactors are given. The possibilities of the program for the reactor campaign calculation are analysed. This program is based on utilisation of the Bubnov-Galerkin method and Wigner disturbance theory. The possibility of application of approximation methods for the optimization researches is discussed. The results of development of the programs for complex reactor computations with account of control rods system and change of physical parameters in the reactor campaign are discussed. (author).

1974-07-01

221

HTR looking forward to his future with confidence  

International Nuclear Information System (INIS)

The days of high-temperature reactors in the Federal Republic of Germany are numbered. The AVR has been decommissioned, and an application has been filed for licensing the decommissioning of the THTR. Nevertheless, Prof. Dr. Rudolf Schulten who is the director of Juelich Nuclear Research Center's Institute for Reactor Development, and also full professor of Aachen Technical University in the field of reactor safety, predicts a good future for the HTR reactor line on a worldwide level, due to the inherent safety of this reactor type. (orig.).

222

Development of breeder reactors in Japan  

Energy Technology Data Exchange (ETDEWEB)

In the framework of a global analysis of the various available sources of energy, Japan has reserved a prominent place to the nuclear energy, and in the long-term view, to the breeder reactor which will be due for commercial deployment in 2010. To achieve these objectives, three stages are envisaged, one of the experimental reactor Joyo (in service), one of the demonstration reactor Monju (its construction has been decided), and one of the pre-commercial reactor (due to be taken in hand at the beginning of the Nineties). Efforts will be made in parallel concerning the fuel cycle.

1984-01-01

223

Utilization of geothermal energy in the USSR  

International Nuclear Information System (INIS)

This paper reports that at present geothermal energy is utilized in the USSR mostly for district heating, and for industrial and agricultural purposes. The populations of 7 towns have district heating that is supplied by thermal waters. The population supplied totals about 125,000 people. The total area of greenhouses is 850,000 m"2. Electric energy generated at geothermal power stations still remains negligible with the installed capacity of the single Pauzhetka station (Kamchatka) being 11 MW. another station at Mutnovka is currently under construction and is expected to be producing 50 MW by 1992 and 200 MW by 1998. The proven geothermal resources in the USSR provide hope for a significant increase in the utilization of the earth's deep heat in the near future.

1990-08-20

224

U.S. Department of Energy, Nevada Operations Office, Environmental Monitoring Program: Summary data report - first and second calendar quarters 1994  

International Nuclear Information System (INIS)

During the first and second quarters of 1994 air samples were collected and analyzed from 54 air particulate/halogen sampling stations, 10 noble gas sampling stations and 19 tritiated water vapor sampling stations. Surface water samples were collected and analyzed from 12 open water supply reservoirs, 8 natural springs, 2 wastewater containment ponds and 9 sewage lagoons. Groundwater samples were obtained brom 10 potable and 1 non-potable supply wells, and 8 drinking water consumption points. Ambient radiation levels were measured at 193 locations.

1991-10-31

225

Thermal impact analysis of discharge of circulating cooling water at Daya Bay Nuclear Power Station (GNPS) and Ling'ao Nuclear Power Station (LNPS)  

International Nuclear Information System (INIS)

The circulating cooling water flowrate of GNPS and LNPS is totally about 190 m"3/s. Both stations are located on the western coast of semi-closed Daya Bay. A lot of studies concerning thermal impact of GNPS and LNPS have been carried out since 1987, including mathematical model, physical model, on-site survey and satellite remote sensing, etc. This paper describes the hydrological features of Daya Bay and discharge characteristics of circulating water of GNPS and LNPS, estimates the actual thermal impact of GNPS and LNPS, and indicates that it is advantageous for the dilution of circulating water while the two discharge channels of GNPS and LNPS are combined together towards east

2004-05-01

226

The influence of contrasting suspended particulate matter transport regimes on the bias and precision of flux estimates  

British Library Electronic Table of Contents (United Kingdom)

A large database (507 station-years) of daily suspended particulate matter (SPM) concentration and discharge data from 36 stations on river basins ranging from 600?km2 to 600,000?km2 in size (USA and Europe) was collected to assess the effects of SPM transport regime on bias and imprecision of flux estimates when using infrequent surveys and the discharge-weighted mean concentration method. By extracting individual SPM concentrations and corresponding discharge values from the database, sampling frequencies from 12 to 200 per year were simulated using Monte Carlo techniques. The resulting estimates of yearly SPM fluxes were compared to reference fluxes derived from the complete database. For each station and given frequency, bias was measured by the median of relative errors between estima...

2006-01-01

227

Quality engineering programme in the design process. A major utility 's experience  

International Nuclear Information System (INIS)

The paper describes the latest approach to quality engineering in the design process as applied by Ontario Hydro throughout the various phases of the project life cycle for Ontario Hydro generating stations and related facilities. Ontario Hydro has long recognized that the high quality and performance required in nuclear generating stations start in the design process and can best be achieved through an adequate and proper quality engineering programme in design. The current approach has evolved over a period of six years and represents a meaningful and effective series of requirements, functions and activities, which are used to ensure safety, reliability, economy and environmental acceptability of nuclear generating stations. (author).

228

Photochemical assessment monitoring: Overview and current status  

Energy Technology Data Exchange (ETDEWEB)

The Clean Air Act Amendments of 1990, established requirements for the Environmental Protection Agency (EPA) to develop rules for the establishment of enhanced ozone monitoring networks or Photochemical Assessment Monitoring Stations (PAMS) in ozone nonattainment areas designated as serious, severe, and extreme. The subsequent rules require these stations to collect ambient air measurements for a target list of volatile organic compounds including several carbonyls, oxides of nitrogen, ozone, and meteorological measurements, both surface and upper air. Twenty-two areas in the US are obligated to install and operate PAMS stations to aid in the identification, development, and implementation of effective ozone control strategies. This paper will examine the specific requirements of the PAMS rules and will provide information regarding the current status of the networks and overall implementation issues.

1994-12-31

229

Behaviour of the steam generators in the Belgian nuclear power plants  

International Nuclear Information System (INIS)

After a brief review of the degradations occurring on tubes of Inconel 600 in steam generators of PWR power stations emphasis is put on the conditioning of the secondary water and more particularly on the condensate treatment in the units of Doel which work on heavily polluted brackish water. The important role of non-destructive testing and eddy-current testing is also pointed out, method developed by Laborelec. The operational experience shows that Belgian stations are nearly not concerned by the degradations mostly found in power stations in other countries which shows the efficiency of the conditioning of the secondary water. On the other hand, other problems have occurred, resulting from: damage caused by foreign objects; fouling of tube before commissioning, cracking of bends and at the limit of the dudgeoning and leaking plugs. (AF).

1986-04-15

230

Application of nuclear energy for power generation at TAPS 3 and 4  

International Nuclear Information System (INIS)

Tarapur Atomic Power Station, Unit 3 and 4 is located on the West Coast of the Arabian Sea near the existing Tarapur Atomic Power Station Unit 1 and 2. The nearest railway station is Boisar at a distance of 12 km from the site, which is on the main Western Railway Mumbai-Delhi route. The site is well connected by road and is about 30 Km from Mumbai-Ahmedabad National Highway-NH-8. The paper describes the land acquisition and rehabilitisation of the affected families, importance of project in the western grid, how it works, working principles of PHWR, principle of operation, major components/equipment, important systems, safety features, and waste management

2010-10-01

231

The Neutron Radiography Reactor (NRAD)  

Science.gov (United States)

The Neutron Radiography Reactor (NRAD) operated by Argonne National Laboratory is described in this paper. NRAD was designed to allow radiography of highly absorbing reactor fuel assemblies in the vertical position on the routine basis. 7 figs.

1990-01-01

232

Fusion Reactor Radioactive Waste Management.  

Science.gov (United States)

Quantities and compositions of non-tritium radioactive waste are estimated for some current conceptual fusion reactor designs, and disposal of large amounts of radioactive waste appears necessary. Although the initial radioactivity of fusion reactor and f...

1976-01-01

233

Fast Flux Test Facility Reactor Vessel Removal Study  

Energy Technology Data Exchange (ETDEWEB)

This study assesses the feasibility of removing the FFTF reactor vessel from its current location in the reactor cavity inside the Containment vessel to a transporter for relocation to a burial pit in the 200 Area.

2002-10-23

234

Emergency reactor core cooling device  

International Nuclear Information System (INIS)

The device of the present invention improves reactor safety by suppressing lowering of water level in a shroud which surrounds a reactor core, even upon occurrence of rupture of pipelines in an emergency reactor core cooling system in a recycling pump-incorporated type reactor. Namely, an opening of each of cooling systems which forms the emergency reactor core cooling device in a reactor pressure vessel is disposed above the upper end of the reactor core. Further, it also comprises an independent high pressure water injection system, gravitational dropping type water injection system and an automatic depressurization system. With such a constitution, even if rupture of pipelines in the system should be assumed, coolants never flow directly from the shroud which surrounds the reactor core. In addition, there are no ...

1993-03-16

235

Designer himself throws light upon high-temperature reactor  

Energy Technology Data Exchange (ETDEWEB)

THe high-temperature reactor is one of the alternatives for the now predominantly employed water-reactors. In a recently published book designer Rudolf Schulten outlines his concept. In this article the book is reviewed. (author). 1 ref.; 1 fig.

1990-04-01

236

Designer himself throws light upon high-temperature reactor  

International Nuclear Information System (INIS)

THe high-temperature reactor is one of the alternatives for the now predominantly employed water-reactors. In a recently published book designer Rudolf Schulten outlines his concept. In this article the book is reviewed. (author). 1 ref.; 1 fig.

237

CANDU year in review  

Energy Technology Data Exchange (ETDEWEB)

The commissioning of four CANDU-600 reactors is discussed, with mention of some design features. The four are Point Lepreau, Gentilly-2, Wolsung and Cordoba reactors. The commissioning of Pickering-5 is also mentioned, and so are some events affecting other CANDU reactors.

1983-01-01

238

Steady-state neutronic investigations to the accident of water ingress in systems with pebble-bed high-temperature gas-cooled reactor fuel  

Energy Technology Data Exchange (ETDEWEB)

For light water reactors, loss of coolant is an important point in safety analysis, whereas for gas-cooled reactors the ingress of water into the core region is an incident of safety relevance. The applicability of the computer code system GAMTEREX to pebble beds of spherical high-temperature gas-cooled reactor fuel elements with simulated water ingress is verified by experiment. The measurements were performed at a Siemens-Argonaut reactor, using its ring core as a driver zone for a pebble-bed core in the center of the reactor.

1987-09-01

239

HTR looking forward to his future with confidence. An interview with Professor R. Schulten, the father of the high-temperature reactor  

Energy Technology Data Exchange (ETDEWEB)

The days of high-temperature reactors in the Federal Republic of Germany are numbered. The AVR has been decommissioned, and an application has been filed for licensing the decommissioning of the THTR. Nevertheless, Prof. Dr. Rudolf Schulten who is the director of Juelich Nuclear Research Center's Institute for Reactor Development, and also full professor of Aachen Technical University in the field of reactor safety, predicts a good future for the HTR reactor line on a worldwide level, due to the inherent safety of this reactor type. (orig.).

1989-06-02

240

Formation and decay of secondary actinides in water reactor and fast neutron reactors  

International Nuclear Information System (INIS)

Actinides other than the main uranium or plutonium isotopes take a growing part in the different stages of the nuclear cycle. For the French nuclear power program based on the development of light water reactors and fast breeders, many evaluations of the secondary actinides build up are made for the both reactor types using mainly the existing reactor codes. The comparison of these foreseen compositions with experimental results allows to perform some adjustments of the neutronic data. The secondary actinide compositions are given for some typical fuels and their consequences on the nuclear cycle are discussed. An hypothetical burning of these wastes in fast reactors has been studied and the main conclusions are reported.

241

Evolution of reactivity control mechanisms for nuclear research and power reactors in India  

International Nuclear Information System (INIS)

Division of Remote Handling and Robotics (DRHR) at Bhabha Atomic Research Centre (BARC) has been working on design and development of Reactivity Control Mechanisms for Nuclear Research Reactors (Dhruva, KAMINI and recently Critical Facility of Advanced Heavy Water Reactor (AHWR)) as well as Power Reactors in India (Pressurized Heavy Water Reactors of 220 MWe at Narora and recently India's first 540 MWe PHWR Unit -1 and 2 at Tarapur). This paper gives a brief account of evolution of reactivity control mechanisms for nuclear research and power reactors in India. (author)

2009-10-01

242

Characterization of chemical looping combustion of coal in a 1 kW{sub th} reactor with a nickel-based oxygen carrier  

Energy Technology Data Exchange (ETDEWEB)

Chemical looping combustion is a novel technology that can be used to meet the demand on energy production without CO{sub 2} emission. To improve CO{sub 2} capture efficiency in the process of chemical looping combustion of coal, a prototype configuration for chemical looping combustion of coal is made in this study. It comprises a fast fluidized bed as an air reactor, a cyclone, a spout-fluid bed as a fuel reactor and a loop-seal. The loop-seal connects the spout-fluid bed with the fast fluidized bed and is fluidized by steam to prevent the contamination of the flue gas between the two reactors. The performance of chemical looping combustion of coal is experimentally investigated with a NiO/Al{sub 2}O{sub 3} oxygen carrier in a 1 kW{sub th} prototype. The experimental results show that the configuration can minimize the amount of residual char entering into the air reactor from the fuel ...

2010-05-15

243

Axiomatic Design Approach for a Reactor Head Structure Assembly  

Energy Technology Data Exchange (ETDEWEB)

Korea Atomic Energy Research Institute (KAERI) has been developing the integral reactor. The reactor head structure assembly (RHSA) is the structure installed over the reactor cover. Due to the characteristics of an integral reactor, there are many instrument cables and power cables coming out from the reactor cover and main components. The RHSA provides an interface location to connect these cables from Architecture Engineer (AE) and System Designer (SD). It also prevents a pipe whip and it prohibits instruments from becoming missiles. In this research, the axiomatic design approach for the RHSA is performed.

2006-07-01

244

The use of neutron activation analysis for the study of environmental risks associated with the fly ash from burning Polish coals  

International Nuclear Information System (INIS)

This report presents leaching experiments with irradiated fly ash from the Kozienice Power Station and, as a reference, with a Czechoslovakian fly ash sample. 7 refs, 11 figs, 3 tabs.

1991-09-10

245

Steam turbines for cogeneration plants; Dampfturbinen fuer die Kraft-Waerme-Kopplung  

Energy Technology Data Exchange (ETDEWEB)

The demand for cogeneration plants is growing worldwide. For the combination of electricity generation and heat extraction in power stations facilitates an excellent fuel exploitation and makes the operator of the plant independent from external energy suppliers. (orig.)

2006-07-01

246

Stations Maidanak2  

Science.gov (United States)

Identification of the Ranging System Reference Point (SRP) ... Daylight Filter Type : (SPECTRAL FILTER/FABRY-PEROT/etc) Dayl. Filt. ... INT/etc) Edit Criterion 1st Chain : (ITERATIVE n.n SIGMA/MANUAL/NONE/etc) Edit Criterion 2nd Chain ...

247

Stations Maidanak1  

Science.gov (United States)

Identification of the Ranging System Reference Point (SRP) ... Daylight Filter Type : (SPECTRAL FILTER/FABRY-PEROT/etc) Dayl. Filt. ... INT/etc) Edit Criterion 1st Chain : (ITERATIVE n.n SIGMA/MANUAL/NONE/etc) Edit Criterion 2nd Chain ...

248

Solar Cogeneration Facility: Cimarron River Station, Central Telephone and Utilities-Western Power. Executive summary  

Energy Technology Data Exchange (ETDEWEB)

A brief overview of the conceptual design of a solar central receiver system integrated with an existing cogeneration facility is provided. A synopsis of the performance and economic evaluation, and an assessment of the concept from the site owner's perspective are given.

1981-08-07

249

Sodium sulphur starts to deliver. [High power density battery  

Energy Technology Data Exchange (ETDEWEB)

The development of a high power density sodium sulphur battery with a five-year maintenance-free life is described. These batteries are likely to be used in industrial trucks, milk floats, electric cars, storing power station output and power for satellites. (U.K.).

1985-10-03

250

Priroda module docks with Mir station today - Johnson Space Center ...  

Science.gov (United States)

Apr 26, 1996 ... StainlesssteelJenn-Air cooktop w/4 burners, $20. Sam,332-3168. Sale:Condo, Friendswood,3-2-2A,1411sq It,. 409-925-4862. ...

251

Prematurity as a public health problem: US policy from the 1920s to the 1960s.  

UK PubMed Central (United Kingdom)

During the 1920s and 1930s, a number of physicians created model premature infant stations in select hospitals, arguing that medicine could successfully treat premature infants, most of whom could be...Full Text Available

1996-06-01

252

Potamonautes paecilei  

Science.gov (United States)

... Binya, Banyala; Binya, Equateur; Flandria; Isangila; Kosa-Kosa. Matadi, Mporo River; Stanleypool Station 35, Nsele River; Maniema, ... River; Riv. Talya, Bilboma, kamituga Talya river 2. Matadi, Luashi. I...

253

Physical Basis for the Lg/P Discriminant: General Properties and Preliminary Modeling.  

Science.gov (United States)

A critical problem for reliable implementation of regional discrimination is incomplete understanding of how regional seismic signals depend on physical characteristics of the source and propagation path to the recording station. This research is directed...

1997-01-01

254

Outboard Waterjet Propulsion Development.  

Science.gov (United States)

The project is currently on schedule. The design review meeting was held on 08/26/97 at the Coastal Systems Station in Panama City, Florida. The mechanical arrangement, performance analysis and design features were presented at the review meeting. A numbe...

1997-01-01

255

Operation of Grand Gulf Nuclear Station, Units 1 and 2, Dockets Nos. 50-416 and 50-417: Mississippi Power and Light Company, Middle South Energy, Inc. , South Mississippi Electric Power Association. Final environmental statement  

Energy Technology Data Exchange (ETDEWEB)

The information in this Final Environmental Statement is the second assessment of the environmental impacts associated with the construction and operation of the Grand Gulf Nuclear Station, Units 1 and 2, located on the Mississippi River in Claiborne County, Mississippi. The Draft Environmental Statement was issued in May 1981. The first assessment was the Final Environmental Statement related to construction, which was issued in August 1973 prior to issuance of the Grand Gulf Nuclear Station construction permits. In September 1981 Grand Gulf Unit 1 was 92% complete and Unit 2 was 22% complete. Fuel loading for Unit 1 is scheduled for December 1981. The present assessment is the result of the NRC staff review of the activities associated with the proposed operation of the Station, and includes the staff responses to comments on the Draft Environmental Statement.

1981-09-01

256

Onboard Systems Record Unique Videos of Space Missions - NASA  

Science.gov (United States)

May 1, 2011 ... Onboard Systems Record Unique Videos of Space Missions ... Corporation, An artist's rendering of LCROSS launching toward the Moon .... Station (ISS) as part of the Commercial Orbital Transportation Services program. ...

257

Oettinger pushes for stress tests of Europe'  

Wastenet

... Austrian Environment Minister Nikolaus Berlakovich called for such stress tests on Sunday (13 March) to make sure that nuclear power stations were quake-proof following Japan's massive earthquake and tsunami. Austria, a mountainous country rich in geothermal energy, has no NPPs and no plans to develop ...

258

Northern Indiana Public Service Company Clean Air Act Settlement...  

Science.gov (United States)

retirement of the Dean H. Mitchell Station Installation of three new flue gas desulfurization systems (FGD) at Schahfer 14, Schahfer 15, and Michigan City 12 Upgrades to...

2011-01-19

259

NASA reopens space station job notices - Johnson Space Center  

Science.gov (United States)

Oct 11, 1993 ... Lease: Meadowgreen,3-2.5-2, 2 storyon cuI- ..... also will have the Lunar Landing Training Vehicle elevated over the center of the ...

260

N A S A T'ECHNICAL, - NASA Technical Reports Server  

Science.gov (United States)

Four temperature sensors were provided instead of the previous two sensors. 4. ... Incoming signals from either one or two ground stations at a frequency of .... The propulsion subsystem consists of a single solid-propellant rocket motor. ...

261

Methodology for designing air-quality-monitoring networks. 1. Theoretical aspects  

Energy Technology Data Exchange (ETDEWEB)

An objective methodology is presented for determining the number and disposition of ambient air-quality stations in a monitoring network for the primary purpose of compliance with air-quality standards. The methodology utilizes a data base with real or simulated data from an air quality dispersion model for application with a two-step process for ascertaining the optimal monitoring network. In the first step, the air-quality patterns in the data base are collapsed into a single composite pattern through a figure-of-merit (FOM) concept. The most-desirable locations are ranked and identified using the resultant FOM fields. In the second step the network configuration is determined on the basis of the concept of spheres of influence (SOI) developed from cutoff values of spatial-correlation coefficients between potential monitoring sites and adjacent locations. The minimum number of required stations is then determined by deletion of lower-ranked ...

1986-01-01

262

Measurement and analysis of temperature, strain and stress of foundation mat concrete in nuclear and thermal power stations  

International Nuclear Information System (INIS)

The problems of the thermal stress in concrete structures are roughly divided into the initial stress due to setting heat and the stress due to external temperature after hardening. The initial stress exists in every concrete structure, and it is usually neglected in beams and columns, but it must be taken into account in case of the foundation mat structures in nuclear power stations, for example. In this paper, (1) the results of measurement of temperature, strain and stress in each lift at the time of and after placing concrete in the foundation mat of a nuclear power station and the comparison of them with the results of analysis, (2) the results of measurement of the temperature and stress in a foundation mat, which was carried out to rationalize the design method for the raft type foundation mats in thermal power stations, and (3) the results of examination on the analysis model, external force conditions and boundary ...

263

Mach 4 Performance of Hypersonic Inlet with Rectangular-to ...  

Science.gov (United States)

station in flowmeter used for mass flow calculation. Introduction. THE design .... length (as a result of a less conservative boundary-layer separation criterion), 2) slight ..... ical Flow, AGARD Conference Proceedings, No. 30, 1968. 5Kantrowitz ...

264

How to charge electric-powered automobiles; Volle Ladung, aber wie?  

Energy Technology Data Exchange (ETDEWEB)

Electric cars can be recharged via charging stations, battery exchange, or induction cable lanes in asphalted roads. The users' wishes remain unexplored, so a number of technologies are competing in this sector.

2011-01-15

265

Harnessing the geothermal resources of sedimentary basins for electricity production  

Science.gov (United States)

Use of geothermal resources for generating electricity is briefly analyzed. Results obtained from optimization of the thermodynamic cycle implemented in the secondary coolant circuit of a binary geothermal power station and the parameters of its primary heat carrier circuit are presented.

2011-02-01

266

Expedition crew rotation highlights upcoming shuttle mission  

Science.gov (United States)

Feb 23, 2001 ... Florida, as an F-16 weapons separation engineer with .... new era of space-based research aboard the International Space. Station. ..... the Web at: http://www. aiaa.org/calen- dar/index.hfm?cal=1&cfp=1 ...

267

Electromagnetic fields, pacemakers and defibrillators; Champs electromagnetiques, cardiostimulateurs et defibrillateurs  

Energy Technology Data Exchange (ETDEWEB)

Presentation of electromagnetic sources constituted by various radio transmitters contributing to different radio communication services in the environment. Results of a measures campaign to assess the electromagnetic field in the close neighbourhood of various stations. Analysis by frequency domains. (author)

2004-07-01

268

Electricity generation: options for reduction in carbon emissions  

Energy Technology Data Exchange (ETDEWEB)

Historically, the bulk production of electricity has been achieved by burning fossil fuels, with unavoidable gaseous emissions, including large quantities of carbon dioxide: an average-sized modern coal-burning power station is responsible for more than 10 Mt of CO{sub 2} each year. This paper details typical emissions from present-day power stations and discusses the options for their reduction. Acknowledging that the cuts achieved in the past decade in the UK CO{sub 2} emissions have been achieved largely by fuel switching, the remaining possibilities offered by this method are discussed. Switching to less-polluting fossil fuels will achieve some measure of reduction, but the basic problem of CO{sub 2} emissions continues. Of the alternatives to fossil fuels, only nuclear power represents a zero-carbon large-scale energy source. Unfortunately, public concerns over safety and radioactive waste have still to be assuaged. Other approaches ...

2002-07-01

269

Conawapa to Winnipeg Power Transmission Complex. Southern Receiver System: Environmental impact assessment status report  

International Nuclear Information System (INIS)

Development of the Conawapa-Winnipeg power transmission complex in Manitoba includes five interrelated transmission and conversion facilities. Environmental and socio-economic assessment work done to date on one component of this system (the upgrading of the Southern Receiver System) is described. This system is composed of a network of high voltage transmission lines and station facilities serving power demand in Winnipeg and southern Manitoba. The upgrading involves three main elements: energizing a second 230 kV ac circuit on an existing tower line running from the proposed Riel Station site to the existing St. Vital Station; constructing a new double-circuit 230 kV tower line on the same existing right-of-way between St. Vital and the Riel site area; and installing an additional transformer and other necessary equipment at St. Vital and other stations affected by the upgrade. The environmental ...

1992-01-01

270

Application of a power system stabilizer in the nuclear power plant Borssele  

Energy Technology Data Exchange (ETDEWEB)

After that power fluctuations had occurred at Borssele nuclear power station it was decided to install a power system stabilizer. This stabilizer shall reduce the unwanted power fluctuations. The preliminary research and the results of measurements carried out during commissioning are described. (J.C.R.)

1985-03-01

271

An example of use of SAT for NPP training OJT model  

International Nuclear Information System (INIS)

The non-licensed operator on the job training model presently considered for development and implementation at C.N. Almaraz (CNA) has the primary objective of imparting practical knowledge and skills to the trainee on a per system basis and specific to the job position. This model is somewhat different in scope from the OJT process used in U.S. stations because the learning process is not done on a task per task basis, but rather on the concept of learning collectively all the knowledge and skills required by the specific-system job. This model arose primarily from two thoughts. First, the knowledge and skills have been obtained from a detailed job and task analysis process which will result in the learning of many required knowledge and skills divided by three categories: components, systems and academics. Secondly, the OJT most commonly used in the U.S. requires that the respective station department administers and implements the OJT ...

1994-03-21

272

Transient overpower test E8 on FFTF-type low-power irradiated fuel  

International Nuclear Information System (INIS)

... excursions fftf reactor fuel elements lmfbr type reactors reactivity insertions

1975-06-08

273

Small propulsion reactor design based on particle bed reactor concept  

Science.gov (United States)

In this paper Particle Bed Reactor (PBR) designs are discussed which use /sup 233/U and /sup 242m/Am as fissile materials. A constant total power of 100MW is assumed for all reactors in this study. Three broad aspects of these reactors is discussed. First, possible reactor designs are developed, second physics calculations are outlined and discussed and third mass estimates of the various candidates reactors are made. It is concluded that reactors with a specific mass of 1 kg/MW can be envisioned of /sup 233/U is used and approximately a quarter of this value can be achieved if /sup 242m/Am is used. If this power level is increased by increasing the power density lower specific mass values are achievable. The limit will be determined by uncertainties in the thermal-hydraulic analysis. 5 refs., 5 figs., 6 tabs.

1989-01-01

274

Reduced activation activities  

Energy Technology Data Exchange (ETDEWEB)

Four low activation alloy classes, two austenitic and two ferritic, have been incorporated into the MOTA-1B experiment in the FFTF reactor to provide an early assessment of the suitability of such alloys for reactor service.

1984-01-01

275

Program for personnel protection from oxygen deficiency in a Fast Breeder Reactor Test Facility (FFTF)  

Science.gov (United States)

The FFTF reactor is described. Procedures and equipment used to protect personnel from potential hazards of oxygen deficient environments are described.

1979-12-12

276

Nitride Fuel for Fast Neutron Nuclear Reactors  

International Science & Technology Center (ISTC)

Development of Technology for Producing High-Effective Nitride Fuel UN with Controlled Microstructure for Advanced Fast Neutron Nuclear Reactors

277

MASTER - NASA Technical Reports Server  

Science.gov (United States)

Reactor Effluent Purification System. 7.4.3. Filter Reactor Outlet Gas (FROG). 7.5. Instrumentation and Controls for NSS Tests ...

279

Failure location analysis for tagged reactor assemblies  

Science.gov (United States)

The location of defective LMFBR fuel pins by the determination of gas tag isotopic ratios is discussed. The application of this method to the FFTF Reactor briefly described.

1979-03-01

280

FFTF & Advance Reactors Transition Program Resource Loaded Schedule  

Energy Technology Data Exchange (ETDEWEB)

This document is the annual update of the FFTF and Advanced Reactors Transition Program Resource Loaded Schedule for FY 2002 using current project direction and authorized funding levels

2001-10-25

281

Actinide transmutation in nuclear reactors  

Energy Technology Data Exchange (ETDEWEB)

Of some interest is the comparison between the actinide nuclide burning up (fission) rates such as americium 241, americium 242, curium 244, and neptunium 237, in the reactors with fast or thermal neutron spectra.

1993-12-31

282

Actinide transmutation in nuclear reactors  

International Nuclear Information System (INIS)

Of some interest is the comparison between the actinide nuclide burning up (fission) rates such as americium 241, americium 242, curium 244, and neptunium 237, in the reactors with fast or thermal neutron spectra.

1992-09-14

283

A motor-driven hoisting winch with a safety-braking device  

International Nuclear Information System (INIS)

... brakes reactor charging machines reactors machine parts Int. Cl. B66d5/00;

284

WATER SUPPLY ANALYSIS  

Energy Technology Data Exchange (ETDEWEB)

This analysis defines and evaluates the surface water supply system from the existing J-13 well to the North Portal. This system includes the pipe running from J-13 to a proposed Booster Pump Station at the intersection of H Road and the North Portal access road. Contained herein is an analysis of the proposed Booster Pump Station with a brief description of the system that could be installed to the South Portal and the optional shaft. The tanks that supply the water to the North Portal are sized, and the supply system to the North Portal facilities and up to Topopah Spring North Ramp is defined.

1996-02-06

285

Utilisation and disposal of residues (ash, gypsum and granulate) from BEWAG pulverised coal and fluidised bed fired power stations  

Energy Technology Data Exchange (ETDEWEB)

Describes the wastes produced and the waste disposal methods used at BEWAG power plants. Wastes covered include fly ash, fluidized bed ash, gypsum from flue gas desulfurization and evaporation residues. Disposal methods include using ashes and gypsum to make building materials. Despite many years of experience in the utilization and disposal of residues from coal-fired power stations BEWAG have not encountered any disposal problems. 5 tabs.

1993-01-01

286

The root cause analysis of 9DVN002ZV fan failure in Daya Bay Nuclear Power Station  

International Nuclear Information System (INIS)

Extensive investigations and detailed analysis of the failure reason of 9DVN002ZV fan in Daya Bay Nuclear Power Station showed that the fan destroy was caused by the failure of non-drive end bear. The direct cause of this bearing' failure was its improper assembly caused by improper maintenance procedure, and the root cause was too small internal radial clearance after mounting. The factor affecting bearing internal radial clearance, the relationship between clearance and operating life time and fan failure process were discussed. (authors)

2005-09-01

287

Standard radiation monitoring at Sendai nuclear power station  

International Nuclear Information System (INIS)

Standard radiation monitoring has been conducted at Sendai nuclear power station for the purpose of estimation of 'source activity' during refueling outage and evaluation of countermeasures to reduce dose rate. Selected objects of the monitoring are radiation dose rate at maintenance area, radiation field at each equipment and piping, coolant chemistry and plant operation condition. Monitored data indicates that 'source activity' variation can be estimated to some extent using influential factors, and that evaluation of change of loose crud activity, which is presumed to be represented by the dose rate at letdown heat exchanger, is necessary to further explain change in radiation field at main work area. (author).

288

Solar power station. Sonnenkraftwerk  

Energy Technology Data Exchange (ETDEWEB)

The invention concerns a solar power station with a hollow solar heater, which has reflected radiation coming in, focussed by a mirror through the inlet opening. To match the differing solar radiation during the day, the inlet opening can be adjusted by changing its cross-section. This is done by at least two thick flat circular parts which can move relative to each other which are preferably movable relative to each other in pairs on a common rail and which are cooled by a coolant which is the working medium for absorbing solar energy.

1982-02-25

289

Results of the 2nd periodical inspection of the asphalt solidification facility and the incinerator in Unit 2 of the Sendai Nuclear Power Station  

International Nuclear Information System (INIS)

The 2nd periodical inspection was carried out on the asphalt solidification facility and the incinerator in Unit 2 of the Sendai Nuclear Power Station from November 5 to 28, 1985. Inspection was made in radiation control facility and disposal facility. By external appearance, disassembly, function and performance tests there were observed no abnormalities. The personnel exposure doses during the inspection were below the permissible level. In the inspection, improvement etc. works were not done. (Mori, K.).

1986-01-01

290

Results of regular inspection of No.2 plant in Sendai Nuclear Power Station, Kyushu Electric Power Co., Inc  

International Nuclear Information System (INIS)

The regular inspection of No.2 plant in Sendai Nuclear Power Station was carried out from January 7 to February 8, 1985. The summary of the results of this regular inspection is as follows. The facilities as the object of inspection were radiation control facilities and waste facilities. On these facilities as the object of inspection, the appearance, disassembling, functional, performance and other inspections were carried out, and as the results, abnormality was not found at all. The works related to this regular inspection were accomplished within the range of the allowable radiation dose based on the relevant laws. (Kako, I.).

1986-01-01

291

Replacement of bearing journals on heat transport pumps at the Wolsung nuclear generating station  

International Nuclear Information System (INIS)

The major details of the inspection and replacement of the bearing journals on each of the four heat transport pumps (HTPs) at Wolsung nuclear generating station in Korea are presented in this paper. Investigation following fracture of one of the journals in 1985 revealed that it was excessively hard. The journal material (ASTM A296 CA 40) is considered to be prone to stress corrosion fatigue if the hardness exceeds Rc 40. In 1986 May, during a planned outage, the HTPs were disassembled, the journals were inspected, found to be excessively hard, and all were replaced. At the same time, the pump to motor couplings were all refurbished to ensure proper alignment.

1987-11-22

292

Reducing the breakdowns and energy consumption in pressure regulating stations by rationalizing the heating of gas  

Energy Technology Data Exchange (ETDEWEB)

Sigma 1) examines ways to reduce the number of breakdowns of pressure-regulating stations and to minimize the energy consumed in warming the gas, 2) determines the optimal gas temperatures upstream from the pressure reduction, and 3) shows the dependence of energy consumption upon the water dewpoint. The method of calculating the optimal input temperature relies on Mollier's diagram. Tables and nomographs for natural gas and water dewpoint at 19/sup 0/F and 580 psi (-7/sup 0/C and 4 MPa) are useful in achieving the desired gas temperatures. Heating the regulators' control valves is important.

1982-04-01

293

Probabilistic safety assessment of station blackout accident and 5th emergency diesel in Daya Bay NPP  

International Nuclear Information System (INIS)

In this paper, probabilistic safety assessment (PSA) of the station blackout (SBO) and 5th emergency diesel in Daya Bay NPP has been carried out, the calculation method of non-recover factors of power supplies is given, and sensitivity analysis on the connection duration of 5th emergency diesel has been executed. It is concluded that the core damage frequency (CDF) induced by SBO is relatively large, the addition of 5th emergency diesel is very helpful for the CDF reduction, and the connection duration of this diesel has great effect on the CDF reduction

2004-08-01

294

Power generation growth to triple LNG use  

Energy Technology Data Exchange (ETDEWEB)

Taiwan`s LNG consumption is planned to rise more than threefold over the next four years as medium-term plans to develop power generation facilities increasingly rely on gas-fired combined-cycle stations to avoid the threat of power shortages. State-run Taiwan Power Company (Taipower) expects its LNG consumption to rise from 1.1 mn tonnes in 1996 to 3.4 mn tonnes in the year 2000. By then the first of several gas-fired private power stations is expected to enter service, further increasing Taiwan`s total LNG requirement for power generation. (Author)

1997-11-01

295

NPD Canada's first nuclear power station  

Energy Technology Data Exchange (ETDEWEB)

This talk reviews the history of the Canadian nuclear-electric program highlighting Canada's first nuclear power station, the Nuclear Power Demonstration or NPD. NPD was commissioned and delivered electricity to Canadian consumers for the first time on june 4, 1962. The Canadian nuclear-electric program is based on the CANDU-PHW (Canadian Deuterium Uranium - Pressurized Heavy Water) concept which was conceived between 1955 and 1958 at the Chalk River Nuclear Laboratory (CRNL) of AECL, located a few miles from Deep River. This talk covers the history of the Canadian nuclear-electric activities dating back to 1939.

2002-07-01

296

Leadership, communication and decision making in man-machine systems; Fuehrung, Kommunikation und Entscheidungsfindung in Mensch-Maschine-Systemen  

Energy Technology Data Exchange (ETDEWEB)

The contribution under consideration spans a wide curve from the first deadly accident of motorized aviation in the year 1908 up to newer tendencies of the so-called team resources management on observation points and control stations in order to pursue fundamental questions in man-machine systems. A continuous differentiation in the consideration of the factor human beings in complex technical systems is described. This is illustrated by the example of concepts for leadership, communication and decision making on observation points and control stations.

2008-07-01

297

GT13E gas turbines to power Killingholme A GTCC [gas turbine combined-cycle] plant  

Energy Technology Data Exchange (ETDEWEB)

National Power is building its first gas turbine combined cycle power station at Killingholme, situated to the south of the River Humber in the East of England. NEI ABB Gas Turbines Limited was awarded the turnkey contract in July 1990 to build a nominal 650 MW combined cycle power station based around three Asea Brown Boveri GT13E gas turbines. The project is outlined in this article. The plant is due for completion in July 1993. (author)

1993-01-01

298

Feasibility study on scheme of disposing spent guide tubes at Daya Bay nuclear power plant  

International Nuclear Information System (INIS)

The author describes feasibility study on the scheme of disposing spent guide tubes at Daya Bay nuclear power plant, including scheme selection, packing cask design, disposal operation and technological process, budget estimation and safety evaluation. The research results show that the new scheme is feasible on technology, and reasonable on budget. If the scheme is adopted to dispose the spent guide tubes at Daya Bay nuclear power station, it can not only save large funds, but also accumulate experience on disposing non-compressible low and intermediate level solid radioactive wastes produced at nuclear power station for the country

1998-12-01

299

Electricity supply in Germany  

Energy Technology Data Exchange (ETDEWEB)

Data on various aspects of the electric power industry in Germany is presented in this article. A map of high voltage transmission lines used by the public utilities is included, which indicates the fuel used at each power station. Data on power generated by fuel used from 1991 to 1996 is given, and additional or new capacity for 1995 to 1999 is also noted. Other tables detail capital investment in public utilities energy input by fuel source, power capacity by utility or private power stations by energy source, utility ownership and electricity demand by consumer. (UK)

1997-09-01

300

Electric power production from the biogas resulting of the sewer treatment: pilot project of the Sewer Treatment Station (ETE) in the Barueri city in the Great Sao Paulo; Producao de energia eletrica a partir do biogas resultante do tratamento de esgoto: projeto piloto na E.T.E. de Barueri na Grande Sao Paulo  

Energy Technology Data Exchange (ETDEWEB)

This paper describes a system for biogas conversion to electric power and heat by using a micro turbine and three Otto cycle engines. The benefit of the energy from a treatment process residue aims the improvement of the global performance of the system, reducing the the emission of the greenhouse gases and contributing to the global energetic efficiency of the sewage treatment station and the basic sanitation in Brazil.

2002-07-01

301

Dampers, fluidics and the failsafe fallacy [fire protection  

International Nuclear Information System (INIS)

The fire protection practices adopted at nuclear power stations generally follow the well established principles used throughout industry. Unfortunately, there is one particular area - the interaction with heating, ventilation and air conditioning (HVAC) services - where nuclear power stations pose a seemingly insoluble conflict: that between the need to contain and the need to ventilate. Now, however, solid state fire dampers using power fluidics may promise a solution. One of the key characteristics of a fluidic device is that it is 'solid state', i.e. it has no moving parts. Because of this, its inherent reliability is orders of magnitude greater than a mechanical device. (U.K.).

302

Conservation of power station components during standstill by means of dry air  

International Nuclear Information System (INIS)

The use of pre-dehumidified air having widely established itself as a safe and economical conservation method during the stoppage of steam turbines, it was obvious that this method would be applied also to steam boilers and ancillary aggregates. Experience with the conservation of condensers, prheaters and the water/steam-side of steam boilers in large-scale power stations is reported on. By the example of projects with topical interest, the problems and possibilities of boiler conservation on the firing side are illustrated. The contribution is to stimulate further discussions. (orig.).

303

Comparison and analysis of results of ? radiation level investigation around Daya Bay  

International Nuclear Information System (INIS)

Investigations were carried out of radiation level around Daya Bay for three times since the construction and operation Daya bay Nuclear Power Station and Lingao Nuclear Power Station in Guangdong province in the period of 1988 to 2000. As shown by the investigation, the radiation levels both in the field and indoors remains unchanged by and large but slightly higher than before on the roads. Also this paper gives the analysis of variations in radiation levels form site to site and from time to time. It was shown that, for environmental ? radiation levels measurements, typical measuring sites have significant impact on the meaning results. (authors)

2003-08-01

304

Biotoxicity characterization of a produced-water discharge in Wyoming  

International Nuclear Information System (INIS)

The objectives of this paper are to document the physicochemical and aquatic toxicological quality of a beneficial-use produced-water discharge and its effect on a receiving stream in Wyoming. Fish and water-flea survival, growth, and reproduction tests indicated that the discharge and all other sampling stations passed the state effluent biomonitoring acute toxicity testing endpoints. while benthic macroinvertebrates were absent at the discharge point designated by the Natl. Pollutant Discharge Elimination System (NPDES), productive and reproducing populations were present at all other downstream and mixing-zone stations. This investigation confirmed the validity of the beneficial-use subcategory for this oilfield discharge.

305

Application of power system stabilizer at Bandar-Abbas power station  

Energy Technology Data Exchange (ETDEWEB)

System instability as result of high power generation of one of the largest plants of the Iranian electric power grid prevented the plant to be fully utilized. PSSs were installed on the generating units of the power station, to improve its small signal stability, and enhance the stable generation limit. Domain separation and pole assignment techniques were applied for the PSS design. Several field tests were also carried out to verify its effectiveness. This paper presents the PSS tuning procedure, including the design criteria and some of the field test results.

1994-08-01

306

Accident assessment under emergency situation in Daya Bay nuclear power station  

International Nuclear Information System (INIS)

The accident assessment under emergency situation includes the accident status evaluation and its consequence estimation. This paper introduces evaluation methods for accident status and its assistant computer system (SESAME-GNP) utilized during the emergency situation in Guangdong Daya Bay Nuclear Power Station (GNPS) in detail. At the same time, an improved accident consequence estimation system in GNPS (RACAS-GNP) is briefly described. With the improvement of the accident assessment systems, the capability of emergency response in GNPS is strengthened

2004-05-01

307

A new procedure for cutting out the broken thermocouple tubes inside the deep holes in the tube plate of moisture re-heater at Daya Bay Nuclear Power Station  

International Nuclear Information System (INIS)

The scenario of the development of a new procedure for cutting out the broken protective wells for thermocouples inside the deep holes in the tube plate in the moisture re-heater (MSR) at Daya Bay nuclear power station is presented. Focused in the innovation and improvement of the self-made tools, the new procedure produced an effective method to cut out swing long inserts stuck inside the deep holes. (authors)

2005-09-01

308

Outline of design and construction of civil engineering work for Higashi-Niigata thermoelectric power station No.4 system; Higashiniigata karyoku hatsudensho yongo keiretsu doboku koji no sekkei to seko no gaiyo  

Energy Technology Data Exchange (ETDEWEB)

Tohoku Electric Power Co., Ltd., is now building an LNG-fired No. 4 System (combined cycle of 1.61-million kW) for its Higashi Niigata Thermoelectric Power Station sited in the Niigata East Harbor industrial zone. This is a unit that aims at a thermal efficiency of 50% first in the world by using high-efficiency gas turbines, etc. After the completion of the No. 4 System, the station (No. 1 Machine, No. 2 Machine; No. 3 System, No. 4 System; Harbor No. 1 Machine, Harbor No. 2 Machine) will be generating a total power of 4.6kW, providing the company with its maximum power source which ranks among the largest-grade thermoelectric power stations in this country. Since the construction work was started in April, 1996, approximately 40% had been completed as of March-end, 1997, including foundations for the power station main building, stack, etc. The power station main building uses a ...

1997-07-05

309

Air quality monitoring report for Alberta, 1991  

Energy Technology Data Exchange (ETDEWEB)

In 1991, the air quality monitoring program in Alberta consisted of continuous, intermittent, static, portable, mobile, and acid precipitation monitoring networks. The air quality monitoring networks are described and results from the continuous, intermittent, static, and acid precipitation networks are summarized. Regulations and guidelines for individual pollutants are discussed in detail. Pollutants monitored continuously (1-h average basis) include ammonia, CO, coefficient of haze, H{sub 2}S, nitrogen oxides, ozone, SO{sub 2}, and total hydrocarbons. Good air quality was observed most of the time at all continuous monitoring stations in 1991. The frequency of good air quality ratings ranged from 81% at the Edmonton northwest station to 98% at the Fort McMurray station. Intermittent monitoring (every 6th day) was conducted for total suspended particulates and for vinyl chloride monomers in the Fort Saskatchewan area. ...

1993-08-01

310

Boiling water reactors, pressurized water reactors, supercritical water reactors; Reacteurs a eau bouillante, a eau pressurisee, ou a eau supercritique  

Energy Technology Data Exchange (ETDEWEB)

This article gives an account of the recent development of light water reactors new concepts in the world. Different projects are being studied. The CE80+ from Combustion Engineering (CE) is a 1350 MWe-PWR-type reactor whose primary circuit is confined in a spherical metallic containment. This reactor was certified by NRC (national regulatory commission) in mid-1996. The APWR (advanced pressurized water reactor) is developed by MHI (Mitsubishi heavy industries) in a collaboration with Westinghouse, this PWR-type reactor fitted with 4 loops derived from the SP90 model that was developed by Westinghouse during the eighties. 2 units of ABWR (advanced boiling water reactor) were commissioned in Japan in 1996 and 1997, ABWR was certified by NRC in mid-1996. The BWR90+ is developed by ABB-atom (Sweden) and it represents a cautious advanced version of the BWR75. ...

2001-07-01

311

Large eddy simulation based fire modeling applications for Indian nuclear power plant  

Energy Technology Data Exchange (ETDEWEB)

Full text of publication follows: The Nuclear Power Plants (NPPs) are always designed for the highest level of safety against postulated accidents which may be initiated due to internal or external causes. One of the external/internal causes, which may lead to accident in the reactor and its associated systems, is fire in certain vital areas of the plant. Conventionally, the fire containment approach and/or the fire confinement approach is used in designing the fire protection systems of NPPs. Indian NPPs (PHWRs) follow the combined approach to ensure plant safety and all newly designed plants are required to comply with the provisions of Atomic Energy Regulatory Board (AERB) fire safety Guide. In respect of older plants, the reassessment of adequacy of fire safety provisions in the light of current advances has becomes essential so as to decide upon the steps for retrofitting. Keeping this in mind the deterministic fire hazard analysis was carried out for the ...

2005-07-01

315

Procedure for operating reactors  

International Nuclear Information System (INIS)

The invention concerns a procedure for operating reactors in nuclear power plants. It aims at utilizing power reserves in nuclear power plants. This can be achieved by a steam-side connection of the steam generators of two reactors. The amount of steam exchanged between the units is chosen in such a way that power changes at the steam turbines feedback mainly to the corresponding reactor. In order to realize a high power transfer it is necessary to return the amount of condensate produced in the steam receiving unit and corresponding to the power transferred to the feedwater system of the steam donating unit.

1985-11-11

316

Newly developed control and stop valves  

International Nuclear Information System (INIS)

... bwr type reactors closures fluidic control devices operation performance pwr

318

Instrumentation and control improvements at Experimental Breeder Reactor II  

Energy Technology Data Exchange (ETDEWEB)

The purpose of this paper is to describe instrumentation and control (I C) system improvements at Experimental Breeder Reactor 11 (EBR-11). The improvements are focused on three objectives; to keep the reactor and balance of plant (BOP) I C systems at a high level of reliability, to provide diagnostic systems that can provide accurate information needed for analysis of fuel performance, and to provide systems that will be prototypic of I C systems of the next generation of liquid metal reactor (LMR) plants.

1993-01-01

319

Instrumentation and control improvements at Experimental Breeder Reactor II  

Energy Technology Data Exchange (ETDEWEB)

The purpose of this paper is to describe instrumentation and control (I&C) system improvements at Experimental Breeder Reactor 11 (EBR-11). The improvements are focused on three objectives; to keep the reactor and balance of plant (BOP) I&C systems at a high level of reliability, to provide diagnostic systems that can provide accurate information needed for analysis of fuel performance, and to provide systems that will be prototypic of I&C systems of the next generation of liquid metal reactor (LMR) plants.

1993-03-01

322

Hydroliquefaction of Australian coals - continuous reactor studies on bituminous coals  

Energy Technology Data Exchange (ETDEWEB)

Results of tests on the 1 kg/h continuous reactor for the hydroliquefaction of coal are described. The reactor was operated at 415-435 C and 21 MPa using a continuous stirred reactor with a retention time of about 2 hours. All product oils were recovered by distillation. Sub-bituminous coal was found to give the best product yield. Tests using 5% red mud and 3% improved red mud showed significant increases in oil yield. (4 refs.)

1981-01-01

323

Hydrogen production for better nuclear utilization  

International Nuclear Information System (INIS)

... no. 2) p. 27-28. economics hydrogen power reactors nonmetals (ELEMENTS

1972-08-22

324
325

Fluidic programmer for nuclear engine application  

International Nuclear Information System (INIS)

... fluidic control devices performance reactor control systems space propulsion

326

Fission fragment rockets: A new frontier  

Energy Technology Data Exchange (ETDEWEB)

A new reactor concept is described which would enable fission fragments to be continuously extracted from the reactor. Such a reactor has the potential of enabling extremely energetic and ambitious deep space missions. In this talk the basic physics issues involved in the operation of this type of reactor are outlined, and some possible applications to space exploration are described. 3 refs., 2 figs., 3 tabs.

1989-04-01

327

FFTF driver fuel pellets: typical pellet lot data  

Science.gov (United States)

Quality assurance data for FFTF reactor fuel pellets are presented.

328

FFTF and the ASME Code  

Science.gov (United States)

Photographs are presented of the FFTF reactor facility, components, and some materials.

1978-01-01

331

Determination of reactor kinetic parameters in a two-core reactor  

Energy Technology Data Exchange (ETDEWEB)

The kinetic parameters, ..cap alpha.. the coupling coefficient and tau-bar the mean neutron transit time have been determined using a reactor oscillator on the coupled-core of the Queen Mary College research reactor. By using correlation techniques it has proved possible to use detectors small enough to be inserted in the fuel tanks. It is shown that the simplified Baldwin model with one-group diffusion theory is inadequate to describe the kinetic behaviour and the experimentally-determined parameters are dependent upon the positioning of the detectors.

1982-01-01

332

Computer based training cost-benefit model  

Energy Technology Data Exchange (ETDEWEB)

The costs of establishing a computer-based training program for FFTF reactor operators are analyzed.

1984-01-01

333

Ceramic Composite Materials  

International Science & Technology Center (ISTC)

Development of Ceramic Composite Materials and Structural Elements for High-Temperature Nuclear Reactors

335

Breeder Reactor Program: base technology  

Energy Technology Data Exchange (ETDEWEB)

Nineteen presentation summaries in this meeting proceedings are individually title listed. (LEW)

1981-01-01

337

An experimental plan for improvement of failed fuel monitoring system in CANDU reactor  

Energy Technology Data Exchange (ETDEWEB)

An experimental plan for improving the problems of failed fuel location system in Wolsung Unit-2 reactors was established. It is not possible to make an experiment on the failed fuel monitoring nuclides in the cold laboratories because they have very short half life. Therefore, the experiments can be only carried out at the existing monitoring system under reactor operation. For that reason, an experimental plan was drawn up for installing the radiation detection system on reactor site.

2003-10-01

338

Positive safety features of US nuclear reactors: technical lessons confirmed at Chernobyl. Hearing before the Subcommittee on Energy Research and Production of the Committee on Science and Technology, US House of Representatives, Ninety-Ninth Congress, Second Session, May 14, 1986, No. 138  

Science.gov (United States)

Dr. Rudolf Schulten of West Germany and expert witnesses from national laboratories, utilities, and the nuclear industry testified on reactor safety issues as they relate to the Chernobyl accident and public concern that modern technology has not paid enough attention to public safety. Each of the witnesses contributed safety-related information based on what has been learned from the Soviet incident. Particular focus went to similarities and differences between the Chernobyl and US reactors in safety design and engineering and to the environmental effects of the accident. The N reactor near Richland and a commercial reactor at Fort St. Vrain, Colorado are the only two operating graphite reactors, but neither is a boiling water reactor.

1986-01-01

339

Positive safety features of US nuclear reactors: technical lessons confirmed at Chernobyl. Hearing before the Subcommittee on Energy Research and Production of the Committee on Science and Technology, US House of Representatives, Ninety-Ninth Congress, Second Session, May 14, 1986, No. 138  

International Nuclear Information System (INIS)

Dr. Rudolf Schulten of West Germany and expert witnesses from national laboratories, utilities, and the nuclear industry testified on reactor safety issues as they relate to the Chernobyl accident and public concern that modern technology has not paid enough attention to public safety. Each of the witnesses contributed safety-related information based on what has been learned from the Soviet incident. Particular focus went to similarities and differences between the Chernobyl and US reactors in safety design and engineering and to the environmental effects of the accident. The N reactor near Richland and a commercial reactor at Fort St. Vrain, Colorado are the only two operating graphite reactors, but neither is a boiling water reactor.

340

Recent developments in the design of conceptual fusion reactors  

International Nuclear Information System (INIS)

Since the first round of conceptual fusion reactor designs in 1973 - 1974, there has been considerable progress in design improvement. Two recent tokamak designs of the Wisconsin and Culham groups, with increased plasma beta and wall loading (power density), lead to more compact reactors with easier maintenance. The Reference Theta-Pinch Reactor has undergone considerable upgrading in the design of the first wall insulator and blanket. In addition, a conceptual homopolar energy storage and transfer system has been designed. In the case of the mirror reactor, there are design changes toward improved modular construction and ease of handling, as well as improved direct converters. Conceptual designs of toroidal-multiple-mirror, liner-compression, and reverse-field pinch reactors are also discussed. A design is presented of a toroidal multiple-mirror reactor that ...

341

Preliminary reactor cavity melt dispersal model for direct containment heating scenarios  

Energy Technology Data Exchange (ETDEWEB)

This paper presents the results of a series of experiments performed to study the effect of initial pressure vessel conditions on the extent of melt dispersal from scaled reactor cavities and describes progress in development of a mathematical model which is designed to predict the melt mass dispersed from reactor cavities as a function of reactor vessel initial conditions and on the vessel breach area. The model, which is being developed to also characterize the heat transfer and chemical reaction phenomena which would take place within the reactor cavity, is designed to be incorporated into a lumped-parameter containment analysis computer code.

1989-01-01

342

Nuclear reactor with external structure cooling by natural convection  

International Nuclear Information System (INIS)

The invention concerns an integrated nuclear reactor comprising natural convection cooling of the supporting skirt on which rests the shield closing the reactor vessel. Cooling is achieved by making the air circulate from the bottom to the top around the skirt and removing this air by a stack. The air can be atmospheric air or air taken from the low parts of the reactor. In the latter case, the stack emerges near a metal roof releasing its heat to the atmosphere by radiation, the air then dropping to the low parts. Application to fast nuclear reactors.

343

Leak sealing on ancillary cooling circuits of CANDU reactors  

International Nuclear Information System (INIS)

This paper discusses the remote plugging of leaks in inaccessible pipework, with main reference to small leaks which frequently appear in ancillary cooling water circuits of nuclear reactors. Initially developed to cure problems of the pre-stressed concrete pressure vessels of UK reactors, the ZORIC sealant has been used to repair leaking biological shield pipework on six CANDU reactors. ZORIC is based on a water-soluble epoxy resin and an aqueous suspension of a refined mineral clay. This paper describes the evolution of the sealant, the qualification and testing program, and their application to CANDU reactor systems. 2 refs., 6 figs.

1992-11-22

344

Irradiation studies of fusion reactor materials utilizing FFTF/MOTA  

International Nuclear Information System (INIS)

The most important and difficult part of materials research for fusion reactor is realized to be irradiation studies of fusion reactor materials. Irradiation studies of fusion reactor materials utilizing FFTF/MOTA, as one of Japan/U.S.A. Fusion Collaboration Programs, have important role to establish fundamental understanding of heavy irradiation effects on materials behavior and properties and to develop methods and technologies for advanced irradiation studies under fusion reactor environment. This paper briefly reviews the history, the state of the art, and the future of the FFTF/MOTA program. (author).

345

Paul Scherrer Institut Scientific Report 2001. Volume V: General Energy  

Energy Technology Data Exchange (ETDEWEB)

Major advances in 'Energy and Materials Cycles' have been achieved in the removal of heavy metals from the solid residues of municipal waste incineration. It has been conclusively shown that the oxidation/reduction conditions established during the thermal treatment of filter ash have a decisive influence on the evaporation of groups of heavy metals. With respect to biomass gasification, studies have been carried out with respect to the best way of extracting pure hydrogen from the low calorific value gas that is typically obtained from a biomass gasifier. The overarching goal of the laboratory 'High Temperature Solar Technology' is the use of solar energy for the production of solar fuels, or for the reduction of CO{sub 2} emissions in large scale industrial processes that are conventionally carried out with the use of fossil fuels. In a short-term project targeted at the solar production of lime, highly encouraging results (98% degree of ...

2002-03-01

346

Station blackout induced severe accident analysis for Daya Bay NPP  

International Nuclear Information System (INIS)

In Aug 2002, the National Nuclear Safety Administration of China issued the policy statement for building new nuclear power plants, which requires the probability based safety goal of severe core damage must be lower than 10"-"5/a. The station blackout accident would be possible to cause a severe accident if there were no effective engineering measures to prevent or mitigate the consequences of the accident. By using MELCOR1.8.5 and KORIGEN codes, the present paper has simulated the station blackout accident for Daya Bay Nuclear Power Plant and calculated the source term and radioactivity of main fission products in the containment in the late phase of the accident. CsI is found the main part of aerosol in the containment. The Xe133 and Xe133m start releasing from the containment after its failure, and the upper limit of the amount of released radioactivity is evaluated less than 5.5 x 10"1"5Bq. The total radioactivity of other significant ...

2004-10-04

347

Sea-to-sky airshed ambient quality monitoring report : 1984-2001  

Energy Technology Data Exchange (ETDEWEB)

This report provides information to government and industry to enable decision-making and management of local environmental quality conditions. The need for a summary air quality report has arisen in recent years due to growing concerns about air quality. Increased growth in population and the tourism industry is placing additional pressures on environmental quality. The report summarized meteorological and air quality data collected by the British Columbia Ministry of Water, Land and Air Protection in the Sea-to-Sky airshed from 1984 to 2001. The airshed is located in the Lower Mainland region of British Columbia. Air quality monitoring was conducted for various periods at 18 different stations and meteorological monitoring was conducted at 4 locations. A list of both provincial and national air quality objectives and standards was provided, with definitions and reference levels from the Canadian Environmental Protection Act. Meteorological data was presented on a ...

2004-09-01

348

Results of a cross-sectional study on the association of electromagnetic fields emitted from mobile phone base stations and health complaints; Ergebnisse einer Querschnittsstudie zum Zusammenhang von elektromagnetischen Feldern von Mobilfunksendeanlagen und unspezifischen gesundheitlichen Beschwerden  

Energy Technology Data Exchange (ETDEWEB)

Background: Despite the fact that adverse health effects are not confirmed for exposure to radiofrequency electromagnetic field (RFEMF) levels below the limit values, as defined in the guidelines of the International Commission on Non-Ionizing Radiation Protection, many persons are worried about possible adverse health effects caused by the RF-EMF emitted from mobile phone base stations, or they attribute their unspecific health complaints like headache or sleep disturbances to these fields. Method: In the framework of a cross-sectional study a questionnaire was sent to 4150 persons living in predominantly urban areas. Participants were asked whether base stations affected their health. Health complaints were measured with standardized health questionnaires for sleep disturbances, headache, health complaints and mental and physical health. 3,526 persons responded (85%) to the questionnaire and 1,808 (51%) agreed to dosimetric measurements in ...

2010-07-01

349

Initial results of the CD-1 reliable multicast experiment  

Energy Technology Data Exchange (ETDEWEB)

During the past year, an experiment has been underway to test use of reliable multicast capabilities for transmission of continuous data in the Global Communication Infrastructure. For the experiment a version of the CD-1 protocol was multicast enabled. The experiment has demonstrated the feasibility of transmitting data in a multicast mode over the GCI. In the case of the Comprehensive Nuclear Test-Ban Treaty the sender could be the station and the receivers the International Data Center (IDC) and one or more National Data Centers (NDC). The potential advantages of multicasting include (a) the timely receipt of the data by the IDC and the host NDC and (b) the simultaneous availability of the raw station data at, at least, two locations. The latter, by introducing redundant data paths, decreases the probability of loss of station data due to a potential failure of a single data receiver. This experiment is only one element ...

2000-09-29

350

Collective effective dose equivalent, population doses and risk estimates from occupational exposures in Japan  

Energy Technology Data Exchange (ETDEWEB)

Collective dose equivalent and population dose from occupational exposures in Japan, 1988 were estimated on the basis of a nationwide survey. The survey was conducted on annual collective dose equivalents by sex, age group and type of radiation work for about 0.21 million workers except for the workers in nuclear power stations. The data on the workers in nuclear power stations were obtained from the official report of the Japan Nuclear Safety Commission. The total number of workers including nuclear power stations was estimated to be about 0.26 million. Radiation works were subdivided as follows: medical works including dental; non-atomic energy industry; research and education; atomic energy industry and nuclear power station. For the determination of effective dose equivalent and population dose, organ or tissue doses were measured with a phantom experiment. The resultant doses were compared with the ...

1993-05-01

351

Collective effective dose equivalent, population doses and risk estimates from occupational exposures in Japan  

International Nuclear Information System (INIS)

Collective dose equivalent and population dose from occupational exposures in Japan, 1988 were estimated on the basis of a nationwide survey. The survey was conducted on annual collective dose equivalents by sex, age group and type of radiation work for about 0.21 million workers except for the workers in nuclear power stations. The data on the workers in nuclear power stations were obtained from the official report of the Japan Nuclear Safety Commission. The total number of workers including nuclear power stations was estimated to be about 0.26 million. Radiation works were subdivided as follows: medical works including dental; non-atomic energy industry; research and education; atomic energy industry and nuclear power station. For the determination of effective dose equivalent and population dose, organ or tissue doses were measured with a phantom experiment. The resultant doses were compared with the ...

1993-01-01

352

Assessment of RELAP5 model for the University of Massachusetts Lowell research reactor  

International Nuclear Information System (INIS)

RELAP5 (Reactor Excursion and Leak Analysis Program) is a system code developed at the Idaho National Environmental and Engineering Laboratory for thermal hydraulic analysis of nuclear reactors. The code RELAP5 is widely used for safety analysis studies of commercial nuclear power plants. However, recent released version of RELAP5/3.2 and over present significant capabilities for analysis of nuclear reactor research systems. As a contribution to the assessment of RELAP5/3.3 for research reactor safety analysis, experimental data from the University of Massachusetts Lowell Research Reactor UMLRR are used. The UMLRR is a 1 MW, light water moderated and cooled, graphite-reflected, open-pool type research reactor. This paper presents the development and the validation of a UMLRR-RELAP model using experimental data. For this purpose, a series of experiments were ...

353

Wood-gas / natural-gas combined-cycle power station for Switzerland - Potential and estimation of financial viability; Holzgas/Erdgas-Kombikraftwerk fuer die Schweiz: Potenzial und Wirtschaftlichkeitsabschaetzung. Input-Papier fuer die Stromangebots-Perspektiven 2035 des Bundesamts fuer Energie  

Energy Technology Data Exchange (ETDEWEB)

This paper was produced as an input to the Swiss Confederation's 'Electricity Perspectives 2035' study made by the Swiss Federal Office of Energy (SFOE). A concept for the combined use of wood and natural gas in a combined-cycle power station is presented. The gasification of wood to provide fuel for the gas turbines and waste-heat boilers of such power stations is proposed as an alternative to just burning wood to provide heat for steam generators. Figures are quoted on the quantities of biomass and wood usable for energy applications in Switzerland. The energetic and financial efficiencies of wood-powered generation of heat and electricity are examined, as are the investments necessary and the costs incurred. Comparisons are presented between wood from forests, sawmill-wastes, scrap wood and natural gas as fuels.

2005-07-01

354

Wire pad chamber for LHCb muon system  

CERN Document Server

2000-003 Wire pad chambers (WPC) have been proposed for the outer Region 4 of the LHCb Muon System. These are double gap MWPCs with small wire spacing allowing to obtain 99% detection efficiency in a 20 ns time window. The chambers have a rectangular shape with the vertical dimension from 20 cm in Station 1 to 30 cm in Station 5. The horizontal dimensions will be different with the maximal size of 3 meters in Station 5. The wires are in the vertical direction. The short wire length allows to use small wire spacing needed for high time resolution. Also, this helps to obtain the uniform gas gain over the whole chamber area. The WPC has one row of the wire pads formed by grouping wires in separate readout channels. Four WPC prototypes have been built at PNPI and tested in the PS beam at CERN. Here we report on the results from these tests. Also, the results of simulation of the WPC performance are presented.

2000-01-01

355

Straw-fuelled heating power stations in Denmark; Strohheizkraftwerke in Daenemark  

Energy Technology Data Exchange (ETDEWEB)

During the past 15 years, 60 straw-fuelled and 25 wood-fuelled district heating stations were commissioned in Denmark, as well as 6 biomass-fuelled heating power stations. All of these plants are equipped with high-pressure boilers, heat exchangers for district heating, and steam turbines with generators. Today, 5 percent of the total energy consumed is provided by biomass fuels. With the new taxes on carbon dioxide emissions and measures to promote renewable energy sources, a 15 percent share can be expected soon. (orig/SR) [Deutsch] In Daenemark wurden in den letzten 15 Jahren 60 strohbefeuerte und 25 holzbefeuerte Fernwaermewerke in Betrieb genommen. Dazu sind in den letzten Jahren 6 biomassebefeuerte Heizkraftwerke gekommen. Alle Anlagen haben Hochdruckkessel, Waermetauscher fuer Fernwaerme und Dampfturbinen mit Generatoren. Heute werden in Daenemark 15 Prozent des Energieverbrauchs mit Biomasse gedeckt. Durch Besteuerung der ...

1996-12-31

356

Seabrook Station Level 2 PRA Update to Include Accident Management  

Science.gov (United States)

A ground-breaking study was recently completed as part of the Seabrook Level 2 PRA update. This study updates the post-core damage phenomena to be consistent with the most recent information and includes accident management activities that should be modeled in the Level 2 PRA. Overall, the result is a Level 2 PRA that fully meets the requirements of the ASME PRA Standard with respect to modeling accident management in the LERF assessment and NRC requirements in Regulatory Guide 1.174 for considering late containment failures. This technical paper deals only with the incorporation of operator actions into the Level 2 PRA based on a comprehensive study of the Seabrook Station accident response procedures and guidance. The paper describes the process used to identify the key operator actions that can influence the Level 2 PRA results and the development of success criteria for these key operator actions. This addresses a key requirement of the ASME PRA Standard for ...

2006-07-01

357

Seabrook Station Level 2 PRA Update to Include Accident Management  

International Nuclear Information System (INIS)

A ground-breaking study was recently completed as part of the Seabrook Level 2 PRA update. This study updates the post-core damage phenomena to be consistent with the most recent information and includes accident management activities that should be modeled in the Level 2 PRA. Overall, the result is a Level 2 PRA that fully meets the requirements of the ASME PRA Standard with respect to modeling accident management in the LERF assessment and NRC requirements in Regulatory Guide 1.174 for considering late containment failures. This technical paper deals only with the incorporation of operator actions into the Level 2 PRA based on a comprehensive study of the Seabrook Station accident response procedures and guidance. The paper describes the process used to identify the key operator actions that can influence the Level 2 PRA results and the development of success criteria for these key operator actions. This addresses a key requirement of the ASME PRA Standard for ...

2006-06-04

358

Scaling Laws and Design Principles for Multi-Cellular Wireless OFDMA Systems  

CERN Document Server

In this paper, we consider the downlink of large-scale multi-cellular OFDMA-based networks and study performance bounds of the system as a function of the number of users $K$, the number of base-stations $B$, and the number of resource-blocks $N$. Here, a resource block is a collection of subcarriers such that all such collections, that are disjoint have associated independently fading channels. We derive novel upper and lower bounds on the sum-utility for a general spatial geometry of base stations, a truncated path loss model, and a variety of fading models (Rayleigh, Nakagami-$m$, Weibull, and LogNormal). We also establish the associated scaling laws and show that, in the special case of fixed number of resource blocks, a grid-based network of base stations, and Rayleigh-fading channels, the sum information capacity of the system scales as $\\Theta(B \\log\\log K/B)$ for extended networks, and as $O(B \\log\\log K)$ and ...

2011-01-01

359

Preliminary study of the effect of pumped-storage plant operation on zooplankton  

Energy Technology Data Exchange (ETDEWEB)

The hydromechanical effect of hydroelectric stations on zooplankton is customarily regarded as a constantly acting and comparatively harmless factor, since its destruction is inevitable when water masses are passed through hydroelectric stations, but its capacity for restoration is high (i.e., destruction of the zooplankton of the forebay is compensated by its production in the after bay). It is not known how correct such an opinion is, or what is the true balance of losses and reproduction of zooplankton in the forebays and after bays of hydroelectric stations. However, hydroelectric plants of a new type, pumped-storage plants, have been constructed in recent years and others are planned for the Dnieper reservoirs. The operational principle and purpose of these plants is that they employ special vertical turbine-electric pumps that pump water at night from the reservoirs into pumped-storage facilities at high levels, and ...

1980-01-01

360

Physical research of microgravity influence on physical phenomenon in cryogenic liquids and general-purpose onboard cryogenic facility for realization of this research aboard International Space Station  

International Nuclear Information System (INIS)

The united research plan named 'Boiling' is created on the basis of several cryogenic research projects developed by experts in Russia and Ukraine for International Space Station. The 'Boiling' plan includes 8 first experiments aimed at investigating the influence of microgravity on boiling processes, heat transfer and hydrodynamics in liquid helium being either under normal or superfluid conditions. The experiments are supposed to be carried out with individual cells collected inside a single cryogenic onboard experimental facility. The international research program experiments are characterized by the following features: utilization of several artificially simulated microgravity levels, owing to rotation of the experimental helium cryostat; visualization of the processes that occur in liquid helium; research of boiling and hydrodynamics both in a large volume of stationary liquid, and in a liquid flow running through a channel. Upon completion of the 'Boiling' ...

2003-06-01

361

Optimization of maintenance programme at Daya Bay Nuclear Power Station based on RCM analysis results  

International Nuclear Information System (INIS)

This paper begins with an introduction to Guangdong Daya Bay Nuclear Power Station (GNPS) and gives a simple introduction to the operations and maintenance documentation system at GNPS. It then will review the maintenance program guidelines base and the associated problems prior to the application of reliability centered maintenance (RCM). How RCM was implemented at GNPS, how the results of RCM analysis were used to optimize the maintenance program and test program, and what is the interface between RCM and the existing maintenance program will be shown. Next, it will show the successful implementation of RCM at GNPS resulted in the following changes: A new understanding of equipment failure challenges operations and maintenance beliefs, maintenance concepts undergo a large change, maintenance program and periodic testing program are continuously modified and optimized, new on-condition maintenance technologies are introduced, non-productive scheduled overhauls are ...

2003-12-01

362

Mid-latitude scintillation model. Technical report, 1 November 1985-31 October 1986  

Energy Technology Data Exchange (ETDEWEB)

Radiowave scintillation in the presence of ionospheric disturbances has the potential to disrupt numerous transionospheric radio and radar systems. This report describes development of a model characterizing the plasma density irregularities that produce scintillation in the naturally disturbed mid-latitude F layer. The model will be incorporated into Program WBMOD, which includes subroutines for computing both link geometry and scintillation indices, the latter by means of phase screen diffraction theory. Earlier versions of WBMOD, were based on extensive analysis of scintillation data collected in the auroral and equatorial zones in Wideband Satellite Mission. The model described herein is based on similarly extensive analysis of Wideband data from one mid latitude station and of data collected from HiLat satellite at another mid latitude station. The model describes irregularities at an effective height of 350 km that are isotropic across ...

1986-10-31

363

Localization explore of electrical and I and C equipments in Daya Bay Nuclear Power Station  

International Nuclear Information System (INIS)

The supply of electronic instrumentation and controlling (I and C) equipments in Daya Bay Nuclear Power Station depends on importation up to now, however, reliable supply of spare parts is presently threatened by many factors. Consequently, Daya Bay Nuclear Power Station tries to localize these equipments. According to a survey, China has possessed the ability to undertake the research, development and production of the I and C system in nuclear power independently. We propose that localization should firstly starts with the production of replacement board and parts for analogical I and C system, gradually leads to the substitution of system cabinet units, and finally realize the independent research, development and production of advanced digital main control system. A series of prominent problems of producing nuclear grade I and C equipments are focused on the designing, manufacturing, testing and reliability evaluation. In this paper, ...

2007-10-01

364

Dynamic load in suppression pool during BWR main steam safety relief valve actuation  

International Nuclear Information System (INIS)

BWRs are so designed that the exhaust steam from main steam safety relief valves is led to pressure suppression pools, and the steam is condensed in pool water, but at this time, dynamic load seems to arise in the pool water. In Tokai No. 2 Power Station, a Mark-2 containment vessel was adopted to improve the reliability as much as possible and to obtain the design with margin. In this report, the result of actual machine test in Tokai No. 2 Power Station and the method of reducing the load are described. When a relief valve works, the discharge of water in exhaust pipes into a suppression pool, the exhaust of air in exhaust pipes and repeated expansion and contraction of bubbles in pool water, and the exhaust of steam and condensation occur. As for the construction of the suppression pool in Tokai No. 2 Power Station, cross-shaped quencher and the structure with jet deflector were installed. The test plan and the test ...

1979-01-01

365

Daya Bay Nuclear Power Station five-year business plan and operating results  

International Nuclear Information System (INIS)

Guangdong Nuclear Power Joint Venture Company, Ltd. first 5-Year Business Plan (hereinafter referred to as 5-Year Business Plan) serves as guidance of both the operations and management of the company. Continuous performance improvement of the nuclear power station has been achieved through the fulfillment of goals and improvement plan defined by the 5-Year Business Plan, and through standard and systematic management. Daya Bay Nuclear Power Station (GNPS) has made great contributions to sustainable economic developments of both Guangdong and Hong Kong since its commercial operation in 1994. As of the end of 1999, the cumulative off-take electricity generated by GNPS had reached 69.9 billion kWh. Of the WANO indicators universally applied by nuclear power industry throughout the world, 6 indicators of Daya Bay performance entered the world top quartile while 9 the medium level

2000-12-05

366

Cogeneration process for small and medium-sized industrial plants; CO-Generation-Process fuer kleinere und mittlere Industrieanlagen  

Energy Technology Data Exchange (ETDEWEB)

Industrial companies are being forced by increasingly restrictive environmental legislation to implement power station technology which is environmentally compatible and which conserves scarce resources. Gas and steam turbine power stations have been causing a sensation in this field for some time. This article gives an introduction to gas and steam turbine power stations in the 4 MW to 30 MW size range. The designs of the plants described here not only provide for electricity generation by gas and steam turbines however, but also designs specific to particular companies for process steam and district heating supply. (orig.) [Deutsch] Durch immer restriktivere Umweltschutzgesetze werden die Industrieunternehmen zu einer umwelt- und ressourcenschonenden Kraftwerkstechnik gedraengt. Auf diesem Gebiet sorgen nun seit geraumer Zeit GuD-Kraftwerke fuer Furore. In diesem Beitrag werden GuD-Kraftwerke in einer Groessenordnung ...

1993-12-31

367

Breakdowns of high-voltage transmission lines due to sea-salt deposits on insulators  

Energy Technology Data Exchange (ETDEWEB)

Until 1990, in Tuscany, salt pollution of anti-salt insulators installed on high-tension transmission lines had led to rare breakdowns. On the contrary, in the last months of 1990, in most of Tuscany, following a strong libeccio wind coming from the Tyrrhenian Sea, and due to a long period of drought, salt deposits accumulated on the insulators of the high-voltage transmission lines (380 kV, 220 kV and 132 kV). This phenomenon not only took place in the coastal areas near Livorno, Pisa and Grosseto, but also in areas far away from the sea such as Florence, Prato, Arezzo and Siena. Following this, several high-tension lines, and whole sections of 380 kV electric stations went out of order, damaging the stations' equipment, insulators on the lines, and in particular porcelain insulators. The maintenance operations that were immediately undertaken consisted in washing operations, first focussed on stations, and then ...

1992-03-01

368

Breakdowns of high-voltage transmission lines due to sea-salt deposits on insulators  

International Nuclear Information System (INIS)

Until 1990, in Tuscany, salt pollution of anti-salt insulators installed on high-tension transmission lines had led to rare breakdowns. On the contrary, in the last months of 1990, in most of Tuscany, following a strong libeccio wind coming from the Tyrrhenian Sea, and due to a long period of drought, salt deposits accumulated on the insulators of the high-voltage transmission lines (380 kV, 220 kV and 132 kV). This phenomenon not only took place in the coastal areas near Livorno, Pisa and Grosseto, but also in areas far away from the sea such as Florence, Prato, Arezzo and Siena. Following this, several high-tension lines, and whole sections of 380 kV electric stations went out of order, damaging the stations' equipment, insulators on the lines, and in particular porcelain insulators. The maintenance operations that were immediately undertaken consisted in washing operations, first focussed on stations, and then on lines. ...

1992-01-01

369

Aerial radiological survey of the Grand Gulf Nuclear Station and surrounding area, Port Gibson, Mississippi. Date of survey: March 1982  

International Nuclear Information System (INIS)

An aerial radiological survey was performed from 11 to 20 March 1982 over a 260-square-kilometer area centered on the Grand Gulf Nuclear Station at Port Gibson, Mississippi (the station was not yet in operation at the time of the survey). All gamma ray data were collected by flying east-west lines spaced 152 meters apart at an altitude 91 meters above ground level. Processed data showed that all gamma rays detected within the survey area were those expected from naturally occurring terrestrial background emitters. Count rates obtained from the aerial platform were converted to exposure rates at 1 meter above the ground and are presented in the form of an isoradiation contour map. The observed exposure rates were between 5 and 13 microroentgens per hour (#mu#R/h), with most of the area ranging from 9 to 10 #mu#R/h. These values include an estimated cosmic ray contribution of 3.6 #mu#R/h. The exposure rate obtained from soil samples and ...

370

A microcontroller-based data-acquisition system for meteorological station monitoring  

International Nuclear Information System (INIS)

This paper presents a study of feasibility of different existing methodologies linked to field's data acquisition from remote meteorological stations. The data transmission serves to collect field's meteorological information, such as temperature, humidity and radiation. In our study the experimental data is registered in a weather station located about 100 km from University of Almeria. Various existing techniques are studied, especially Radio, GSM (global system of mobile communication) and GPRS (general packet radio service). In the result of these studies has been designed a system of field's data acquisition (herein referred as Meteologger) which we are going to present in this paper. The system is based on an ATmega 16 microcontroller, which scans 8 sensors together at any programmable intervals. This paper presents the study of the mentioned project, application and some main characteristics of the prototype system and its program. We ...

2008-12-01

371

United States Domestic Research Reactor Infrastrucutre TRIGA Reactor Fuel Support  

Energy Technology Data Exchange (ETDEWEB)

The United State Domestic Research Reactor Infrastructure Program at the Idaho National Laboratory manages and provides project management, technical, quality engineering, quality inspection and nuclear material support for the United States Department of Energy sponsored University Reactor Fuels Program. This program provides fresh, unirradiated nuclear fuel to Domestic University Research Reactor Facilities and is responsible for the return of the DOE-owned, irradiated nuclear fuel over the life of the program. This presentation will introduce the program management team, the universities supported by the program, the status of the program and focus on the return process of irradiated nuclear fuel for long term storage at DOE managed receipt facilities. It will include lessons learned from research reactor facilities that have successfully shipped spent fuel elements to DOE receipt facilities.

2011-03-01

372

Transuranium isotopes production and their effect on the three-dimensional core calculation  

Energy Technology Data Exchange (ETDEWEB)

The operation of a nuclear power reactor necessarily implies the consumption or burnup of reactor fuel by fission and capture, which gives rise to a decrease in the reactivity of the reactor. The effect of americium formation on the criticality of a thermal power reactor using two types of fuel is studied. The three-dimensional core calculation is used to calculate the production of the transuranium isotopes and their effect on the effective multiplication factor (K[sub eff]). This effect cannot be neglected for thermal power reactors with UO[sub 2]-PuO[sub 2] fuel (3.11% after 70 weeks of operation). The effect of the transuranium isotopes on the K[sub eff] for a thermal power reactor with UO[sub 2] fuel is about 0.0018% and can be ignored. (author).

1993-02-01

373

Transuranium isotopes production and their effect on the three-dimensional core calculation  

International Nuclear Information System (INIS)

The operation of a nuclear power reactor necessarily implies the consumption or burnup of reactor fuel by fission and capture, which gives rise to a decrease in the reactivity of the reactor. The effect of americium formation on the criticality of a thermal power reactor using two types of fuel is studied. The three-dimensional core calculation is used to calculate the production of the transuranium isotopes and their effect on the effective multiplication factor (K_e_f_f). This effect cannot be neglected for thermal power reactors with UO_2-PuO_2 fuel (3.11% after 70 weeks of operation). The effect of the transuranium isotopes on the K_e_f_f for a thermal power reactor with UO_2 fuel is about 0.0018% and can be ignored. (author).

374

The explosion reason analysis of urea reactor of Pingyin  

British Library Electronic Table of Contents (United Kingdom)

In allusion to the explosion of a urea reactor took place in a fertilizer plant at Pingyin, Shandong, China, a series of evidence collection and inspection jobs which includes collecting operation condition and parameters, sampling the explosion fracture, reactor body apart from explosion fracture, and leak detection medium and its hangover, etc., had been carried out firstly. Based on these jobs, farther analysis and computation work has been done to the structural and materials characteristics and the operation condition of the urea reactor, including compositions, metallographic phases, tensile properties, impact energy, strain ageing characteristics, and fracture toughness of the urea reactor steels, the compositions of leak detection medium and its hangover in the urea reactor, and ex...

2009-01-01

375

The advanced MAPLE reactor concept  

International Nuclear Information System (INIS)

High-flux neutron sources are continuing to be of interest both in Canada and internationally to support materials testing for advanced power reactors, new developments in extracted-neutron-beam applications, and commercial production of selected radioisotopes. The advanced MAPLE reactor concept has been developed to meet these needs. The advanced MAPLE reactor is a new tank-type D_2O reactor that uses rodded low-enrichment uranium fuel in a compact annular core to generate peak thermal-neutron fluxes of 1 x 10"1"9 n#centre dot#s"-"1 in a central irradiation rig with a thermal power output of 50 MW. Capital and incremental development costs are minimized by using MAPLE reactor technology to the greatest extent practicable.

1985-10-14

376

Status report on the fusion breeder  

Energy Technology Data Exchange (ETDEWEB)

The rationale for hybrid fusion-fission reactors is the production of fissile fuel for fission reactors. A new class of reactor, the fission-suppressed hybrid promises unusually good safety features as well as the ability to support 25 light-water reactors of the same nuclear power rating, or even more high-conversion-ratio reactors such as the heavy-water type. One 4000-MW nuclear hybrid can produce 7200 kg of /sup 233/U per year. To obtain good economics, injector efficiency times plasma gain (eta/sub i/Q) should be greater than 2, the wall load should be greater than 1 MW m/sup -2/, and the hybrid should cost less than 6 times the cost of a light-water reactor. Introduction rates for the fission-suppressed hybrid are unusually rapid.

1980-12-12

377

Space reactor fuel element testing in upgraded TREAT  

Energy Technology Data Exchange (ETDEWEB)

The testing of candidate fuel elements at prototypic operating conditions with respect to temperature, power density, hydrogen coolant flow rate, etc., a crucial component in the development and qualification of nuclear rocket engines based on the Particle Bed Reactor (PBR), NERVA-derivative, and other concepts. Such testing may be performed at existing reactors, or at new facilities. A scoping study has been performed to assess the feasibility of testing PBR based fuel elements at the TREAT reactor. initial results suggest that full-scale PBR, elements could be tested at an average energy deposition of {approximately}60--80 MW-s/L in the current TREAT reactor. If the TREAT reactor was upgraded to include fuel elements with a higher temperature limit, average energy deposition of {approximately}100 MW/L may be achievable.

1993-05-01

378

Review of SCDAP/RELAP5 Code Application to severe accident analysis of CANDU Reactors  

International Nuclear Information System (INIS)

SCDAP/RELAP5 code has been developed in US for best-estimate simulation of light water reactors transients during nuclear accidents. The code models the coupled behaviour of the cooling system, reactor core and fission products release during the accident. It is the result of the coupling between RELAP5, modelling thermal hydraulic, control system, reactor kinetics and the transport of noncondensable gases, and SCDAP code modelling the behaviour of the reactor core during severe accidents. The paper briefly presents the application of SCDAP/RELAP5 code to CANDU severe accident analysis. Also, the paper proposes a summary of the needs for development that could enhance the quality of the severe accidents related predictions in CANDU reactors. (authors)

2009-10-12

379

Research and development on next generation reactor (phase I)  

Energy Technology Data Exchange (ETDEWEB)

The objective of the study is to improve the volume of nuclear power plant which adopts passive safety system concept. The passive safety system reactor is characterized by excellent safety and reliability. But the volume of NSSS (Nuclear Steam Supply System) of the passive safety system reactor is so small that it should be upgraded for commercial operation. For volume upgrade, detailed analyses are performed as follows; core design, hydraulics, design and mechnical structures, and safety analysis. In addition to above analysis, some investigations must be supplied as follows: power density vs. DNB margin decrease, outlet temperature vs. EPRI-URD, additional tests for upgraded reactor, dynamic analysis of mechanical vibration according to expanded reactor vessel and expanded in-core structures, and Merit loss of passive safety system reactor according to design margin decrease. ...

1994-10-01

380

Radioactive waste disposal for fission and fusion reactors  

Energy Technology Data Exchange (ETDEWEB)

The calculated radioactive waste inventories of the Turkey Point pressurized water fission reactor (PWR) and the Starfire conceptual fusion tokamak are compared as a function of time from initial start-up to 10,000 years after decommissioning. Only material out of reactor at least one year is considered. The total activity in Ci/W(th) of the Starfire tokamak is slightly greater than that of the PWR during the active lifetimes of the two reactors and beyond 1000 years. However, using reduced activation materials in Starfire can result in about 1/2000 as much long-lived radioactivity as in the fission reactor. It is stressed that comparison of wastes on this basis is not straightforward, since the radioisotopes and methods required for their disposal are different for fusion and fission reactors. 2 refs., 1 fig., 2 tabs.

1989-01-01

381

MOVPE growth of GaAs and InP based compounds in production reactors using TBAs and TBP  

Energy Technology Data Exchange (ETDEWEB)

Today TBP and TBAs are the compounds which have the highest potential to replace the hydrides arsine and phosphine in the MOVPE process. The authors have demonstrated the entire material system Ga-In-As-P can be grown without any loss of quality using TBP and TBAs not only in one reactor, but in a complete family of reactors. These reactors range from small-scale single wafer R and D reactors to multiwafer Planetary Reactor systems. Both InP based and GaAs based materials could be grown with an excellent quality. Thus all growth processes for III-V devices--long and short wavelength lasers, LEDs, high speed transistors, etc.--can be switched to TBP and TBAs. This will drastically reduce safety hazards and lead to processes that have advantages both from the ecological and economical point of view.

1996-12-31

382

Liquid metal reactor cover gas purification and analysis in the USA  

International Nuclear Information System (INIS)

Two sodium cooled reactors are currently being operated in the United States of America for the US Department of Energy. These are Experimental Breeder Reactor 11, EBR-11, and the Fast Flux Test Facility, FFTF. EBR-11 is located near Idaho Falls, Idaho, and the FFTF is near Richland, Washington. These reactors are currently engaged in a wide range of testing including fuels and materials tests, and plant system performance and safety development. The US DOE program also includes designs of a next generation sodium cooled power reactor. The FFTF and EBR-11 communities are providing input to these designs. This paper discusses the efforts to develop and operate cover gas systems for the sodium cooled nuclear reactor program in the USA.

1986-09-24

383

Laser application in the fabrication of gas-tagged capsules. A leak detection system  

Energy Technology Data Exchange (ETDEWEB)

Encapsulation of a unique isotopic blend of krypton and xenon gas employs a special application of laser technology. The encapsulated gas is then used as the primary medium for detection and identification of failed nuclear fuel rods. The use of gas tagging as a means of detecting and identifying failed nuclear fuel rods has been successfully demonstrated and used by the Argonne National Laboratory, Experimental Breeder Reactor (EBR-2) Project, and the Westinghouse Hanford Company (WHC), Fast Flux Test Facility (FFTF) Fast Breeder Reactor Program. The Power Reactor and Nuclear Fuel Development Corporation (PNC) of Japan has selected this leak detection system for use in their MONJU Prototype Reactor fuel assemblies. The MONJU reactor is almost identical in design to the highly successful FFTF reactor, which is currently in standby status.

1993-12-01

384

Five years operating experience at the Fast Flux Test Facility  

Energy Technology Data Exchange (ETDEWEB)

The Fast Flux Test Facility (FFTF) is a 400 Mw(t), loop-type, sodium-cooled, fast neutron reactor. It is operated by the Westinghouse Hanford Company for the United States Department of Energy at Richland, Washington. The FFTF is a multipurpose test reactor used to irradiate fuels and materials for programs such as Liquid Metal Reactor (LMR) research, fusion research, space power systems, isotope production and international research. FFTF is also used for testing concepts to be used in Advanced Reactors which will be designed to maximize passive safety features and not require complex shutdown systems to assure safe shutdown and heat removal. The FFTF also provides experience in the operation and maintenance of a reactor having prototypic components and systems typical of large LMR (LMFBR) power plants. The 5 year operational performance of the FFTF reactor is ...

1987-04-01

385

Five years operating experience at the Fast Flux Test Facility  

International Nuclear Information System (INIS)

The Fast Flux Test Facility (FFTF) is a 400 Mw(t), loop-type, sodium-cooled, fast neutron reactor. It is operated by the Westinghouse Hanford Company for the United States Department of Energy at Richland, Washington. The FFTF is a multipurpose test reactor used to irradiate fuels and materials for programs such as Liquid Metal Reactor (LMR) research, fusion research, space power systems, isotope production and international research. FFTF is also used for testing concepts to be used in Advanced Reactors which will be designed to maximize passive safety features and not require complex shutdown systems to assure safe shutdown and heat removal. The FFTF also provides experience in the operation and maintenance of a reactor having prototypic components and systems typical of large LMR (LMFBR) power plants. The 5 year operational performance of the FFTF reactor is ...

1987-09-13

386

{sup 222}Rn as indicator of atmospheric turbulence: measurements at Lake Maggiore and on the pre-Alps  

Energy Technology Data Exchange (ETDEWEB)

Radon concentration measurements in atmosphere were taken in years from 1997 to 1999 in Milan and at pre-alpine sites located north of Lombardy. In this paper the results of measuring campaigns and a comparison of radon levels observed in the hilly area north of the town and on the pre-Alps are reported. The general criteria of the measurements and the interpretative models of radon concentration are presented. The Lake Maggiore area shows evidence of a great nocturnal stability and frequent formation of Nocturnal Stable Layer. The peculiar findings in the high altitude stations confirm the use of radon as an indicator of atmospheric dispersion of pollutants in an area with complex orography. The afternoon minimum values are concordant for the different stations: this implies a remixing in afternoon hours over the whole area investigated.

2006-07-01

387

Use of portable HPGE detector and multichannel analyzer for in-situ gamma spectrometry of soil  

International Nuclear Information System (INIS)

Measurement of fission and activation products in the soil or over a plane grass land of a nuclear power station environment is required to find out the long term changes. The inventory of radionuclides in the soil is routinely determined by soil sampling, processing and gamma spectrometry in the laboratory. The method although is proven and accurate is time consuming and largely dependent on homogenous distribution. Therefore, an alternative and rapid method of in-situ gamma spectrometry using portable devices was standardized to determine the concentration of radionuclides in soil, for regular environmental monitoring as well as during emergency condition. The paper presents the methodology, ready to use factors and compares the results of a few measurements made in the environment of Tarapur Atomic Power Station by both in-situ and laboratory methods. (author)

2005-11-23

388

The development of open-pore multi-layer systems for steam turbines operating with 700 C technology; Die Entwicklung offenporoeser Mehrschichtsysteme fuer Dampfturbinen der 700 C-Technologie  

Energy Technology Data Exchange (ETDEWEB)

In the context of the special research area 561 (Thermally highly loaded, open-porous and cooled multi-layer systems for combined-cycle power stations), the actual technical and scientific realizations are to be extended and new scientific bases are to be created in order to realize total efficiencies of 65 %. In addition, innovative material solutions and new concepts must be compiled for the cooling and drainage. Under this aspect, the author of the contribution under consideration reports on the development of open-porous multi-layer systems for steam turbines of the 700 C technology. It results an efficiency potential of 12 % and a potential of 15 % with the reduction of CO{sub 2} in relation to the actual state of the art. Thereby, the potential of future combined-cycle power stations is not yet exhausted.

2008-07-01

389

The SOS-LUX-TOXICITY-Test on the International Space Station  

British Library Electronic Table of Contents (United Kingdom)

For the safety of astronauts and to ensure the stability and integrity of the genome of microorganisms and plants used in bioregenerative life support systems, it is important to improve our knowledge of the combined action of (space) radiation and microgravity. The SOS-LUX-TOXICITY test, as part of the TRIPLE-LUX project (accepted for flight at Biolab in Columbus on the International Space Station, (ISS)), will provide an estimation of the health risk resulting from exposure of astronauts to the radiation environment of space in microgravity. The project will: (i) increase our knowledge of biological/health threatening action of space radiation and enzymatic DNA repair; (ii) uncover cellular mechanisms of synergistic interaction of microgravity and space radiation; (iii) provide specified...

2006-01-01

390

Summarization of radioactive effluent monitoring in Daya Bay Nuclear Power Station 1994-2002  

International Nuclear Information System (INIS)

This paper introduces the radioactive effluent monitoring systems, measurement and quality control methods used in Daya Bay Nuclear Power Station from its commercial operation in 1994. The main work and experiences for the management of effluent release are discussed and analyzed. The radwaste data appear declining trend and are far blow the annual limit approved by the national Environmental Protection Bureau since 1995. The normalized release (unit GBq/GWa) of 9 years is as follows: liquid nuclides (except tritium) 11.1, liquid tritium 1.91 x 10"4, noble gas 2.03 x 10"4, halogen 0.13, aerosol 7.57 x 10"-"3. For "1"1"0"mAg, the average release from 1998 to 2002 has been reduced to 1/7 of the quantity in 1997

2004-05-01

391

Quality control and evaluation for environmental radiological baseline study of Guangdong Daya Bay nuclear power station  

International Nuclear Information System (INIS)

The main points of quality control methods and technique of environmental radiological baseline study of Guangdong Daya Bay Nuclear Power Station are reported. Results of intercalibration of international and inland laboratories are given. The random chosen samples are checked and compared with two measurement methods. The data obtained in Daya Bay environment are put to the correlation statistics test using the linear regression analysis method between the correlative items such as "4"0K activity by gamma spectrum measurement and potassium content by chemical analysis, total #alpha#(#beta#) activity and nuclide content, as well as environmental gamma radiation dose rate and TLD accumulation dose. The data of Daya Bay environmental radioactivity baseline level show good concordance and reliability.

392

Process for producing calcium sulfate dihydrate during desulfurization of stack gases from power station boilers. Verfahren zur Herstellung von Calciumsulfat-Dihydrat im Zuge der Entschwefelung von Rauchgasen aus Kraftwerkskesselfeuerungen  

Energy Technology Data Exchange (ETDEWEB)

This is a process for producing calcium sulfate dihydrate during desulfurization of stack gases from power station boilers, where the stack gases are introduced into a washing tower and are treated with a washing water suspension containing lime in the washing tower, where oxygen in the form of air or of air enriched in oxygen is also blown into the washing tower, and where the washing water suspension drawn off from the washing tower is fed back to the washing tower at a temperature of 45 to 50/sup 0/C in the circuit and at least part of the flow goes via a thickener and where calcium sulfate dihydrate slurry is drawn off from the thickener.

1986-06-12

393

Problem of microelements in the combustion, gasification and hydrogenation of coals  

Energy Technology Data Exchange (ETDEWEB)

Role of microelements in coal in connection with their combustion in power stations, gasification and hydrogenation is discussed from the standpoint of environmental pollution and effects on technological parameters. In the wastes from fossil-fuel power stations there are biogenic and toxic elements (Be, B, Pb, etc.) present, which eventually go into the soil. Analyses showed that coal from the Kuznetsk, Donetsk, Ehkibastuz and Kansk-Achinsk basins which are used for power, have a relatively low level of biogenic and toxic microelements, e.g. Ba, B, Mn, Pb, Co, Ni, V, Cu, Y. Coal reactivity in gasification and hydrogenation is discussed. The catalytic effect of several microelements in coal gasification and hydrogenation is established. A geochemical multiplicative indicator is presented which makes quantitative evaluation of the suitability of coals for hydrogenation possible. 17 references.

1984-11-01

394

PSPs at Bhira and Bhivpuri  

International Nuclear Information System (INIS)

Tata Electric Companies (TEC) are engaged in the generation of hydro and thermal energy. TEC, to minimise backing down of its thermal units in off peak hours and also to at least partially meet the growing deficit in the supply during peak hours is moving to install pumped storage plants (PSPs) utilising off-peak surplus energy for pumping the water from lower pond to the upper pond for subsequent utilisation for power generation during peak hours. In view of some of the infra structural facilities such as storage ponds, water conductor system, transmission lines, etc. being already available, at the existing hydro power stations owned by TEC, the pumped storage units are being proposed within the environs of existing hydro stations, i.e. a 150 MW pumped storage unit at Bhira and a 90 MW pumped storage unit at Bhivpuri. The projects are described and cost estimates is given. (author). 2 figs.

1992-01-01

395

Influence of sintering conditions on the #beta#-sialon ceramics properties from power station fly ashes  

International Nuclear Information System (INIS)

Fly ash from Lagisza power station with addition of kaolin and calculated amount of carbon was reacted in flowing nitrogen at 1520"oC in order to obtain #beta#-sialon. The resulted powder was sintered with and without Y_2O_3 addition. Examinations show that it is possible to sinter that material without any sintering additives, however additive of Y_2O_3 decreases sintering temperature of about 100"oC. Sintering temperature influences the final mechanical properties like: flexural strength, microhardness, Young elastic modulus (E) and fracture toughness (K_I_c). (author)

2004-09-12

396

IEEE standard quality assurance program requirements for the design and manufacture of class 1E instrumentation and electric equipment for nuclear power generating station  

International Nuclear Information System (INIS)

The Institute of Electrical and Electronic Engineers (IEEE) standards for the quality assurance requirements for the design and manufacture of Class 1E instrumentation and electric equipment for a nuclear power generating station are presented. This standard establishes Quality Assurance Program requirements for electrical manufacturers. This standard, used in conjunction with ANSI N45.2-1977 and the supplemental standards to the extent referenced in this standard, is intended to meet the requirements of 10CFR50, Appendix B. These requirements are intended to assure that Class 1E instrumentation and electric equipment are responsibly engineered and manufactured from proper materials, that the manufacturing processes and practices are controlled, and that the manufacturing process produces a product of the required quality for Class 1E application.

397

Hybrid insulator - the excellent post insulator for HVAC and HVDC power station  

Energy Technology Data Exchange (ETDEWEB)

A solid layer artificial pollution test was carried out to study the pollution performance of a new type of hybrid station post insulator used in suspension and tensile high voltage transmission lines. The structure of the separated silicone rubber shed and porcelain core hybrid insulator was shown. The new insulator showed excellent pollution performance under both HVAC and HVDC conditions. It also exhibited excellent aging performance in artificial aging tests. The mechanical strength of the hybrid insulator was also better than normal composite insulators. Another advantage revealed was the fact that separated silicone rubber sheds and porcelain core hybrid post insulators are easier to manufacture than normal porcelain post insulators and other hybrid insulators. 5 refs., 6 tabs., 1 fig.

1997-12-31

398

Feeding ecology of mesopelagic zooplankton of the subtropical and subarctic North Pacific Ocean determined with fatty acid biomarkers  

British Library Electronic Table of Contents (United Kingdom)

Mesopelagic zooplankton may meet their nutritional and metabolic requirements in a number of ways including consumption of sinking particles, carnivory, and vertical migration. How these feeding modes change with depth or location, however, is poorly known. We analyzed fatty acid (FA) profiles to characterize zooplankton diet and large particle (>51?m) composition in the mesopelagic zone (base of euphotic zone ?1000m) at two contrasting time-series sites in the subarctic (station K2) and subtropical (station ALOHA) Pacific Ocean. Total FA concentration was 15.5 times higher in zooplankton tissue at K2, largely due to FA storage by seasonal vertical migrators such as Neocalanus and Eucalanus. FA biomarkers specific to herbivory implied a higher plant-derived food sou...

2010-01-01

399

Effect of the tide on the diffusion of "3H in the liquid effluent discharged from Daya Bay Nuclear Power Station  

International Nuclear Information System (INIS)

The tide field at the time of liquid effluent discharging from Daya Bay nuclear power station, and the average water speed at the monitoring points in west Daya Bay from the time of discharging to the time of sampling were calculated by ADI (Alternating Direction Implicit) method. By comparing analysis, the difference of "3H diffusion between spring tide and neap tide (the expansion of "3H within one day of spring tide is greater than that within one day of neap tide) was found. So, an equivalent diffusion time is introduced to modify the original model, and a better attenuation relation between the average "3He concentration in west Daya Bay and the time since the liquid "3H discharging is obtained. (authors)

2006-07-01

400

Device for transporting loads, especially for belt driving stations in open pit mining  

Science.gov (United States)

A device is described for transporting loads, especially for moving belt driving stations in open pit mining operations with a propelling mechanism which for lifting a respective load is operable to move into a free space formed by the load with the ground. The device comprises a plurality of lifting mechanisms, by means of which, a lifting platform can be brought into engagement with a supporting surface of the load. The device comprises at least one supporting member which is so designed that it prevents the lifting platform from lifting off lifting mechanisms. Furthermore, means are provided which permit a turning of the lifting platform relative to the lifting mechanisms about a vertical axis which is arranged in a certain relationship to the propelling mechanism.

1977-07-19

401

Development of design support system for pipeless batch plants; Pipeless batch plant sekkei shien system no kaihatsu  

Energy Technology Data Exchange (ETDEWEB)

A pipeless batch plant is a batch processing production system using mobile vessels. The plant performances depend on both hardware of equipment and software of operation. So the plant includes many design factors such as number of vessels, stations and AGVS, layout of stations, vessel moving rules, job scheduling and so on. In this paper, the characteristics of pipeless batch plant design are considered to handle the problem by the systems engineering approach. Then, a practical design method known as design-by-analysis is applied to solve such a complex design problem. Based on this concept, a design support system composed of modeling, simulation and evaluation subsystems is developed. This system enables rational decision making through performance evaluation for proposed design of a pipeless batch plant. The usefulness of the system is illustrated by industrial examples. 12 refs., 8 figs., 6 tabs.

1997-07-10

402

Construction progress of the cooling & ventilation in the LHC project  

CERN Document Server

After the LEP dismantling Phase the Cooling and Ventilation Group has started the LHC construction work. Year 2001 through to 2004 will certainly be the most important period of activity for the CV group in the erection phase The author will report on the current works that are in progress on the different LHC Points distinguishing between the Ventilation and the Water Cooling installations. The Ventilation work completed in the new surface buildings in Points 1, 4,5,6 and 8. The work for the Cooling plants comprehend to the pumping stations, the cooling towers and the chilled water production stations in Points 1 and 5, For all of these activities, an updated report of the progress the work, the planning and of the expenses are given. Finally, a brief overview of the future activities is presented.

2002-01-01

403

Construction Progress of the Cooling and Ventilation in the LHC Project  

CERN Document Server

The Cooling and Ventilation Group has started the LHC construction work in September 1999 and will get into full activity when LEP will be stopped and dismantled: in total 12 major contracts for an amount of about 120 MCHF will be established to build the needed installations for the LHC. The author will report on the current works that are in progress on the different LEP Points distinguishing between the Ventilation and the Water Cooling installations. The Ventilation work, completed in the new surface buildings in Points 18, is currently held in Points 4 and 5. Point 1 will follow in the near future. The work for the Cooling plants comprehend the pumping stations, the cooling towers and the chilled water production stations in Points 1 and 5, the buried pipes in Points 1 and 4. For all of these activities, an updated report of the progress of the work, of the planning and of the expenses is given. Finally, a short overview of the future ...

2001-01-01

404

Climatic changes in Central Italy and their potential effects on corn water consumption  

British Library Electronic Table of Contents (United Kingdom)

This study evaluates the trends of meteorological and agrometeorological indices computed at different sites in the Region of Umbria (Central Italy). The indices were selected on the basis of whether they enable the evaluation of the potential effects of climatic changes on agricultural water requirements and management. The meteorological stations were preliminarily selected considering the length and entirety of the data series and a homogeneous spatial coverage of the region under study. The daily rainfall and minimum and maximum temperature data collected at the stations were elaborated to calculate meteorological and agrometeorological indices (for corn, widespread irrigated crop in Central Italy).The results of the analysis show that rainfall has decreased generally everywhere and th...

2008-01-01

405

An integrated oil and chemicals chain  

International Nuclear Information System (INIS)

Last year, 1991, was a difficult one for Finland's oil and chemicals company, Neste Corporation. The sharp fall in the international price of chemicals products had a significant impact on the corporation's overall result. Neste was, however, able to improve its competitive position, move ahead with numerous investments, and develop new businesses. This was particularly evident in two areas that have received significant emphasis within Neste in recent years: oil exploration and the Baltic region where a network of modern service stations in Neste livery and stretching from Vyborg on the Finnish-Russian border, through St. Petersburg, Tallinn, and the Baltic countries to Warsaw, is currently taking shape. The majority of the western-style stations in this network will be located along the route of the M12 highway, which has been dubbed the Via Baltica.

406

Ageing and life-time management in nuclear power stations - concept and examples; Alterungs- und Lebensdauermanagement in Kernkraftwerken - Konzept und Beispiele  

Energy Technology Data Exchange (ETDEWEB)

Knowledge, assessment and understanding of phenomena caused by ageing, together with systematic utilization and extension of the technical life-time of components and systems, are of critical importance to the safety and economy of electricity generation in nuclear power stations. Economic use can be optimized by integrated ageing and life-time management; it can also be used to improve performance characteristics. (orig.) [Deutsch] Fuer die Sicherheit und Wirtschaftlichkeit der Stromerzeugung in Kernkraftwerken sind die Kenntnis, Bewertung und Beherrschung alterungsbedingter Phaenomene und systematische Ausnutzung bzw. Verlaengerung der technischen Lebensdauer der Komponenten und Systeme von zentraler Bedeutung. Durch ganzheitliches Alterungs- und Lebensdauermanagement, das auch auf die Verbesserung von Leistungsmerkmalen abzielt, kann der wirtschaftliche Nutzen optimiert werden. (orig.)

1999-07-01

407

Adenopathies in lung cancer: a comparison of pathology, Computed Tomography and endoscopic ultrasound findings  

International Nuclear Information System (INIS)

A prospective comparative study with pathology was performed to assess the clinical value of Computed Tomography (CT) and endoscopic ultrasound (EUS) for nodal staging in lung cancer. A total of 329 nodal stations were dissected or sampled and 755 lymph nodes were examined at histology. On a pre-station basis, CT had greater sensitivity (74%) than EUS (56%), but EUS was more specific (83% versus 93%). The accuracy rates of the two techniques were similar. In conclusion, endoscopic ultrasound should be part of a routine preoperative diagnostic approach to non-small-cell lung cancer., because of its high specificity. Results can be improved when EUS and CT are combined., which suggests that these imaging modalities should be used together in selected patients for the noninvasive staging of non-small-cell lung cancer to identify local lymphatic spread.

1999-01-01

408

"2"2"2Rn as indicator of atmospheric turbulence: measurements at Lake Maggiore and on the pre-Alps  

International Nuclear Information System (INIS)

Radon concentration measurements in atmosphere were taken in years from 1997 to 1999 in Milan and at pre-alpine sites located north of Lombardy. In this paper the results of measuring campaigns and a comparison of radon levels observed in the hilly area north of the town and on the pre-Alps are reported. The general criteria of the measurements and the interpretative models of radon concentration are presented. The Lake Maggiore area shows evidence of a great nocturnal stability and frequent formation of Nocturnal Stable Layer. The peculiar findings in the high altitude stations confirm the use of radon as an indicator of atmospheric dispersion of pollutants in an area with complex orography. The afternoon minimum values are concordant for the different stations: this implies a remixing in afternoon hours over the whole area investigated.

409

A comparison study on activation safety of fusion, fission and hybrid reactor technology  

Energy Technology Data Exchange (ETDEWEB)

The activation aspects of pure fusion and hybrid fusion technology is studied to assess the radioactive safety of various fusion concepts including tokamak pure fusion, fissile fuel producing hybrid and radio waste transmuting hybrid. The activation properties of breeding, coolant and structural materials in fusion reactors might be quite different from those in fission reactors because of the high energy D-T fusion neutrons from the fusion cores. A study on the involved activation reactions and the uncertainties of the associated nuclear cross-sections is carried. The activation properties of various first wall concepts and blanket concepts are discussed. The radioactive inventory during the operation lifetime and the potential hazard of the radioactive nuclides with respect to near term (reprocessing) and long term (waste disposal) aspects are calculated, with reference to ITER/NET (International Thermonuclear Experiment ...

1994-12-31

410

A comparison study on activation safety of fusion, fission and hybrid reactor technology  

International Nuclear Information System (INIS)

The activation aspects of pure fusion and hybrid fusion technology is studied to assess the radioactive safety of various fusion concepts including tokamak pure fusion, fissile fuel producing hybrid and radio waste transmuting hybrid. The activation properties of breeding, coolant and structural materials in fusion reactors might be quite different from those in fission reactors because of the high energy D-T fusion neutrons from the fusion cores. A study on the involved activation reactions and the uncertainties of the associated nuclear cross-sections is carried. The activation properties of various first wall concepts and blanket concepts are discussed. The radioactive inventory during the operation lifetime and the potential hazard of the radioactive nuclides with respect to near term (reprocessing) and long term (waste disposal) aspects are calculated, with reference to ITER/NET (International Thermonuclear Experiment ...

411

System Requirements Document for the Molten Salt Reactor Experiment  

Energy Technology Data Exchange (ETDEWEB)

The purpose of the conversion process is to convert the {sup 233}U fluoride compounds that are being extracted from the Molten Salt Reactor Experiment (MSRE) equipment to a stable oxide for long-term storage at Bldg. 3019.

2000-04-01

412

Study on the separation characteristics of tritiated water vapor adsorption.  

Science.gov (United States)

In order to reduce the air concentration of (sup 3)H in the reactor buiIding of Wolsung Heavy Water Reactor, a computer code for estimation of adsorption behavior was programmed based on an equation derived for analysis of water vapor adsorption, and a ba...

1991-01-01

413

Spent fuel management in Czechoslovak WWER-440 type reactors  

International Nuclear Information System (INIS)

The main aspects of the present WWER-440 reactors spent fuel management are described in the paper. Experimental results of fuel integrity studies which are carried out under conditions of a long-term storage are also presented. (author). 5 refs, 5 figs.

1988-12-01

414

Simulation tools and new developments of the molten salt fast reactor  

International Nuclear Information System (INIS)

Starting from the Molten Salt Breeder Reactor project of Oak-Ridge, we have performed parametric studies in terms of safety coefficients, reprocessing requirements and breeding capabilities. In the frame of this major re-evaluation of the molten salt reactor (MSR), we have developed a new concept called Molten Salt Fast Reactor or MSFR, based on the Thorium fuel cycle and a fast neutron spectrum. This concept has been selected for further studies by the MSR steering committee of the Generation IV International Forum in 2009. Our reactor's studies of the MSFR concept rely on numerical simulations making use of the MCNP neutron transport code coupled with a code for materials evolution which resolves the Bateman's equations giving the population of each nucleus inside each part of the reactor at each moment. Because of MSR's fundamental characteristics compared to classical ...

415

Seismic Testing of Reactor Components.  

Science.gov (United States)

This report is the final report on the seismic testing of reactor components conducted since 1977 with opening of the vibration laboratory at KAERI. In 1979, forced vibration testing of Wolsung-1 steam generator model using sine dwell and white nosie rand...

1980-01-01

416

Radioactive Waste Disposal for Fission and Fusion Reactors.  

Science.gov (United States)

The calculated radioactive waste inventories of the Turkey Point pressurized water fission reactor (PWR) and the Starfire conceptual fusion tokamak are compared as a function of time from initial start-up to 10,000 years after decommissioning. Only materi...

1989-01-01

417

New neutron simulation capabilities provided by the Sandia Pulse Reactor (SPR-III) and the Upgraded Annular Core Pulse Reactor (ACPR)  

Science.gov (United States)

The paper briefly describes the nuclear reactor facilities at Sandia Laboratories which are used for simulating nuclear weapon produced neutron environments. These reactor facilities are used principally in support of continuing R and D programs for the Department of Energy/Office of Military Application (DOE/OMA) in studying the effects of radiation on nuclear weapon systems and components. As such, the reactors are available to DOE and DOD agencies and their contractors responsible for the radiation hardening of advanced nuclear weapon systems. Emphasis is placed upon two new reactor simulation sources; the Sandia Pulse Reactor-III (SPR-III) Facility which enhances the neutron exposure volume capabilities over those presently available with the existing SPR-II Facility, and the Upgraded Annular Core Pulse Reactor (ACPR) Facility which enhances the neutron ...

1978-07-01

418

Neutron data requirements for calculating transactinide isotope build-up in reactors  

International Nuclear Information System (INIS)

Based on a generalized theory of perturbations and on non-linear programming an approach to the quantitative determination of necessary accuracies for nuclear data is described. It is used to calculate transactinide isotope build-up in reactors.

1979-08-01

419

NUCLEAR REACTOR WITH CHARGE OF HOMOGENEOUSLY CAST BREEDER ELEMENTS  

Science.gov (United States)

A reactor was proposed in which the breeder mantel would consist of a charge of homogeneous cast breeder elements, so that the breeder element has the same shape as the fuel elements. By this method it would be possible to use the breeder element after its irradiation immediately for the charging of the fuel elements.

1959-01-01

420

Irradiation-effects considerations for the SP-100 space reactor  

International Nuclear Information System (INIS)

The Sp-100 reactor is a lithium-cooled high-temperature fast-spectrum reactor. The fuel is UN. The cladding is fabricated from PWC-11, a Nb alloy, as are all the primary structural components. A reactor lifetime of up to ten years with an operating temperature of 1370 K is required. The accumulated fluence is expected to be 6 x10"2"2 n/cm"2. The damage, which could result in swelling or embrittlement, anneals out as fast as it occurs for the majority of the structure. This has been confirmed by earlier radiation testing. A number of components, however, are exposed to lower temperatures and the reactor design and materials selection for these components must take this into consideration. Radiation effects must also be considered for the UN fuel, bearing materials, etc. To data an instrumented experiment, MOTO 1000A, has been conducted in the FFTF reactor and as uninstrumented ...

1992-03-01

421

Fuels and materials testing capabilities in Fast Flux Test Facility  

Energy Technology Data Exchange (ETDEWEB)

The Fast Flux Test Facility (FFTF) reactor, which started operating in 1982, is a 400 MWt sodium-cooled fast neutron reactor located in Hanford, Washington State, and operated by Westinghouse Hanford Co. under contract with U.S. Department of Energy. The reactor has a wide variety of functions for irradiation tests and special tests, and its major purpose is the irradiation of fuel and material for liquid metal reactor, nuclear reactor and space reactor projects. The review first describes major technical specifications and current conditions of the FFTF reactor. Then the plan for irradiation testing is outlined focusing on general features, fuel pin/assembly irradiation tests, and absorber irradiation tests. Assemblies for special tests include the material open test assembly (MOTA), fuel open test assembly (FOTA), closed loop ...

1989-07-01

422

Fuels and materials testing capabilities in Fast Flux Test Facility  

International Nuclear Information System (INIS)

The Fast Flux Test Facility (FFTF) reactor, which started operating in 1982, is a 400 MWt sodium-cooled fast neutron reactor located in Hanford, Washington State, and operated by Westinghouse Hanford Co. under contract with U.S. Department of Energy. The reactor has a wide variety of functions for irradiation tests and special tests, and its major purpose is the irradiation of fuel and material for liquid metal reactor, nuclear reactor and space reactor projects. The review first describes major technical specifications and current conditions of the FFTF reactor. Then the plan for irradiation testing is outlined focusing on general features, fuel pin/assembly irradiation tests, and absorber irradiation tests. Assemblies for special tests include the material open test assembly (MOTA), fuel open test assembly (FOTA), closed loop ...

423

Final Report of ''On-the-Job Training'' on the CANDU Reactor.  

Science.gov (United States)

This is the final Report for the technical ''on-the-job traning'' for the Wolsung CANDU nuclear power plant which is the first Pressurized Heavy Water Reactor setting up in Korea. The technical ''on-the-job traning'' was established to increase the capabi...

1983-01-01

424

Coal reactor conservation of blast furnace coke  

Science.gov (United States)

Coke consumption may be cut as much as fifty percent using a coal reactor to furnish carbon monoxide for ore reduction in a blast furnace while lowering the sulfur content of pig iron accompanied by a smaller slag volume.

1982-02-23

425

Advanced PWR technology development -Development of advanced PWR system analysis technology-  

Energy Technology Data Exchange (ETDEWEB)

The primary scope of this study is to establish the analysis technology for the advanced reactor designed on the basis of the passive and inherent safety concepts. This study is extended to the application of these technology to the safety analysis of the passive reactor. The study was performed for the small and medium sized reactor and the large sized reactor by focusing on the development of the analysis technology for the passive components. Among the identified concepts the once-through steam generator, the natural circulation of the integral reactor, heat pipe for containment cooling, and hydraulic valve were selected as the high priority items to be developed and the related studies are being performed for these items. For the large sized passive reactor, the study plans to extend the applicability of the best estimate computer code RELAP5/MOD3 which is ...

1995-07-01

426

A design study of reactor core optimization for direct nuclear heat-to-electricity conversion in a space power reactor  

Energy Technology Data Exchange (ETDEWEB)

To propose a new design concept of a nuclear reactor used in the space, research has been conducted on the conceptual design of a new nuclear reactor on the basis of the following three main concepts: (1) Thermionic generation by thermionic fuel elements (TFE), (2) reactivity control by rotary reflector, and (3) reactor cooling by liquid metal. The outcomes of the research are: (1) A calculation algorithm was derived for obtaining convergent conditions by repeating nuclear characteristic calculation and thermal flow characteristic calculation for the space nuclear reactor. (2) Use of this algorithm and the parametric study established that a space nuclear reactor using 97% enriched uranium nitride as the fuel and lithium as the coolant and having a core with a radius of about 25 cm, a height of about 50 cm and a generation efficiency of about 7% can probably be operated continuously ...

1998-01-01

427

Waste management considerations for fusion power reactors  

International Nuclear Information System (INIS)

To estimate the waste management needs of a fusion power reactor, a scheme for handling radioactive waste from a fusion plant has been devised. The handling scheme proceeds with radioactive waste, primarily from blanket replacement, being stored on-site; waste in cooled and shielded casks is then isolated off-site; finally, the materials are recycled. Using activities and component lifetimes supplied by designers, several conceptual fusion power reactors have been analyzed and their waste streams compared to fission reactors with regard to total activity, specific activity, and lifetimes of activity.

428

Waste management considerations for fusion power reactors  

Science.gov (United States)

To estimate the waste management needs of a fusion power reactor, a scheme for handling radioactive waste from a fusion plant has been devised. The handling scheme proceeds with radioactive waste, primarily from blanket replacement, being stored on-site; waste in cooled and shielded casks is then isolated off-site; finally, the materials are recycled. Using activities and component lifetimes supplied by designers, several conceptual fusion power reactors have been analyzed and their waste streams compared to fission reactors with regard to total activity, specific activity, and lifetimes of activity.

1978-02-01

429

UK's Sizewell inquiry; funny how time slips away  

Energy Technology Data Exchange (ETDEWEB)

Comments are made on the Public Inquiry into CEGB's proposal to construct a pressurized water reactor (PWR) at Sizewell, UK. Aspects discussed include: time elapsed and its possible effect on the result; economics of nuclear power plants compared with coal-fired power plants; changes in real sterling/dollar exchange rates; effect of mineworkers' strike; the UK electric power generating system; AGR reactors compared with PWR reactors; extension of Magnox reactor life; radioactive waste management; political decisions.

1985-03-01

430
431

The SBWR (simplified boiling water reactor) thermal-hydraulic performance analysis and testing  

Science.gov (United States)

Utility interest has recently increased in potential future nuclear units that combine the characteristics of smaller size, greater simplicity, and more passive safety features. In response to such interest, General Electric (GE) began development in 1982 of a 600-MW(electric) reactor with simplified power generation and safety systems. This paper provides an overview of the simplified boiling water reactor (SBWR) design, with emphasis on the thermal-hydraulic aspects of the design. The SBWR is a natural circulation reactor requiring no pumps to circulate the water through the core.

1989-11-01

433

Some studies on physics parameters of Wolsung unit no. 1  

International Nuclear Information System (INIS)

Nuclear physics parameters of the Wolsung CANDU-PHW reactor are computed by use of the PHWCELL computer code that is an improved version of LATREP. The PHWCELL code mainly computes cell parameters of heavy water moderated reactors, and modeling scheme of heavy water reactor cell calculations has been developed with the PHWCELL computer code. The reactor operating conditions considered in the study are cold zero power (CZP) and hot full power (HFP) with equilibrium poison. The cell parameters are also computed as a function of fuel burnup and the numerical results are compared with the results in PSR of the Wolsung unit and in the previous study. (author).

1980-01-01

434

Safe Type of Transference for Spent Fuel  

International Science & Technology Center (ISTC)

Safe Transference of Spent Fuel Assemblies from Near-Reactor Storage Pools to Long-term "Dry" Storage

435

Risk assessment for the SNR-300 reactor. Earthquake hazard emanating from reactor component failure  

International Nuclear Information System (INIS)

The risk analysis was carried out in consideration of conditions prevailing at the Kalkar site analogous to the investigations in phase A of DRS (German Reactor Study). Earthquake design loads include the probabilities of upper deviations of the site intensities to be expected. The calculations of dynamic loads for select buildings are made using models and computational methods. Component analyses were performed analogous to DRS for the supports of large components, supports of the roof construction of the reactor building taking into account support reserves due to plastic work capacity, wall disks in steam generator buildings and switchboard plant buildings. (DG).

436

Real-time neutron radiography at the Georgia Tech Research Reactor  

International Nuclear Information System (INIS)

(Jun 1982). United States Davis, MV Berger, H. Patricelli, F. Georgia Institute

1982-06-11

439

Potential gas entry into FFTF after a postulated pipe rupture  

International Nuclear Information System (INIS)

... failures fftf reactor heat transfer hydraulics loss of coolant pipes primary coolant

440

Method for limiting scram discharge water  

International Nuclear Information System (INIS)

Object: To limit the discharge amount of reactor water in a primary system at the time of scram to prevent excessive outflow of reactor water outside the system. Structure: A signal from an upper limit position indicator detects the fact that control rods are completely inserted when the reactor is urgently stopped and the detection signal causes a valve in an outflow line of the discharge water from a control rod driving mechanism to be closed to limit the amount of discharge flown into the scram discharge vessel, thus preventing outflow of reactor water in the primary system after the scram has been initiated. (Kamimura, M.).

442

Investigation of FP paths during hypothetical severe accident as a result of Small Break LOCA of WWER-1000 reactor type  

International Nuclear Information System (INIS)

Modelling the behaviour of fission product (FP) in a nuclear reactor coolant system (RCS) undergoing a hypothetical severe accident is an important step in the evaluation of radioactive release outside a nuclear power plant. This paper scrutinize Small Break LOCA sequence for WWER1000 reactor in order to investigate the possible paths for release of FP from fuel pallets to the reactor containment. Contemporaneous computer code for simulation of RCS will be use for the analysis. The results from analysis of fuel damage and release of FP trough the break of cold leg are present. (author)

2006-04-01

443

Handbook: Approaches for the Remediation of Federal Facility ...  

Science.gov (United States)

... 4-4 UXO disposal operations ... testing of sequencing batch reactor treatment of ... and lead toward the anode compartment ..... ...

1993-09-01

444
445

Fuel Assembly Materials under Dry Storage  

International Science & Technology Center (ISTC)

Behavior of Nuclear Reactor Fuel Assembly Materials during Their Long-Term Dry Storage

446

Finite Element Analysis of Magnetoelastic Plate Problems.  

Science.gov (United States)

... in the design of such devices as fusion reactors, magnetohydrodynamic generators, magnetically levitated vehicles, magnetic forming devices, and ...

1981-08-01

447

FFTF progress highlights, winter 1975--1976  

Science.gov (United States)

Milestones concerning equipment, reactor components, and testing and operations at the FFTF since July 1, 1975 are highlighted. (JWR)

1975-07-01

448

Experience of HWR nuclear fuel fabrication technology development in Korea  

Energy Technology Data Exchange (ETDEWEB)

Since January, 1981, the project of development of nuclear fuel fabrication technology for Wolsung reactor (CANDU type) was undertaken by KAERI(Korea Advanced Energy Research Institute) and successfully fulfilled with loading 24 fuel bundles made by KAERI in Wolsung reactor in September, 1984. On the basis of this accumulated technology and experience, mass production plan to supply all the nuclear fuels for Wolsung reactor is under way. In this presentation, the Korean experience in the development of the nuclear fuel fabrication technology, safety and performance evaluation of KAERI fuel and the results of irradiation of KAERI fuels in Wolsung reactor will be described.

1985-07-01

449

Experience of HWR nuclear fuel fabrication technology development in Korea  

International Nuclear Information System (INIS)

Since January, 1981, the project of development of nuclear fuel fabrication technology for Wolsung reactor (CANDU type) was undertaken by KAERI(Korea Advanced Energy Research Institute) and successfully fulfilled with loading 24 fuel bundles made by KAERI in Wolsung reactor in September, 1984. On the basis of this accumulated technology and experience, mass production plan to supply all the nuclear fuels for Wolsung reactor is under way. In this presentation, the Korean experience in the development of the nuclear fuel fabrication technology, safety and performance evaluation of KAERI fuel and the results of irradiation of KAERI fuels in Wolsung reactor will be described.

1985-10-29

450

Evaluation of tritiated water retention capacity of fusion reactor concrete building  

Energy Technology Data Exchange (ETDEWEB)

In this paper the diffusion of tritiated water vapor into concrete walls is studied to evaluate tritiated water retention capacity of a fusion reactor concrete building. Using a model of the tritiated water diffusion determined form experimental results, depth profiles of tritiated water in concrete are calculated in the case of being exposed to air containing tritiated water vapor during the normal operational condition of a fusion reactor. A 0.5-m-thick concrete is sufficient for reactor hall walls from a viewpoint of the tritium containment.

1992-03-01

451

Evaluation of tritiated water retention capacity of fusion reactor concrete building  

International Nuclear Information System (INIS)

In this paper the diffusion of tritiated water vapor into concrete walls is studied to evaluate tritiated water retention capacity of a fusion reactor concrete building. Using a model of the tritiated water diffusion determined form experimental results, depth profiles of tritiated water in concrete are calculated in the case of being exposed to air containing tritiated water vapor during the normal operational condition of a fusion reactor. A 0.5-m-thick concrete is sufficient for reactor hall walls from a viewpoint of the tritium containment.

452

Evaluation of the fluid force in main feed water control valve for APWRs  

International Nuclear Information System (INIS)

... 2432 v. 43(1) SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS

2006-01-01

453

Emergency core cooling device for a reactor  

International Nuclear Information System (INIS)

Purpose : To obtain an emergency core cooling device in a FBR type reactor by utilizing heat pipes which are not actuated at usual operation condition but actuated reliably upon emergency. Constitution : A system for injecting heat medium into heat pipes is provided. By injecting the heat medium into the heat pipes upon emergency to actuate the heat pipes, the reactor core is cooled. During normal reactor operation, the inside of the heat pipes is evacuated from a vacuum pump and no heat medium is filled therein, whereby unnecessary heat loss during the normal operation can be prevented. (Ikeda, J.).

1982-01-24

454

Directions for improved fusion reactors  

International Nuclear Information System (INIS)

Conceptual fusion reactor studies over the past 10 to 15 years have projected systems that may be too large, complex, and costly to be of commercial interest. One main direction for improved fusion reactors points towards smaller, higher-power-density approaches. First-order economic issues (i.e., unit direct cost and cost of electricity) are used to support the need for more compact fusion reactors. A generic fusion physics/engineering/costing model is used to provide a quantiative basis for these arguments for specific fusion concepts.

455

Development of Synthol circulating fluidized bed reactors  

Energy Technology Data Exchange (ETDEWEB)

In 1980 Sasol completed its very large coal conversion complex, Sasol Two and Three in South Africa. This complex, the largest coal-to-liquids facility in the world, utilizes Sasol's proprietary Fischer-Tropsch technology, the Synthol Process. The two key elements of the Synthol Process are its catalyst and its unique fluidized bed reactor, the Synthol Circulating Fluidized Bed Reactor. Details on the catalytic aspects and reaction mechanism have been given elsewhere. In this paper, the history of the development of the reactor is discussed.

1986-08-01

456

Depleted zinc: Properties, application, production  

Energy Technology Data Exchange (ETDEWEB)

The addition of ZnO, depleted in the Zn-64 isotope, to the water of boiling water nuclear reactors lessens the accumulation of Co-60 on the reactor interior surfaces, reduces radioactive wastes and increases the reactor service-life because of the inhibitory action of zinc on inter-granular stress corrosion cracking. To the same effect depleted zinc in the form of acetate dihydrate is used in pressurized water reactors. Gas centrifuge isotope separation method is applied for production of depleted zinc on the industrial scale. More than 20 years of depleted zinc application history demonstrates its benefits for reduction of NPP personnel radiation exposure and combating construction materials corrosion.

2009-07-15

457

Core simulations using actual detector readings for a Canada deuterium uranium reactor  

Science.gov (United States)

This paper reports that, to obtain better simulation results for a Canada deuterium uranium (CANDU) reactor operation, a new simulation method is developed that uses actual detector readings as a correction factor. Detector readings from a CANDU reactor are used to correct the calculated flux distribution during core calculation iterations. A suitable function is found to describe the relationship between the detector flux and the fluxes of mesh points around the detector. The new simulation method is tested by performing numerical calculations for the Wolsung reactor (a CANDU-600). The results show that the new method predicts the core state more accurately with fewer iterations.

1991-02-01

458

Computer control of fuel handling activities at FFTF  

International Nuclear Information System (INIS)

The Fast Flux Test Facility near Richland, Washington, utilizes computer control for reactor refueling and other related core component handling and processing tasks. The computer controlled tasks described in this paper include core component transfers within the reactor vessel, core component transfers into and out of the reactor vessel, remote duct measurements of irradiated core components, remote duct cutting, and finally, transferring irradiated components out of the reactor containment building for off-site shipments or to long term storage. 3 refs., 16 figs.

1985-09-08

459

Canadian nuclear review  

International Nuclear Information System (INIS)

Progress in the construction of Candu reactors at home and abroad is surveyed. Some A.E.C.L. research projects are also mentioned. During 1979, Candu reactors again showed their superior capacity factors, four of them being among the ten most reliable reactors in the world. Progress in construction at Pickering B, Bruce B, Point Lepreau, Gentilly-2, Darlington, Wolsung (Korea), Cordoba (Argentina), and Cernavoda (Romania) is recounted. In 1979, it was unfortunately necessary to replace installed steam generators at Pickering B, Bruce B, Point Lepreau and Gentilly-2. At Wolsung, the reactor was pre-assembled before installation, which is a new technique. (N.D.H.).

1979-01-01

460

CARBON DIOXIDE REDUCTION SYSTEM  

Science.gov (United States)

... be easily replaceable, and its compartment or container ... in a simple, efficient manner for storage or disposal. ... and enters the reactor at approximatel ...

1963-01-01

461

Assessment of cooling effects on extending the maximum operating time for the Syrian Miniature Neutron Source Reactor  

International Nuclear Information System (INIS)

Various schemes of cooling have been investigated for the purpose of assessing potential benefits on the operational characteristics of the Syrian MNSR reactor. A detailed thermal hydraulic model for the analysis of MNSR has been developed. The analysis shows that an auxiliary cooling system, installed in the pool which surrounds the lower section of the reactor vessel, will significantly offset the consumption of excess reactivity due to the negative reactivity temperature coefficient, Hence, the maximum operating time of the reactor is extended. Compared with experimental data, the suggested model proves to be valid for the analysis of MNSR behavior under both steady state and transient conditions. (author)

2007-01-01

462

Application of the GEM shutdown device to the FFTF reactor  

Energy Technology Data Exchange (ETDEWEB)

A novel device called the gas expansion model (GEM) is being developed at the Hanford Engineering Development Laboratory for testing in the 400-MW(th) fast flux test facility (FFTF) reactor. Incorporation of the GEM into liquid-metal reactor designs is intended to measurably contribute to the achievement of inherent safety, by allowing the reactor to passively shut down even in the extremely remote (hypothetical) event of an unprotected (no scram) loss-of-flow accident. The purpose of this paper is to describe the GEM and present predictive analyses of the effectiveness of the device during unprotected loss-of-flow experiments in the FFTF.

1986-01-01

463

Application of the GEM shutdown device to the FFTF reactor  

International Nuclear Information System (INIS)

A novel device called the gas expansion model (GEM) is being developed at the Hanford Engineering Development Laboratory for testing in the 400-MW(th) fast flux test facility (FFTF) reactor. Incorporation of the GEM into liquid-metal reactor designs is intended to measurably contribute to the achievement of inherent safety, by allowing the reactor to passively shut down even in the extremely remote (hypothetical) event of an unprotected (no scram) loss-of-flow accident. The purpose of this paper is to describe the GEM and present predictive analyses of the effectiveness of the device during unprotected loss-of-flow experiments in the FFTF.

1986-11-16

465

Thorium dioxide: properties and nuclear applications  

Energy Technology Data Exchange (ETDEWEB)

This is the sixth book on reactor materials published under sponsorship of the Naval Reactors Office of the United States Department of Energy, formerly the United States Atomic Energy Commission. This book presents a comprehensive compilation of the most significant properties of thorium dioxide, much like the book Uranium Dioxide: Properties and Nuclear Applications presented information on the fuel material used in the Shippingport Pressurized Water Reactor core.

1984-01-01

466

The integrated PWR; Les REP integres  

Energy Technology Data Exchange (ETDEWEB)

This document presents the integrated reactors concepts by a presentation of four reactors: PIUS, SIR, IRIS and CAREM. The core conception, the operating, the safety, the economical aspects and the possible users are detailed. From the performance of the classical integrated PWR, the necessity of new innovative fuels utilization, the research of a simplified design to make easier the safety and the KWh cost decrease, a new integrated reactor is presented: SCAR 600. (A.L.B.)

2002-07-01

467

The controllability analysis of the purification system for heavy water reactors  

International Nuclear Information System (INIS)

The heavy water reactor such as Wolsung No.1 and No.2 has a purification system to purify the reactor coolant. The control system regulates the coolant temperature to protect the ion exchanger. After the fuel exchanges of operating plant, the increase of the coolant pressure makes the purification temperature control difficult. In this paper, the controllability of the control dynamics of the purification system was analysed and the optimal parameters were proposed. To reduce the effects of the flow disturbance, the feedforward control structure was proposed and analysed.

2001-10-01

468

Status of neutron cross sections for reactor dosimetry  

International Nuclear Information System (INIS)

The status of neutron activation cross sections for some threshold reactions important for reactor materials dosimetry is reviewed. An attempt is made to understand and explain discrepancies between integral and differential data, using recent available experimental results. The importance of standard and benchmark neutron fields for testing differential data for reactor dosimetry is emphasized and the Interlaboratory Reaction Rate (ILRR) program, as well as a similar program pursued by the IAEA, are briefly described.

1976-07-06

469

Production capabilities in US nuclear reactors for medical radioisotopes  

Energy Technology Data Exchange (ETDEWEB)

The availability of reactor-produced radioisotopes in the United States for use in medical research and nuclear medicine has traditionally depended on facilities which are an integral part of the US national laboratories and a few reactors at universities. One exception is the reactor in Sterling Forest, New York, originally operated as part of the Cintichem (Union Carbide) system, which is currently in the process of permanent shutdown. Since there are no industry-run reactors in the US, the national laboratories and universities thus play a critical role in providing reactor-produced radioisotopes for medical research and clinical use. The goal of this survey is to provide a comprehensive summary of these production capabilities. With the temporary shutdown of the Oak Ridge National Laboratory (ORNL) High Flux Isotope Reactor (HFIR) in November 1986, the ...

1992-11-01

470

Plasma Flow Equilibrium, Confinement Scaling Laws and Fusion Prospects of a Field Reversed Configuration  

International Nuclear Information System (INIS)

Field reversed configuration (FRC) is a prospective high ? magnetic system for high efficiency D- 3He fusion reactor. Self-consistent FRC plasma profiles and static electric field for reactor calculations are discussed in framework of the model including flow equilibrium and collisionless transport equations. The extrapolations to reactor regimes of plasma confinement scaling laws are considered.

2006-01-01

471

Nuclear power generation. Chapter 14  

International Nuclear Information System (INIS)

As part of a handbook on the efficient use of energy a chapter is included which is intended to give an appreciation of the principles and problems involved in the generation of nuclear power. The subject is discussed under the following headings: introductory nuclear physics; basic reactor physics; thermal reactors; fast reactors; fuel reserves and utilization; environmental considerations; nuclear fusion. (U.K.).

1975-01-01

472

NO{sub x} formation in lean premixed combustion of methane at high pressures  

Energy Technology Data Exchange (ETDEWEB)

High pressure experiments in a jet-stirred reactor have been performed to study the NO{sub x} formation in lean premixed combustion of methane/air mixtures. The experimental results are compared with numerical predictions using four well known reaction mechanisms and a model which consists of a series of two perfectly stirred reactors and a plug flow reactor. (author) 2 figs., 7 refs.

1999-08-01

473

Investigation on natural convection decay heat removal for the EFR: Status of the program  

International Nuclear Information System (INIS)

The European Research and Development Program on decay heat removal by natural convection for the European Fast Reactor (EFR) covers the calculational methods and the model experiments performed for code validation. The studies concentrate on important physical effects of the cooling modes within the primary system and the direct reactor cooling circuits and include fundamental tests as well as reactor experiments. (author)

1991-11-05

474

Heavy water leak due to fretting of DN tube  

International Nuclear Information System (INIS)

Wolsung nuclear power plant has experienced four occasions of reactor shutdown owing to heavy water leaks since its commercial operation. Among these heavy water leaks, only one case was acute and brought about reactor shutdown but the other cases listed below were chronic and repaired after manual reactor shutdown. (author). 4 tabs., 10 figs.

1989-06-04

475

HLMC Fast Reactor With Complete Natural Circulation  

Science.gov (United States)

To seek for a promising concept of a heavy liquid metal coolant (HLMC) fast reactor plant, Japan Nuclear Cycle Development Institute (JNC) and the electric utilities conducted conceptual design study on various types of plant concepts and compared these concepts based on technical feasibility and economical perspective. The Pb-Bi cooled complete natural circulation reactor concept may attain high safety level and construction cost goal (Yen 200,000/kWe) (authors)

2002-07-01

476

FMDP Reactor Alternative Summary Report: Volume 2 - CANDU heavy water reactor alternative  

Energy Technology Data Exchange (ETDEWEB)

The Department of Energy Office of Fissile Materials Disposition (DOE/MD) initiated a detailed analysis activity to evaluate each of ten plutonium disposition alternatives that survived an initial screening process. This document, Volume 2 of a four volume report, summarizes the results of these analyses for the CANDU reactor based plutonium disposition alternative.

1996-09-01

477

Efficiency of preliminary transmutation of actinides before ultimate storage  

International Nuclear Information System (INIS)

The concept of preliminary transmutation of minor actinides before placement to the long-term storage is considered. The purpose of such preliminary transmutation before ultimate storage is to incinerate a part of actinides and to transform another part into new actinides providing low level of radiotoxicity accumulated in the storage. Modes of transmutation in reactors of PWR, PHWR (CANDU), and Superfenix types are compared. Among power reactors, heavy-water PHWR type reactor is most acceptable for preliminary transmutation. (author)

2003-04-20

478

Design and procurement report for the FFTF fuel handling systems bottom-loading transfer cask  

International Nuclear Information System (INIS)

The Fast Flux Test Facility (FFTF) bottom-loading transfer cask (BLTC) system is designed to provide ex-vessel fuel transfers of irradiated reactor components between the reactor containment building and the LMFBR shipping cask in the reactor service building. This system is being procured from National Lead Industries, Wilmington, Delaware, under management of Aerojet Manufacturing Company.

1975-11-16

479

Afterheat assessment for conceptual tokamak reactors  

International Nuclear Information System (INIS)

Afterheat represents an important consideration in design of conceptual fusion power reactors, particularly during normal or unplanned shutdown. Afterheat calculations have been undertaken for various generic designs, but with special reference to the Culham DEMO reactor. These calculations have included the redistribution of heating by gamma ray transport. Selected temperature response calculations have been undertaken. (author).

1987-12-01

480

Use of the acoustic method for checking the quality of concrete of hydroelectric and pumped storage stations  

Energy Technology Data Exchange (ETDEWEB)

This article describes acoustic methods used in the in-service inspection of the dams and peripheral concrete structures of the Toktogul, Kurpsai, and Bratsk hydroelectric and pumped storage plants. The tests were conducted to assess the compression strength, elasticity, and tensile strength of the concretes. Comparative evaluations against drill core studies proved the acoustic methods to be sufficiently accurate in predicting aging behavior and loss of mechanical and physical integrity in the concretes.

1987-09-01

481

Thailand: utilisation programme set for massive expansion  

Energy Technology Data Exchange (ETDEWEB)

The US$360 million project to increase gas supplies to Eastern and Southern Thailand is discussed, and the use of international competitive bidding to purchase the line pipe and other facilities is reported. The government approved proposal for a gas fired combined-cycle power station and gas separation plant are discussed. (UK).

1991-11-01

482

Supervision monitoring for radiation environment around Daya Bay and Lingao nuclear power stations  

International Nuclear Information System (INIS)

This paper systematically introduces the supervision monitoring for radiation environment around the Guangdong Daya Bay and Ling Ao nuclear power station by the Guangdong Environmental Radiation Research and Monitoring Center. It includes the monitoring plan, methods, quality assurance, main results and conclusions. The results show that: (1) The gas discharge have not caused any detectable impacts to the terrestrial and atmospheric environment since their operation; (2) "1"1"0"mAg could only be detected in seawater in the West Daya Bay in 1995 and 1997 and in sediments in 1997. The maximum annual average in seawater was 3.1 Bq/m"3, annual average of "1"1"0"mAg in sediments was 1.0 Bq/kg(dry). But it was always detectable in pearl oyster, gulfweed and cuttlefish in the West Daya Bay. The "1"1"0"mAg concentrations in halobios were relatively higher in 1994, 1996 and 1997. The maximum concentrations in pearl oyster, gulfweed and cuttlefish were 2.2, 1.7 and 5.8 Bq/kg ...

2004-05-01

483

Study of Water Quality Value in Sub of the Stream Area of Cisadane Rivers Upstream as Reference Area Based on Macro invertebrate Composition  

International Nuclear Information System (INIS)

Specific structure of biota community condition can used as indicator for the ecosystem stability value or the waters pollution level where the aquatic biota exist. the macro invertebrates as bio indicator organism can used to assess the upper Cisadane Sub River Basin water quality. The grouping and calculation result from family number, Ept presences (sensitive macro invertebrate), Diversity index (H"'), DO value and TOC value showed 5 criteria of water quality as reference site. This criteria is used to determine water quality level from ten branches of rivers in the upper Cisadane Sub River Basin, Cijeruk districts. The biotic index calculation for ASPT (Average Score Per Taxon) and T and T (index Trihadiningrum and Tjindronegoro) is used to asses water quality based on macro invertebrate composition indicator. Both biotic index system support and give the similar evaluation to water quality level from ten branches of river on the upper Cisadane Sub River Basin. The water quality ...

2001-11-01

484

Shuttle Showcase: STS-124  

National Aeronautics and Space Administration (NASA)

The second in a series of flights to assemble the Japanese segment of the International Space Station saw the mammoth Kibo module delivered to the complex complements of Discovery and its crew on the STS-124 mission. Kibo, the Japanese word for u201chopeu201d would house dozens of experiments and serve as a platform for external payloads brought to the complex on subsequent Shuttle flights and the Japanese u201cKounotoriu201d H-2 Transfer Vehicle cargo ship.

2011-07-10

485

Principles of ground relaying for high voltage and extra high voltage transmission lines  

Energy Technology Data Exchange (ETDEWEB)

This paper is a tutorial discussion of the basic principles of ground relaying for high voltage and extra high voltage transmission lines. Three different HV configurations are considered: Long lines, lines with a weak mid-point station, and mutually-coupled lines. Application criteria for EHV circuits are also discussed, and specific setting calculations are included where appropriate.

1983-02-01

486

Plant for processing sewage gas to natural-gas quality  

Energy Technology Data Exchange (ETDEWEB)

Sewage gas or biogas as a product of anaerobic digestion contains methane and carbon dioxide as its main components. Biogas is scrubbed off carbon dioxide in absorption columns and purified to natural-gas quality. The purified gas then is piped to the gas pressure control station and fed into the public network. Description of process and plant is given.

1983-09-01

487

Occupational exposure information system in Daya Bay Nuclear Power Station  

International Nuclear Information System (INIS)

This paper introduces an occupational exposure information system in detail, which is developed and in operation presently by Daya Bay nuclear power plant. It is presented in the paper that individual dose monitoring items and method, design and classification of database configuration, statistics and analysis of individual dose, and management of staff entering and exiting controlled area. The system is instructive to analysing individual dose and optimizing radiation protection measures. (authors)

2005-07-01

488

Monitoring, sampling and analysis of fine particulates -- Results and experiences from DOE's Federal Energy Technology Center  

Energy Technology Data Exchange (ETDEWEB)

The overall goal of the DOE fine particulate program is to ensure that the best science and technology is available for any regulatory decision-making related to the health and environmental impacts of ambient fine particulate matter and regional haze. Interest primarily lies in the particulate fraction having aerodynamic diameters of 2.5 microns and less (PM2.5). Particulates of this size are the focus of the newly established National Ambient Air Quality Standards. As such, the Federal Energy Technology Center (FETC) is establishing a fine particulate sampling station at the Center's Pittsburgh site located in South Park Township, PA. This sampling station is one of a group of stations scattered throughout Pennsylvania, West Virginia, and Ohio that constitute the Upper Ohio River Valley Project. The station is equipped with a full complement of fine particulate and gaseous monitors including ...

1999-07-01

489

Human error and experienced feedback during refuelling overhauling of Daya Bay Nuclear Power Station  

International Nuclear Information System (INIS)

The authors describe the various human error encountered during Daya bay refueling overhaul, and the subsequent root cause evaluation and protective measure. Authors consider transparency is the key in reducing human error and event recurrence. Additional y, event transparency will enhance the effectiveness if experience feedback and reduce event consequence

2000-10-01

490

Grid-Search Location Methods for Ground-Truth Collection From Local and Regional Seismic Networks  

Energy Technology Data Exchange (ETDEWEB)

This project investigated new techniques for improving seismic event locations derived from regional and local networks. The technqiues include a new approach to empirical travel-time calibration that simultaneously fits data from multiple stations and events, using a generalization of the kriging method, and predicts travel-time corrections for arbitrary event-station paths. We combined this calibration approach with grid-search event location to produce a prototype new multiple-event location method that allows the use of spatially well-distributed events and takes into account correlations between the travel-time corrections from proximate event-station paths. Preliminary tests with a high quality data set from Nevada Test Site explosions indicated that our new calibration/location method offers improvement over the conventional multiple-event location methods now in common use, and is applicable to more general ...

2005-05-13

491

Foshan. A fast track combined cycle for Guangdong  

Energy Technology Data Exchange (ETDEWEB)

To meet growth in the fast developing Pearl River Delta economic zone in China`s Guangdong province, a 270 MW oil-fired combined cycle at Foshan was built and commissioned in only 22 months from financial closure. This article describes the Foshan power station, specifications, design, procurement, construction and operating concerns. 5 figs.

1995-03-01

492

Electricity supply in the United Kingdom. Brief details and statistics  

Energy Technology Data Exchange (ETDEWEB)

Statistical detail is given of the electricity generation and transmission systems in the UK. Breakdown by type of station, by fuel and the proportion generated by others apart from the generating or area boards is presented. Figures are provided for the various high voltage transmission lines in terms of route and circuit length as well as the number of towers and the capacity of mains transformers.

1987-06-01

493

ECONOMICS OF RETROFITTING BIG RIVERS ELECTRIC CORPORATION'S LIME-BASED FGD (FLUE GAS DESULFURIZATION) SYSTEM TO ORGANIC-ACID-ENHANCED LIMESTONE OPERATIONS  

Science.gov (United States)

The report describes the site specific changes required to convert an existing lime FGD system to a limestone system enhanced by dibasic acid (DBA) or adipic acid, and the costs of making such a change. In 1982-83, pilot plant tests were conducted at the R. D. Green Station of Bi...

494

Chalk Point Cooling Tower Project: Cooling Tower Effects on Crops and Soils. Preoperational Report, Appendix.  

Science.gov (United States)

This report contains data collected on a monthly basis over the period April, 1973 - April, 1975 for dustfall particulates, sodium and chloride and SO2 levels obtained from 12 monitoring sites near the Chalk Point Generating Station operated by PEPCO and ...

1976-01-01

495

Chalk Point Cooling Tower Project: Cooling Tower Effects on Crops and Soils. Post Operational Report No. 2.  

Science.gov (United States)

This report contains a summary of monthly dustfall, SO2, rainfall, crops and soils information obtained over the period May, 1976 to March, 1977 from 12 monitoring sites near the Chalk Point Generating Station operated by PEPCO which is located 65 km sout...

1977-01-01

496

Chalk Point Cooling Tower Project. Volume 2. Cooling Tower Drift Dye Tracer Experiment, June 16 and 17, 1977.  

Science.gov (United States)

A drift dye tracer experiment, using Rhodamine (WT) dye, was conducted on airborne drift from a natural draft cooling tower at PEPCO's Chalk Point, Maryland Power Generating Station. This experiment was designed to separate and identify cooling tower aero...

1977-01-01

497

Advancements in electric and hybrid electric vehicle technology  

Energy Technology Data Exchange (ETDEWEB)

Contents of this volume include: Influence of Battery Characteristics on Traction Drive Performance; Chassis Design for a Small Electric City Car; Thermal Comfort of Electric Vehicles; Power Quality Problems at Electric Vehicle`s Charging Station; The Development and Performance of the AMPhibian Hybrid Electric Vehicle; The Selection of Lead-Acid Batteries for Use in Hybrid Electric Vehicles; and more.

1994-12-31

498

18-months cycle reload design verifications of Daya Bay Nuclear Power Station  

International Nuclear Information System (INIS)

18-Months cycle reload design verifications of Daya Bay NPS is briefly described. It was attempted giving the description of analysis scope and key technology for a nuclear power plant which will be changed fuel management strategy from one year to 18-months cycle

2002-10-01