ASME XI stroke time testing of solenoid valves at Connecticut Yankee Station

Energy Technology Data Exchange (ETDEWEB)

Martin, C.W.

1996-12-01

Connecticut Yankee Atomic Power Company has developed the capability of measuring the stroke times of AC and DC solenoid valves. This allows the station to measure the stroke time of any solenoid valve in the plant, even those valves which do not have valve stem position indicators. Connecticut Yankee has adapted the ITI MOVATS Checkmate 3 system, using a signal input from a Bruel and Kjaer (B&K) Model 4382 acoustic accelerometer and the Schaumberg Campbell Associates (SCA) Model SCA-1148 dual sensor, which is a combined accelerometer and gaussmeter.

ASME XI stroke time testing of solenoid valves at Connecticut Yankee Station

International Nuclear Information System (INIS)

Martin, C.W.

1996-01-01

Connecticut Yankee Atomic Power Company has developed the capability of measuring the stroke times of AC and DC solenoid valves. This allows the station to measure the stroke time of any solenoid valve in the plant, even those valves which do not have valve stem position indicators. Connecticut Yankee has adapted the ITI MOVATS Checkmate 3 system, using a signal input from a Bruel and Kjaer (B ampersand K) Model 4382 acoustic accelerometer and the Schaumberg Campbell Associates (SCA) Model SCA-1148 dual sensor, which is a combined accelerometer and gaussmeter

Safety Evaluation Report, pump and valve inservice testing program, Yankee Rowe Nuclear Power Station (Docket No. 50-29). Revision 1

International Nuclear Information System (INIS)

Ransom, C.B.; Rockhold, H.C.

1985-10-01

The staff reviewed the Yankee Rowe IST program submittal dated October 2, 1981 and evaluated the proposed tests for compliance with the requirements of the ASME Boiler and Pressure Vessel Code, Section XI, 1977 Edition, through the Summer of 1978 Addenda. Those items not in compliance were discussed in a working session with Yankee Atomic Electric Company personnel, USNRC representatives, and EG and G Idaho reviewers on June 22, 1982. The evaluations presented in this SER of the Yankee Rowe pump and valve inservice testing program and the associated relief requests are those of the NRC staff. These findings apply only to component testing

78 FR 50458 - Entergy Nuclear Operations, Inc., James A. Fitzpatrick Nuclear Power Plant, Vermont Yankee...

Science.gov (United States)

2013-08-19

... Nuclear Operations, Inc., James A. Fitzpatrick Nuclear Power Plant, Vermont Yankee Nuclear Power Station... that the NRC take action with regard to James A. Fitzpatrick Nuclear Power Plant, Vermont Yankee.... Fitzpatrick Nuclear Power Plant (Fitzpatrick), Vermont Yankee Nuclear Power Station (Vermont Yankee), and...

77 FR 48565 - Maine Yankee Atomic Power Company, Maine Yankee Independent Spent Fuel Storage Installation...

Science.gov (United States)

2012-08-14

... reduction in a margin of safety nor creates a new or different kind of accident from any accident previously... the probability or consequences of an accident previously evaluated; (ii) granting the exemption would... would not result in a significant construction impact because there are no construction activities...

Auxiliary feedwater system risk-based inspection guide for the Maine Yankee Nuclear Power Plant

International Nuclear Information System (INIS)

Gore, B.F.; Vo, T.V.; Moffitt, N.E.; Bumgardner, J.D.

1992-10-01

In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. The information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. Maine Yankee was selected as one of a series of plants for study. ne product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the Maine Yankee plant

Technical evaluation of the electrical, instrumentation, and control design aspects of the low temperature overpressure protection system for the Maine Yankee nuclear power plant

International Nuclear Information System (INIS)

Latorre, V.R.; Mayn, B.G.

1979-08-01

This report documents the technical evaluation of the electrical, instrumentation, and control design aspects for the low temperature overpressure protection system of the Maine Yankee nuclear power plant. Design basis criteria used to evaluate the acceptability of the system included operator action, system testability, single failure criterion, and seismic Category I and IEEE Std-279-1971 criteria

Determination of the neutron flux for the Yankee Rowe experiment in the Ford Nuclear Reactor

International Nuclear Information System (INIS)

Cacciapouti, R.J.; Petrusha, L.

1994-01-01

Yankee Atomic Electric Company undertook a Test Irradiation Program at the Ford Nuclear Reactor of the University of Michigan. The program was implemented to characterize the irradiation response of representative Yankee Rowe reactor vessel beltline plate materials. The program was also intended to remove uncertainties in the existing reactor vessel fluence and damage predictions on the Yankee Rowe reactor vessel steel. Since this is the first in-core experiment of this type for the Ford Nuclear Reactor, the measurement of the reaction rate and the estimate of the fluence are presented

Examination of failed studs from No. 2 steam generator at the Maine Yankee Nuclear Power Station

International Nuclear Information System (INIS)

Czajkowski, C.

1983-02-01

Three studs removed from service on the primary manway cover from steam generator No. 2 of the Maine Yankee station were sent to Brookhaven National Laboratory (BNL) for examination. The examination consisted of visual/dye penetrant examination, optical metallography and Scanning Electron Microscopy/Energy Dispersive Spectroscopy (SEM/EDS) evaluation. One bolt was through cracked and its fracture face was generally transgranular in nature with numerous secondary intergranular cracks. The report concludes that the environmenally assisted cracking of the stud was due to the interaction of the various lubricants used with steam leaks associated with this manway cover

76 FR 19148 - Entergy Nuclear Operations, Inc., Entergy Nuclear Vermont Yankee, LLC, Vermont Yankee Nuclear...

Science.gov (United States)

2011-04-06

... NUCLEAR REGULATORY COMMISSION [Docket No. 50-271; License No. DPR-28; NRC-2011-0074] Entergy Nuclear Operations, Inc., Entergy Nuclear Vermont Yankee, LLC, Vermont Yankee Nuclear Power Station..., ``Requests for Action under this Subpart,'' the U.S. Nuclear Regulatory Commission (NRC) take action with...

Nuclear Regulatory Commission Issuances, Volume 44, No. 5

International Nuclear Information System (INIS)

1996-11-01

This report includes the issuances received in November 1996. Issuances are from the Commission, the Atomic Safety and Licensing Boards, and the Directors' Decisions. Seven issuances were received and are abstracted individually in the database: Emerick S. McDaniel, U.S. Enrichment Corporation, Sequoyah Fuels Corporation and General Atomics, all power reactor licensees, Florida Power and Light Company, Maine Yankee Atomic Power Company, and Northern States Power Company. No issuances were received from the the Administrative Law Judges or the Decisions on Petitions for Rulemaking

Yankee Rowe SPDS development and its validation and verification

International Nuclear Information System (INIS)

Candon, D.; Cain, D.

1986-01-01

The decision to proceed with EPRI on a prototypical Safety Parameter Display System (SPDS) was made by Yankee Atomic Electric Company management. The general direction to the implementors was to decide from whom would the SPDS be designed, to decide how the SPDS would coincidentally support the twin goals of meeting the regulations and the corporate objective to generate electricity safely and efficiently, and to decide what was known and proven in the arena of computer graphics to minimize cognitive dissonance between the final product SPDS and the operators

Review of reactor pressure vessel evaluation report for Yankee Rowe Nuclear Power Station (YAEC No. 1735)

International Nuclear Information System (INIS)

Cheverton, R.D.; Dickson, T.L.; Merkle, J.G.; Nanstad, R.K.

1992-03-01

The Yankee Atomic Electric Company has performed an Integrated Pressurized Thermal Shock (IPTS)-type evaluation of the Yankee Rowe reactor pressure vessel in accordance with the PTS Rule (10 CFR 50. 61) and a US Regulatory Guide 1.154. The Oak Ridge National Laboratory (ORNL) reviewed the YAEC document and performed an independent probabilistic fracture-mechnics analysis. The review included a comparison of the Pacific Northwest Laboratory (PNL) and the ORNL probabilistic fracture-mechanics codes (VISA-II and OCA-P, respectively). The review identified minor errors and one significant difference in philosophy. Also, the two codes have a few dissimilar peripheral features. Aside from these differences, VISA-II and OCA-P are very similar and with errors corrected and when adjusted for the difference in the treatment of fracture toughness distribution through the wall, yield essentially the same value of the conditional probability of failure. The ORNL independent evaluation indicated RT NDT values considerably greater than those corresponding to the PTS-Rule screening criteria and a frequency of failure substantially greater than that corresponding to the ''primary acceptance criterion'' in US Regulatory Guide 1.154. Time constraints, however, prevented as rigorous a treatment as the situation deserves. Thus, these results are very preliminary

75 FR 54400 - Florida Power and Light Company; Establishment of Atomic Safety and Licensing Board

Science.gov (United States)

2010-09-07

...] Florida Power and Light Company; Establishment of Atomic Safety and Licensing Board Pursuant to delegation..., notice is hereby given that an Atomic Safety and Licensing Board (Board) is being established to preside over the following proceeding: Florida Power & Light Company (Turkey Point Units 6 and 7) This...

76 FR 51065 - Florida Power & Light Company; Establishment of Atomic Safety and Licensing Board

Science.gov (United States)

2011-08-17

... & Light Company; Establishment of Atomic Safety and Licensing Board Pursuant to delegation by the... hereby given that an Atomic Safety and Licensing Board (Board) is being established to preside over the following proceeding: Florida Power & Light Company (St. Lucie Plant, Unit 1) This proceeding involves a...

Maine Yankee Atomic Power Plant. Annual operating report: January--December 1976

International Nuclear Information System (INIS)

1977-01-01

Net electrical energy generated was 5,928,868 MWH with the generator on line 8,347.6 hrs. Information is presented concerning operating experience; specification procedural, and design changes; surveillance tests; containment leak testing; maintenance; licensee events reports; power generation, shutdowns and load reductions; personnel radiation exposures; and primary coolant chemistry

Data logger system of Tokai (I) Nuclear Power Station, the Japan Atomic Power Company

International Nuclear Information System (INIS)

Machida, Akira; Chikahata, Kiyomitsu; Nakamura, Mamoru; Nanbu, Taketoshi; Kawakami, Hiroshi

1977-01-01

The Tokai(I) nuclear power station, the Japan Atomic Power Company, was commissioned in July, 1966. In this station, temperatures of about 700 points are monitored and recorded with a data logger. However, the logger was manufactured some 15 years ago, therefore it is now old-fashioned, and has caused frequent failures these 2 or 3 years. So it was decided to replace it with a new one, and the process control computer, U-300 system including CRT display, has been adopted considering the latest trend in U.K. The control and monitoring system in this station is not a centralized control system, but a distributed control system divided into three control rooms, namely main control room, turbine generator control room and fuel exchanger (cask machine) control room. Therefore for grasping the complete plant conditions at the main control room, the system has not been convenient, and the centralization of data processing has been desired from the viewpoint of operation. The new logger system is composed so as to facilitate the centralized monitoring in the main control room, considering the above requirement. It has been improved so as to have seven important functions in addition to the existing functions. Hardware and software of this system are briefly explained. The new system was started up in February 1977, and is now operating well, though some early failures were experienced. (Wakatsuki, Y.)

RETRAN-02 analysis of upper head cooling during controlled natural circulation cooldown of Yankee Nuclear Power Station

International Nuclear Information System (INIS)

Fujita, N.; Helrich, R.E.; Bergeron, P.A.

1982-01-01

RETRAN-02 is particularly well-suited for investigating the fluid conditions in the upper head during a natural circulation cooldown. The RETRAN input model was developed with four basic objectives: (1) accurate description of the upper head cooling mechanisms; (2) proper simulation of natural circulation; (3) respresentations of operator actions required to proceed from full-power to shutdown-cooling-system conditions using both automatic and manual controls; and (4) reduction of the computer cost of simulating this evolution of approximately 10-hour duration. The response of the upper head fluid temperature calculated by RETRAN was in close agreement with measured data obtained from a natural circulation cooldown experiment performed for the Connecticut Yankee Plant, whose design is very similar to the Yankee Nuclear Power Station

75 FR 33853 - Maine Yankee Atomic Power Company; Independent Spent Fuel Storage Installation; Issuance of...

Science.gov (United States)

2010-06-15

... previously evaluated by the NRC, and it was determined to pose no increased risk to health and safety. The... has the potential to cause effects on historic or cultural properties, assuming such properties are... differences in environmental impact between the proposed action and the alternative considered and that the...

An aerial radiological survey of the Vermont Yankee Nuclear Power Station and surrounding area, Vernon, Vermont

International Nuclear Information System (INIS)

Reiman, R.; Bluitt, C.M.

1993-10-01

An aerial radiological survey was conducted over the Vermont Yankee Nuclear Power Station in Vernon, Vermont, during the period August 7 through August 17, 1989. The survey was conducted at an altitude of 300 feet (91 meters) over a 65-square-mile (168-square-kilometer) area centered on the power station. The purpose of the survey was to document the terrestrial gamma radiation environment of the Vermont Yankee Power Station and surrounding area. The results of the aerial survey are reported as inferred gamma radiation exposure rates at 1 meter above ground level in the form of a contour map. Outside the plant boundary, exposure rates were found to vary between 6 and 10 microroentgens per hour (μR/h) and were attributed to naturally occurring uranium, thorium, and radioactive potassium gamma emitters. The aerial data were compared to ground-based open-quotes benchmarkclose quotes exposure rate measurements and radionuclide assays of soil samples obtained within the survey boundary. The ground-based measurements were found to be in good agreement with those inferred from the aerial measuring system

An aerial radiological survey of the Yankee Rowe Nuclear Power Station and surrounding area, Rowe, Massachusetts

International Nuclear Information System (INIS)

Boyns, P.K.; Bluitt, C.M.

1993-09-01

An aerial radiological survey was conducted over the Yankee Rowe Nuclear Power Station in Rowe, Massachusetts, during the period August 17--24, 1989. The survey was conducted at an altitude of 300 feet (91 meters) over an 87-square-mile (225-square-kilometer) area centered on the power station. The purpose of the survey was to document the terrestrial gamma radiation environment of the Yankee Rowe Power Station and the surrounding area. The results of the aerial survey are reported as inferred gamma radiation exposure rates at 1 meter above ground level in the form of a contour map. Outside the plant boundary, exposure rates were found to vary between 6 and 10 microroentgens per hour (μR/h) and were attributed to naturally-occurring uranium, thorium, and radioactive potassium gamma emitters. The aerial data were compared to ground-based ''benchmark'' exposure rate measurements and radionuclide assays of soil samples obtained within the survey boundary. The ground-based measurements were found to be in good agreement with those inferred from the aerial measuring system

76 FR 41532 - Yankee Atomic Electric Company, Yankee Nuclear Power Station (Yankee-Rowe); Notice of...

Science.gov (United States)

2011-07-14

... electronic submission through the NRC E-filing system. Requests for a hearing and petitions for leave to... entities participating under 10 CFR 2.315(c), must be filed in accordance with the NRC E-Filing rule (72 FR 49139, August 28, 2007). The E-Filing process requires participants to submit and serve all adjudicatory...

Evaluation of BWROG EPG level/power control strategy for Vermont Yankee

International Nuclear Information System (INIS)

Chandola, V.; Robichaud, J.D.

1987-01-01

The current Boiling Water Reactor Owner's Group (BWROG) emergency procedure guidelines (EPGs) direct reactor operators to manually lower the reactor pressure vessel (RPV) water level to the top of active fuel (TAF) during an anticipated transient without scram (ATWS) event. Lowering the water level reduces the core inlet flow, thereby reducing core power. However, reducing water level is contrary to current operator training, which requires that normal RPV water level be maintained to assure core cooling. In addition, the indicated water level near TAF using cold calibrated level instrumentation may not be reliable, which could potentially result in uncovering the core. This paper evaluates the EPGs' level/power control strategy for the Vermont Yankee plant and proposes alternative to the BWROG guidelines as applied to ATWS response

75 FR 10833 - In the Matter of Entergy Nuclear Operations; Vermont Yankee Nuclear Power Station; Demand for...

Science.gov (United States)

2010-03-09

... NUCLEAR REGULATORY COMMISSION [Docket No. 05000271; License No. DPR-28; EA-10-034; NRC-2010-0089] In the Matter of Entergy Nuclear Operations; Vermont Yankee Nuclear Power Station; Demand for... this Demand for Information, the following information, in writing, and under oath or affirmation: 1...

Fabrication data package for HEDL-RI dosimetry in the Maine Yankee Replacement Surveillance Capsule 263 and cavity positions

International Nuclear Information System (INIS)

Kellogg, L.S.; Ulseth, J.A.; Lippincott, E.P.; Oliver, B.; Farrar, H.

1982-12-01

This document provides a complete description of dosimetry fabricated for the Maine Yankee Surveillance Capsule Number 263 and three azimuthal positions in the reactor cavity. Surveillance Capsule 263 was originally scheduled for insertion in October 1982, but will be held in reserve for future use, pending establishment of an equilibrium low leakage core burnup distribution. The cavity dosimetry is scheduled for insertion in November 1982

Nuclear Regulatory Commission issuances. Volume 44, Number 3

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-09-01

This report includes issuances received during September 1996. After reviewing in detail each of the claims made in this informal proceeding the presiding officer sustained the staff of the USNRC in its determination that the applicant did not pass the written portion of his examination to become a licensed operator of a nuclear power plant. In the proceeding concerning citizen group challenges to the decommissioning plan for the Rowe Yankee power station, the licensing board grants licensee Yankee Atomic Electric Company`s motion for summary disposition.

75 FR 33653 - Connecticut Yankee Atomic Power Company; Notice of Consideration of Issuance of Amendment to...

Science.gov (United States)

2010-06-14

... Company; Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards; Consideration Determination, and Opportunity for a Hearing The U.S. Nuclear Regulatory... the amendment request involves no significant hazards consideration. Under the Commission's...

Effects of respirator use on worker performance

Energy Technology Data Exchange (ETDEWEB)

Cardarelli, R. [Yankee Atomic Electric Co., Bolton, MA (United States)

1995-03-01

In 1993, EPRI funded Yankee Atomic Electric Company to examine the effects of respirator use on worker efficiency. Phase I of Yankee`s effort was to develop a study design to determine respirator effects. Given success in Phase I, a larger population will be tested to determine if a stasitically significant respirator effect on performance can be measured. This paper summarizes the 1993 EPRI/Yankee Respirator Effects of Pilot Study, and describes the study design for the 1994 EPRI/Yankee Respirator Study to be conducted at the Oyster Creek Nuclear Power Plant. Also described is a summary of respirator effect studies that have been conducted during the last ten (10) years.

Joint Regulation of Radionuclides at Connecticut Yankee Haddam Neck Plant - Finding Common Ground and Lessons Learned

International Nuclear Information System (INIS)

Peters, J.; Glucksberg, N.; Fogg, A.; Couture, B.

2006-01-01

During the site closure of nuclear facilities where both radionuclides and chemicals are present in environmental media, state and federal regulatory agencies other than the Nuclear Regulatory Commission often have a stake in the regulation of the site closure process. At the Connecticut Yankee Atomic Power Company (CYAPCO) Haddam Neck Plant in Haddam, Connecticut, the site closure process includes both radiological and chemical cleanup which is regulated by two separate divisions within the state and two federal agencies. Each of the regulatory agencies has unique closure criteria which pertain to radionuclides and, consequently, there is overlapping and in some cases disparate regulation of radionuclides. Considerable effort has been expended by CYAPCO to find common ground in meeting the site closure requirements for radionuclides required by each of the agencies. This paper discusses the approaches that have been used by CYAPCO to address radionuclide site closure requirements. Significant lessons learned from these approaches include the demonstration that public health cleanup criteria for most radionuclides of concern at nuclear power generation facilities are protective for chemical toxicity concerns and are protective for ecological receptors and, consequently, performing a baseline ecological risk assessment for radionuclides at power generation facilities is not generally necessary. (authors)

Results of small break LOCA analysis for Kuosheng nuclear power plant using the RELAP5YA computer code

International Nuclear Information System (INIS)

Wang, L.C.; Jeng, S.C.; Chung, N.M.

2004-01-01

One lesson learned from the Three Mile Island (TMI) accident was the analysis methods used by Nuclear Steam Supply System (NSSS) vendors and/or nuclear fuel suppliers for small break Loss Of Coolant Accident (LOCA) analysis for compliance with appendix K to 10CFR50 should be revised, documented and submitted for USNRC approval and the plant-specific calculations using NRC-approved models for small-break LOCA to show compliance with 10CFR50.46 should be submitted for NRC approval. A study by Taiwan Power Company (TPC) under the guidance of Yankee Atomic Electric Company (YAEC) has been undertaken to perform this analysis for Kuosheng nuclear power plant. This paper presents the results of the analysis that are useful in satisfying the same requirements of the Republic Of China Atomic Energy Commission (ROCAEC). (author)

Expanded spent fuel storage project at Yankee Atomic Electric Plant

International Nuclear Information System (INIS)

Chin, S.L.

1980-01-01

A detailed discussion on the project at the Yankee Rowe power reactor for expanding the capacity of the at-reactor storage pool by building double-tier storage racks. Various alternatives for providing additional capacity were examined by the operators. Away-from-reactor alternatives included shipment to existing privately owned facilities, a regional independent storage facility, and transshipments to other New England nuclear power plant pools. At-reactor alternatives evaluated included a new pool modification of the existing structure and finally, modification of the spent fuel pit. The establishment of a federal policy precluding transshipment of spent fuel prohibited the use of off-site alternatives. The addition of another pool was too expensive. The possibility of modifying an existing on-site structure required a new safety evaluation by the regulatory group with significant cost and time delays. Therefore, the final alternative - utilizing the existing spent fuel pool with some modification - was chosen due to cost, licensing possibility, no transport requirements, and the fact that the factors involved were mainly under the control of the operator. Modification of the pool was accomplished in phases. In the first phase, a dam was installed in the center of the pool (after the spent fuel was moved to one end). In the second phase, the empty end of the pool was drained and lined with stainless steel and the double-tier rack supports were added. In the third phase, the pool was refilled and the dam was removed. Then the spent fuel was moved into the completed end. In the fourth phase, the dam was replaced and the empty part of the pool was drained. The liner and double-tier rack supports were installed, the pool was refilled, and the dam was removed.The project demonstrated that the modification of existing spent fuel fuel pools for handling double-tier fuel racks is a viable solution for increasing the storage capacity at the reactor

Nuclear Regulatory Commission issuances, Volume 44, No. 4

International Nuclear Information System (INIS)

1996-10-01

This report includes the issuances received in October 1996. Issuances are from the Commission, the Atomic Safety and Licensing Boards, and the Directors' Decisions. 15 issuances were received and are abstracted individually in the database: Louisiana Energy Services, U.S. Enrichment Corporation, Yankee Atomic Electric Company, General Public Utilities Nuclear Corporation, James L. Shelton, Juan Guzman, Northern States Power Company, TESTCO Inc., Washington Public Power Supply System, all nuclear plants, Cleveland Electric Illuminating Company, Duke Power Company, Florida Power Corporation, and Northeast Nuclear Energy Company (2 issuances). No issuances were received from the the Administrative Law Judges or the Decisions on Petitions for Rulemaking

Nuclear Regulatory Commission issuances, Volume 44, No. 4

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-10-01

This report includes the issuances received in October 1996. Issuances are from the Commission, the Atomic Safety and Licensing Boards, and the Directors` Decisions. 15 issuances were received and are abstracted individually in the database: Louisiana Energy Services, U.S. Enrichment Corporation, Yankee Atomic Electric Company, General Public Utilities Nuclear Corporation, James L. Shelton, Juan Guzman, Northern States Power Company, TESTCO Inc., Washington Public Power Supply System, all nuclear plants, Cleveland Electric Illuminating Company, Duke Power Company, Florida Power Corporation, and Northeast Nuclear Energy Company (2 issuances). No issuances were received from the the Administrative Law Judges or the Decisions on Petitions for Rulemaking.

Anticipated corrosion in the Vermont Yankee spent fuel pool

International Nuclear Information System (INIS)

Weeks, J.R.

1977-06-01

The report provides additional information relating to a proposed modification to the spent fuel pool at the Vermont Yankee Nuclear Power Station (VYNPS) and addresses corrosion of spent fuel pool storage materials and zircaloy, and provides an analysis of the effectiveness of the Boral sealing

Nuclear Regulatory Commission issuances. Volume 44, Number 3

International Nuclear Information System (INIS)

1996-09-01

This report includes issuances received during September 1996. After reviewing in detail each of the claims made in this informal proceeding the presiding officer sustained the staff of the USNRC in its determination that the applicant did not pass the written portion of his examination to become a licensed operator of a nuclear power plant. In the proceeding concerning citizen group challenges to the decommissioning plan for the Rowe Yankee power station, the licensing board grants licensee Yankee Atomic Electric Company's motion for summary disposition

Effort to grapple with improvement of security and reliability of nuclear power plant. Actions of the Japan Atomic Power Company

International Nuclear Information System (INIS)

Ishiguma, Kazuo

2012-01-01

Following the Great Tohoku Earthquake in 2011, Tokai No.2 reactor was shut down automatically. Three of emergency diesel generators worked automatically at loss-of-offsite-power and began to work the cooling system of reactor. The reactor could be kept stable and safe in cold state by management of power from the gas turbine electric generator and power source car. Actions of Japan Atomic Power Company (JAPC) for cold shutdown and Tsunami were stated. Inspection results after the earthquake and testimony of staff was described. Countermeasure of improvement of safety of nuclear power station is explained by ensuring of power source and water supply, crisis management system, countermeasure of accident, ensuring, and training of workers, and action for better understanding of reliance. (S.Y.)

Flexibility analysis of main primary heat transport system : Narora Atomic Power Project

International Nuclear Information System (INIS)

Rastogi, S.K.

1975-01-01

The paper presents flexibility analysis problem of main primary heat transport system and the approximate analysis that has been made to estimate the loads coming on major equipments. The primary heat transport system for Narora Atomic Power Project is adopting vertical steam generators and pumps equally divided on either side of the reactor with inter-connecting pipes and feeders. Since the system is mainly spring supported with movement of a few points in certain direction defined but no anchorage, it represents a good problem for flexibility analysis which can only be solved in one step by developing a good computer programme. (author)

Human factors in atomic power plant

International Nuclear Information System (INIS)

Kawano, Ryutaro

1997-01-01

To ensure safety should have priority over all other things in atomic power plants. In Chernobyl accident, however, various human factors including the systems for bulb check after inspection and communication, troubles in the interface between hardwares such as warning speakers and instruments, and their operators, those in education and training for operators and those in the general management of the plant have been pointed out. Therefore, the principles and the practical measures from the aspect of human factors in atomic power plants were discussed here. The word, ''human factor'' was given a definition in terms of the direct cause and the intellectual system. An explanatory model for human factors, model SHEL constructed by The Tokyo Electric Power Co., Ltd., Inc. was presented; the four letter mean software(S), hardware(H), environment(E) and liveware(L). In the plants of the company, systemic measures for human error factors are taken now in all steps not only for design, operation and repairing but also the step for safety culture. Further, the level required for the safety against atomic power is higher in the company than those in other fields. Thus, the central principle in atomic power plants is changing from the previous views that technology is paid greater importance to a view regarding human as most importance. (M.N.)

Setting of cesium residual ratio of molten solidified waste produced in Japan Atomic Power Company Tokai and Tokai No.2 Power Stations

International Nuclear Information System (INIS)

2013-02-01

JNES investigated the appropriateness of a view of the Japan Nuclear Fuel Co. on cesium residual content and the radioactivity measurement precision regarding the molten solidified (with lowered inorganic salt used) radioactive wastes which were produced from Japan Atomic Power Company Tokai and Tokai No. 2 Power Stations. Based on the written performance report from the request and past disposal confirmation experience, a view of the JNFC is confirmed as appropriate that setting of 15% cesium residual ratio for molten solidified with volume ratio larger than 4% and less than 10% cases. (S. Ohno)

Vermont Yankee simulator BOP model upgrade

International Nuclear Information System (INIS)

Alejandro, R.; Udbinac, M.J.

2006-01-01

The Vermont Yankee simulator has undergone significant changes in the 20 years since the original order was placed. After the move from the original Unix to MS Windows environment, and upgrade to the latest version of SimPort, now called MASTER, the platform was set for an overhaul and replacement of major plant system models. Over a period of a few months, the VY simulator team, in partnership with WSC engineers, replaced outdated legacy models of the main steam, condenser, condensate, circulating water, feedwater and feedwater heaters, and main turbine and auxiliaries. The timing was ideal, as the plant was undergoing a power up-rate, so the opportunity was taken to replace the legacy models with industry-leading, true on-line object oriented graphical models. Due to the efficiency of design and ease of use of the MASTER tools, VY staff performed the majority of the modeling work themselves with great success, with only occasional assistance from WSC, in a relatively short time-period, despite having to maintain all of their 'regular' simulator maintenance responsibilities. This paper will provide a more detailed view of the VY simulator, including how it is used and how it has benefited from the enhancements and upgrades implemented during the project. (author)

Reviewing fluid systems for age-related degradation

International Nuclear Information System (INIS)

Smith, Stan

1991-01-01

Yankee Atomic Electric Company has developed the component degradation assessment tool (CoDAT), an expert system, that aids in handling and evaluating the large amounts of data required to support the license renewal process for nuclear power station fluid systems. In 1990, CoDAT evaluated the Yankee Nuclear Power Station fluid systems for age-related degradation. Its results are now being used to help focus the plant's maintenance programs and manage the expected degradation. CoDAT uses 'If-Then' rules, developed from industry codes, standards and publications, to determine the potential for 19 age-related degradation mechanisms. Other nuclear utilities pursuing the license renewal option also could use CoDAT. (author)

Technical evaluation of the electrical, instrumentation, and control design aspects of the low temperature overpressure protection system for the Yankee Rowe nuclear power plant

International Nuclear Information System (INIS)

Latorre, V.R.; Mayn, B.G.

1979-08-01

This report documents the technical evaluation of the electrical, instrumentation, and control design aspects for the low temperature overpressure protection system of the Yankee Rowe nuclear power plant. Design basis criteria used to evaluate the acceptability of the system included operator action, system testability, single failure criterion, and seismic Category I and IEEE Std-279-1971 criteria

The roles played by the Canadian General Electric Company's Atomic Power Department in Canada's nuclear power program: work, organization and success in APD, 1955-1995

International Nuclear Information System (INIS)

Cantello, G.W.

2003-01-01

This thesis explores the roles played by the Canadian General Electric Company's Atomic Power Department (APD) in Canada's distinctive nuclear power program. From the establishment of APD in 1955 until the completion of the KANUPP project in Pakistan in 1972, the company's strategy encompassed the design, manufacture, and commissioning of entire nuclear power projects in Canada and abroad. APD then developed a specialized role in the design and supply of complete nuclear fuel handling systems, nuclear fuel bundles, and service work, that sustained a thriving workplace. Five key factors are identified as the reasons behind the long and successful history of the department: (1) Strong, capable and efficient management from the start, (2) Flexible organizational structure, (3) Extremely competent design group, (4) Excellent manufacturing, test, commissioning and service capabilities, (5) Correctly identifying, at the right time, the best fields in which to specialize. (author)

Nuclear plant owners move closer to life extension

International Nuclear Information System (INIS)

Smith, D.J.

1991-01-01

A major debate is now underway about the safety of 40-year-old nuclear power plants. Under the Atomic Energy Act of 1954 a nuclear power plant's license is limited to a maximum of 40 years. Although the act permits the renewal of an operating license, it does not outline any standards or procedures for determining when or under what conditions a plant's operating license should be renewed. This paper reports that the Electric Power Research Institute (EPRI) and the U.S. Department of Energy (DOE) are co-sponsors of a program to demonstrate the license renewal process for two nuclear power plants - Yankee Atomic Electric's 175-MW Yankee PWR plant and Northern States Power's 536-MW Monticello BWR plant. The demonstration is known as the lead plant project. Yankee Atomic has already analyzed the plant's condition and evaluated aging using computer-based expert systems and the plant's operating experience. During these tests Yankee Atomic found embrittlement of the reactor vessel

The state of improvement of security management setup in the Japan Atomic Power Company and improvement of facilities in its Tsuruga Nuclear Power Station

International Nuclear Information System (INIS)

1982-01-01

In connection with the series of accidents in the Tsuruga Nuclear Power Station of the Japan Atomic Power Company, the state of security management in JAPC and the safety of facilities in the Tsuruga Nuclear Power Station, which have resulted from improvement efforts, are described on the following items: security management setup - communication and reporting in emergency, the management of inspection and maintenance records, work control and supervision in repair, improvement, etc., functional authority and responsibility in maintenance management, operation management, radiation control, personnel education; improvement of facilities - feed water heaters, laundry waste-water filter room, radioactive waste treatment facility, general drainage, concentrated waste liquid storage tanks in newly-built waste treatment building, etc. (Mori, K.)

Physical decommissioning of the Shippingport Atomic Power Station

International Nuclear Information System (INIS)

Crimi, F.P.

1988-01-01

The Shippingport Atomic Power Station consists of the nuclear steam supply system and associated radioactive waste processing systems, which are owned by the United States Department of Energy (USDOE), and the turbine-generator and balance of plant which is owned by the Duquesne Light Company. The station is located at Shippingport, Pennsylvania on seven acres of land leased by USDOE from the Duquesne Light Company. The Shippingport Station Decommissioning Project (SSDP) is being managed for the USDOE by the General Electric Company and its integated subcontractor, Morrison Knudsen-Ferguson (MK-F) Company. The objectives of the Shippingport Station Decommissioning Project (SSDP) are to: Demonstrate the safe and cost effective dismantlement of a large scale nuclear power plant; Provide useful data for future decommissioning projects

Evaluation of Haddam Neck (Connecticut Yankee) Nuclear Power Plant, environmental impact prediction, based on monitoring programs

International Nuclear Information System (INIS)

Gore, K.L.; Thomas, J.M.; Kannberg, L.D.; Mahaffey, J.A.; Waton, D.G.

1976-12-01

A study was undertaken by the U.S. Nuclear Regulatory Commission (NRC) to evaluate the nonradiological environmental data obtained from three nuclear power plants operating for a period of one year or longer. The document presented reports the second of three nuclear power plants to be evaluated in detail by Battelle, Pacific Northwest Laboratories. Haddam Neck (Connecticut Yankee) Nuclear Power Plant nonradiological monitoring data were assessed to determine their effectiveness in the measurement of environmental impacts. Efforts were made to determine if: (1) monitoring programs, as designed, can detect environmental impacts, (2) appropriate statistical analyses were performed and if they were sensitive enough to detect impacts, (3) predicted impacts could be verified by monitoring programs, and (4) monitoring programs satisfied the requirements of the Environmental Technical Specifications. Both preoperational and operational monitoring data were examined to test the usefulness of baseline information in evaluating impacts. This included an examination of the methods used to measure ecological, chemical, and physical parameters, and an assessment of sampling periodicity and sensitivity where appropriate data sets were available. From this type of analysis, deficiencies in both preoperational and operational monitoring programs may be identified and provide a basis for suggested improvement

Nuclear Regulatory Commission issuances, Volume 46, No. 4

International Nuclear Information System (INIS)

1997-10-01

This report includes the issuances received in October 1997. Issuances are from the Commission, the Atomic Safety and Licensing Boards, and the Directors' Decisions. Five issuances were received on the following subjects: (1) decontamination and decommissioning funding for Sequoyah Fuels Corporation and General Atomics; (2) involvement in NRC-licensed activities by Aharon Ben-Haim; (3) Barnett Industrial X-Ray, Inc.; (4) spent fuel storage installation at Northern States Power Company; and (5) Vermont Yankee Nuclear Power Station. No issuances were received from the the Administrative Law Judges or the Decisions on Petitions for Rulemaking

Nuclear Regulatory Commission issuances, Volume 46, No. 4

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-10-01

This report includes the issuances received in October 1997. Issuances are from the Commission, the Atomic Safety and Licensing Boards, and the Directors` Decisions. Five issuances were received on the following subjects: (1) decontamination and decommissioning funding for Sequoyah Fuels Corporation and General Atomics; (2) involvement in NRC-licensed activities by Aharon Ben-Haim; (3) Barnett Industrial X-Ray, Inc.; (4) spent fuel storage installation at Northern States Power Company; and (5) Vermont Yankee Nuclear Power Station. No issuances were received from the the Administrative Law Judges or the Decisions on Petitions for Rulemaking.

Exxon Nuclear Company WREM-based generic PWR ECCS evaluation model. Appendix C to Volume II. Yankee Rowe example problem

International Nuclear Information System (INIS)

1975-01-01

Core 12, of the Yankee Rowe (YR), plant is to be licensed with the Exxon Nuclear Co. PWR Evaluation Model. This appendix presents methodology and results of an example calculation for the YR plant using the ENC Evaluation Model. This example problem is for the double-ended guillotine cold leg break with a discharge coefficient of 0.6 assuming loss of one emergency diesel. The NSSS supplier has determined this case to give the highest peak cladding temperature (PCT) for Core 11. The YR example problem was performed to determine the maximum acceptable local peak heating rate (Kw/ft). The blowdown was performed with beginning-of-cycle (BOC) ENC fuel at full power with the hot assembly power corresponding to the design peak rod heating rate of 12.9 Kw/ft. The HOT CHANNEL, TOODEE2, and RELAP4-FLOOD runs were made at several reduced hot assembly radial peaks, holding axial peaking constant, until an acceptable PCT was achieved. This procedure results in a PCT of 1834 0 F at a reduced peak linear heating rate of 10.5 Kw/ft for the ENC fuel at BOC. (auth)

Comparison of BR3 Surveillance and Vessel Plates to the Surrogate Plates Representative of the Yankee Rowe PWR Vessel

Energy Technology Data Exchange (ETDEWEB)

Fabry, A.; Chaouadi, R.; Puzzolante, J.L.; Van de Velde, J.; Biemiller, E.C.; Rosinski, S.T.; Carter, R.G

1998-07-01

The sister pressure vessels at the BR3 and Yankee Rowe PWR plants were operated at lower-than-usual temperature ( 260 degrees Celsius) and their plates were austenitized a higher-than-usual temperature (970 degrees Celsius) - a heat treatment leading to a coarser microstructure than is typical for the fine grain plates considered in development of USNRC Regulatory Guide 1.99. The surveillance programs provided by Westinghouse for the two plants were limited to the same A302-B plate representative of the Rowe vessel upper shell plate; this material displayed outlier behaviour characterized by a 41 J Charpy-V Notch shift significantly larger than predicted by Regulatory Guide 1.99. Because lower irradiation temperature and nickel alloying are generally considered detrimental to irradiation sensitivity, there was a major concern that the nickel-modified lower Rate plate and the nickel-modified BR3 plate may become too embrittled to satisfy the toughness requirements embodied in the PTS screening criterion. This paper compares free complementary studies undertaken to clarify these uncertainties: (1) The accelerated irradiation and test program launched in 1990 by Yankee Atomic Electric Company using typical vessel plate materials containing 0.24% copper at two nickel levels: YA1, 0.63 % (A533-B) and YA9, 0.19 (A302-B). These were heat-treated to produce the coarse and fine grain microstructures representative of the Yankee/BR3 and the Regulatory Guide plates, respectively; (2) The BR3 surveillance and vessel testing program: this vessel was wet-annealed in 1984, relicensed for operation till the plant shutdown in 1987, and was trepanned in early 1995; (3) The accelerated irradiations in the Belgian test reactor BR2 of the Yankee coarse grain plates YA1 and YA9 together with BR3 vessel specimens extracted at nozzle elevation, a location with negligible radiation exposure. It is contended that the PTS screening criterion was never attained by the BR3 and Rowe plates, and

Comparison of BR3 Surveillance and Vessel Plates to the Surrogate Plates Representative of the Yankee Rowe PWR Vessel

International Nuclear Information System (INIS)

Fabry, A.; Chaouadi, R.; Puzzolante, J.L.; Van de Velde, J.; Biemiller, E.C.; Rosinski, S.T.; Carter, R.G.

1998-07-01

The sister pressure vessels at the BR3 and Yankee Rowe PWR plants were operated at lower-than-usual temperature ( 260 degrees Celsius) and their plates were austenitized a higher-than-usual temperature (970 degrees Celsius) - a heat treatment leading to a coarser microstructure than is typical for the fine grain plates considered in development of USNRC Regulatory Guide 1.99. The surveillance programs provided by Westinghouse for the two plants were limited to the same A302-B plate representative of the Rowe vessel upper shell plate; this material displayed outlier behaviour characterized by a 41 J Charpy-V Notch shift significantly larger than predicted by Regulatory Guide 1.99. Because lower irradiation temperature and nickel alloying are generally considered detrimental to irradiation sensitivity, there was a major concern that the nickel-modified lower Rate plate and the nickel-modified BR3 plate may become too embrittled to satisfy the toughness requirements embodied in the PTS screening criterion. This paper compares free complementary studies undertaken to clarify these uncertainties: (1) The accelerated irradiation and test program launched in 1990 by Yankee Atomic Electric Company using typical vessel plate materials containing 0.24% copper at two nickel levels: YA1, 0.63 % (A533-B) and YA9, 0.19 (A302-B). These were heat-treated to produce the coarse and fine grain microstructures representative of the Yankee/BR3 and the Regulatory Guide plates, respectively; (2) The BR3 surveillance and vessel testing program: this vessel was wet-annealed in 1984, relicensed for operation till the plant shutdown in 1987, and was trepanned in early 1995; (3) The accelerated irradiations in the Belgian test reactor BR2 of the Yankee coarse grain plates YA1 and YA9 together with BR3 vessel specimens extracted at nozzle elevation, a location with negligible radiation exposure. It is contended that the PTS screening criterion was never attained by the BR3 and Rowe plates, and

Comparison of BR3 surveillance and vessel plates to the surrogate plates representative of the Yankee Rowe PWR vessel

International Nuclear Information System (INIS)

Fabry, A.; Chaouadi, R.; Puzzolante, J.L.; Van de Velde, J.; Biemiller, E.C.; Rosinski, S.T.; Carter, R.G.

1999-01-01

The sister pressure vessels at the BR3 and Yankee Rowe PWR plants were operated at lower-than-usual temperature (∼260 C) and their plates were austenitized at higher-than-usual temperature (∼970 C) -- a heat treatment leading to a coarser microstructure than is typical for the fine grain plates considered in development of USNRC Regulatory Guide 1.99. The surveillance programs provided by Westinghouse for the two plants were limited to the same A302-B plate representative of the Rowe vessel upper shell plate; this material displayed outlier behavior characterized by a 41J. Charpy-V Notch shift significantly larger than predicted by Regulatory Guide 1.99. Because lower irradiation temperature and nickel alloying are generally considered detrimental to irradiation sensitivity, there was a major concern that the nickel-modified lower Rowe plate and the nickel-modified BR3 plate may become too embrittled to satisfy the toughness requirements embodied in the PTS screening criterion. This paper compares three complementary studies undertaken to clarify these uncertainties: (1) The accelerated irradiation and test program launched in 1990 by Yankee Atomic Electric Company using typical vessel plate materials containing 0.24% copper at two nickel levels: YA1, 0.63% (A533-B) and YA9, 0.19% (A302-B). These were heat-treated to produce the coarse and fine grain microstructures representative of the Yankee/BR3 and the Regulatory Guide plates, respectively; (2) The BR3 surveillance and vessel testing program; this vessel was wet-annealed in 1984, relicensed for operation till the plant shutdown in 1987, and was trepanned in early 1995; (3) The accelerated irradiations in the Belgian test reactor BR2 of the Yankee coarse grain plates YA1 and YA9 together with BR3 vessel specimens extracted at nozzle elevation, a location with negligible radiation exposure. It is contended that the PTS screening criterion was never attained by the BR3 and Rowe plates, and that the BR3 vessel

75 FR 44224 - Grant of Authority for Subzone Status; Yankee Candle Corporation (Candles and Gift Sets); Whately...

Science.gov (United States)

2010-07-28

... Status; Yankee Candle Corporation (Candles and Gift Sets); Whately and South Deerfield, MA Pursuant to... special-purpose subzone at the candle and gift set manufacturing and distribution facilities of Yankee... activity related to the manufacturing and distribution of candles and gift sets at the facilities of Yankee...

Embrittlement and annealing of reactor pressure vessel steels: comparison of BR3 surveillance and vessel plates to the surrogate plates representative of the Yankee Rowe vessel

International Nuclear Information System (INIS)

Fabry, A.; Chaouadi, T.; Puzzolante, J.L.; Van de Velde, J.; Biemiller, E.C.; Rossinski, S.T.; Carter, R.G.

1996-07-01

The sister pressure vessels at the BR3 and Rowe Yankee PWR plants were operated at a lower-than-usual temperature (260 degrees Celsius) and their plates were austenitized at higher-than-usual temperature (970 degrees Celsius). A heat tratemement leading to a coarser microstructure than typical for the fine grain plates that are considered in development of USNRC Regulatory guide 1.99. This material displayed outlier behaviour charackterized by a 41J CVN-shift significantly larger than predicted by Regulatory Guide 1.99. Because lower radiation temperature and nickell alloying are generally considered detrimental to irradiation sensitivity, there was a major concern that the nickel-modified lower Rowe plate and the nickel-modified BR3 plate may become too embrittled to satisfy the toughness requirements enbodied in the PTS screening criterion. This paper compares three complementary studies undertaken to clarify these uncertainties: 1) the accelerated irradiation and test program launched in 1990 by Yankee Atomic Electric Company using typical vessel plate materials containing 0.24% copper at two nickel levels: YA1, 0.63% (A533-B) and YA9, 0.19% (A302-B). These were heat-treated to produce the coarse and fine grain microstructures representative of the Yankee/BR3 and the Regulatory Guide plates, respectively, 2) the BR3 surveillance and vessel testing program: this vessel was wet-annealed in 1984, relicensed for operation till the plant shutdown in 1987, ANCL was trepanned in early 1995, 3) the accelerated irradiations in the Belgian BR2 test reactor of the Yankee coarse grain plates YA1 and YA9 together with BR3 vessel specimens extracted at nozzle elevation, a location with negligible radiation exposure. It is shown that the PTS screening criterion was never attained by the BR3 and Rowe plates, and that the BR3 vessel anneal was neither necessary nor sufficient. Finally, the sensitivity of embrittlement, annealing and post-annealing reembrittlement to irradiation

Embrittlement and annealing of reactor pressure vessel steels: comparison of BR3 surveillance and vessel plates to the surrogate plates representative of the Yankee Rowe vessel

Energy Technology Data Exchange (ETDEWEB)

Fabry, A.; Chaouadi, T.; Puzzolante, J.L.; Van de Velde, J. [Centre de l``Etude de l``Energie Nucleaire, Mol (Belgium); Biemiller, E.C. [Yankee Atomic Electric Company, Bolton (United States); Rossinski, S.T.; Carter, R.G. [Electric Power Research Institute, Charlotte (United States)

1996-07-01

The sister pressure vessels at the BR3 and Rowe Yankee PWR plants were operated at a lower-than-usual temperature (260 degrees Celsius) and their plates were austenitized at higher-than-usual temperature (970 degrees Celsius). A heat tratemement leading to a coarser microstructure than typical for the fine grain plates that are considered in development of USNRC Regulatory guide 1.99. This material displayed outlier behaviour charackterized by a 41J CVN-shift significantly larger than predicted by Regulatory Guide 1.99. Because lower radiation temperature and nickell alloying are generally considered detrimental to irradiation sensitivity, there was a major concern that the nickel-modified lower Rowe plate and the nickel-modified BR3 plate may become too embrittled to satisfy the toughness requirements enbodied in the PTS screening criterion. This paper compares three complementary studies undertaken to clarify these uncertainties: 1) the accelerated irradiation and test program launched in 1990 by Yankee Atomic Electric Company using typical vessel plate materials containing 0.24% copper at two nickel levels: YA1, 0.63% (A533-B) and YA9, 0.19% (A302-B). These were heat-treated to produce the coarse and fine grain microstructures representative of the Yankee/BR3 and the Regulatory Guide plates, respectively, 2) the BR3 surveillance and vessel testing program: this vessel was wet-annealed in 1984, relicensed for operation till the plant shutdown in 1987, ANCL was trepanned in early 1995, 3) the accelerated irradiations in the Belgian BR2 test reactor of the Yankee coarse grain plates YA1 and YA9 together with BR3 vessel specimens extracted at nozzle elevation, a location with negligible radiation exposure. It is shown that the PTS screening criterion was never attained by the BR3 and Rowe plates, and that the BR3 vessel anneal was neither necessary nor sufficient. Finally, the sensitivity of embrittlement, annealing and post-annealing reembrittlement to irradiation

Vermont Yankee advanced off-gas system (AOG)

International Nuclear Information System (INIS)

Littlefield, P.S.; Miller, S.R.; DerHagopian, H.

1975-01-01

Early in 1971 the Vermont Yankee Nuclear Power Corporation decided to modify the existing off-gas delay system to reduce the release of noble gas isotopes from its boiling water reactor. This modification included a subsystem for recombining the radiolytic hydrogen and oxygen from the reactor and a series of adsorber tanks filled with activated carbon to delay the noble gas isotopes from the condenser air ejectors. The off-gas system and its operating history from initial operation in November 1973 to the present time are described. Data are also presented on the measured dynamic adsorption coefficient of the ambient carbon subsystem. Laboratory adsorption tests were conducted on the carbon prior to AOG startup and the results are compared with the effective coefficients obtained under operating conditions. (U.S.)

Nuclear Regulatory Commission issuances

International Nuclear Information System (INIS)

1996-03-01

This document is the March 1996 listing of NRC issuances. Included are: (1) NRC orders granting Cleveland Electric Illuminating Company's petition for review of the ASLB order LBP-95-17, (2) NRC orders relating to the potential disqualification of two commissioners in the matter of the decommissioning of Yankee Nuclear Power Station, (3) ASLB orders pertaining to the Oncology Services Corporation, (4) ASLB orders pertaining to the Radiation Oncology Center, (5) ASLB orders pertaining to the Yankee Nuclear Power Station, and (6) Director's decision pertaining to the Yankee Nuclear Power Station

Report of fact finding survey on atomic energy industries in FY1989

International Nuclear Information System (INIS)

1991-01-01

Japan Atomic Industrial Forum, Inc. summarized the results of 31st fact finding survey on atomic energy industries, which investigated and analyzed the actual status and future perspective of the expenditure, sales and personnel related to atomic energy in electric power, mining and manufacture and trading companies in FY1989. As to the state of activities of atomic energy industries, the expenditure related to atomic energy of electric power companies was 1633.7 billion yen, decrease by 7 % as compared with the previous fiscal year. The main factors are that the construction works of nuclear power stations came to temporary pause, and the operation and maintenance expenses for power stations turned to decrease due to the mechanization of inspection and the decrease of expendables. The sales related to atomic energy of mining and manufacturing companies was 1728.3 billion yen, which is the highest so far, and is increase by 18 % as compared with the previous fiscal year. Due to the diversification of atomic energy market, the manufacture for service field and others grew by 64 %, and the mechanization of production seemed to advance. The backlog of mining and manufacturing companies which is the index of future market trend was as high as 3526 billion yen. (K.I.)

EASE+PEPSE: A productivity tool for the performance engineer

International Nuclear Information System (INIS)

Lucier, R.D.; Gay, R.R.

1986-01-01

Plant performance monitoring has gained increased emphasis given the current political, economic and licensing climate. Utility planners and management can no longer rely on smooth acceptance and financing of new power stations. Therefore, the emphasis has shifted to getting more production out of existing plants. There has also been a dramatic shift towards small but powerful personal computers for engineering applications. This paper discusses how well personal computer based software can fit into utility performance programs. In particular, the use of the EASE+PEPSE software at Yankee Atomic Electric Company is outlined

Decommissioning cost recovery in the United States: lessons learned from Connecticut Yankee NPP

International Nuclear Information System (INIS)

Joosten, J.

1999-01-01

The international audience at ICONE-7 is already familiar with the roles of the owner and the NRC in ensuring the technical and safety performance goals of nuclear plant decommissioning. This paper addresses the role of the economic regulator since the pursuit of technical and safety goals must necessarily carry with them -a price tag- and owners must be concerned with the recovery of those costs. Answers to questions about how to pay and who should pay for decommissioning can very often influence nuclear power plant owner's decision-making. In the United States, most nuclear power plants are privately owned. Nevertheless, their owners are not totally free to determine the plant's economics or profitability. Instead, plant owners must sell their electricity to consumers in a regulated market wherein the price of electricity and terms of sale are controlled by the government. Under this regulatory regime, utilities are generally allowed to recover their investment costs -including decommissioning costs- provided that such costs are prudently, incurred. However, when an owner retires the plant prematurely, the prudence of his actions -up to and including the shutdown- are likely to be challenged. In 1997, for example, the owners of the Connecticut Yankee reactor faced a stiff challenge to the recovery of decommissioning costs when they shut down the plant ten years before license expiration. The Connecticut Yankee case thus provides valuable insights into the role of economic regulation on a nuclear plant's decommissioning strategy. (author)

Examination of turbine discs from nuclear power plants

International Nuclear Information System (INIS)

Czajkowski, C.J.; Weeks, J.R.

1982-01-01

Investigations were performed on a cracked turbine disc from the Cooper Nuclear Power Station, and on two failed turbine discs (governor and generator ends) from the Yankee-Rowe Nuclear Power Station. Cooper is a boiling water reactor (BWR) which went into commercial operation in July 1974, and Yankee-Rowe is a pressurized water reactor (PWR) which went into commercial operation in June 1961. Cracks were identified in the bore of the Cooper disc after 41,913 hours of operation, and the disc removed for repair. At Yankee-Rowe two discs failed after 100,000 hours of operation. Samples of the Cooper disc and both Yankee-Rowe disc (one from the governor and one from the generator end of the LP turbine) were sent to Brookhaven National Laboratory (BNL) for failure analysis

Power companies international year book 1997

International Nuclear Information System (INIS)

Anon.

1996-12-01

The Power Companies International Yearbook covers around 250 major international power generating and distributing companies worldwide, giving a comprehensive overview of this dynamic global industry. Both publicly and privately owned companies are features. It details financial performance, ownership status, affiliated businesses, activities, operations, key personnel, type/capacity of generation, subsidiary activities and plans for diversification within and outside the global power sector. (Author)

Spent nuclear fuel storage pool thermal-hydraulic analysis

International Nuclear Information System (INIS)

Gay, R.R.

1984-01-01

Storage methods and requirements for spent nuclear fuel at U.S. commercial light water reactors are reviewed in Section 1. Methods of increasing current at-reactor storage capabilities are also outlined. In Section 2 the development of analytical methods for the thermal-hydraulic analysis of spent fuel pools is chronicled, leading up to a discussion of the GFLOW code which is described in Section 3. In Section 4 the verification of GFLOW by comparisons of the code's predictions to experimental data taken inside the fuel storage pool at the Maine Yankee nuclear power plant is presented. The predictions of GFLOW using 72, 224, and 1584 node models of the storage pool are compared to each other and to the experimental data. An example of thermal licensing analysis for Maine Yankee using the GFLOW code is given in Section 5. The GFLOW licensing analysis is compared to previous licensing analysis performed by Yankee Atomic using the RELAP-4 computer code

Power of Companies in Supply Chains and Their Effect on Network Development

Directory of Open Access Journals (Sweden)

Tamás Brányi

2015-01-01

Full Text Available A general supply chain functions as a closed cluster and consists of at least three companies: supplier, producer and buyer. In an optimal case the companies within a supply chain are well integrated, partnership rests on trust which results in common strategic decisions. Business practices show that there is a stronger company within the chain that uses its power position to influence network development. The objective of the research is to measure how and what kind of power position is needed to influence the supply chain. The hypothesis states, that power and network development are opposite effects in a supply chain. Statistical examination of data gained from 221 companies state that the company with power position has advantages if the supply chain extends. SPSS analysis proves that the hypothesis is false and opens a new direction of research. Companies within the supply chain have to cope with power structures while cooperating with each other. They tend to look for solutions to ease dependency. Using or misusing power has several factors; mainly they are inherited from the strongest link of the supply chain. This is usually a problem but the results of the statistical analysis show that still a win-win situation is needed for the companies in order to deepen the cooperation. To conclude this research the data shows that the goal is to be more competitive as a chain, not just as a company.

Maine Tidal Power Initiative: Environmental Impact Protocols For Tidal Power

Energy Technology Data Exchange (ETDEWEB)

Peterson, Michael Leroy [Univ. of Maine, Orono, ME; Zydlewski, Gayle Barbin [Univ. of Maine, Orono, ME; Xue, Huijie [Univ. of Maine, Orono, ME; Johnson, Teresa R. [Univ. of Maine, Orono, ME

2014-02-02

The Maine Tidal Power Initiative (MTPI), an interdisciplinary group of engineers, biologists, oceanographers, and social scientists, has been conducting research to evaluate tidal energy resources and better understand the potential effects and impacts of marine hydro-kinetic (MHK) development on the environment and local community. Project efforts include: 1) resource assessment, 2) development of initial device design parameters using scale model tests, 3) baseline environmental studies and monitoring, and 4) human and community responses. This work included in-situ measurement of the environmental and social response to the pre-commercial Turbine Generator Unit (TGU®) developed by Ocean Renewable Power Company (ORPC) as well as considering the path forward for smaller community scale projects.

Analysis of Dust Samples Collected from an In-Service Interim Storage System at the Maine Yankee Nuclear Site.

Energy Technology Data Exchange (ETDEWEB)

Bryan, Charles R.; Enos, David

2016-10-01

In July, 2016, the Electric Power Research Institute and industry partners performed a field test at the Maine Yankee Nuclear Site, located near Wiscasset, Maine. The primary goal of the field test was to evaluate the use of robots in surveying the surface of an in-service interim storage canister within an overpack; however, as part of the demonstration, dust and soluble salt samples were collected from horizontal surfaces within the interim storage system. The storage system is a vertical system made by NAC International, consisting of a steel-lined concrete overpack containing a 304 stainless steel (SS) welded storage canister. The canister did not contain spent fuel but rather greater-than-class-C waste, which did not generate significant heat, limiting airflow through the storage system. The surfaces that were sampled for deposits included the top of the shield plug, the side of the canister, and a shelf at the bottom of the overpack, just below the level of the pillar on which the canister sits. The samples were sent to Sandia National Laboratories for analysis. This report summarizes the results of those analyses. Because the primary goal of the field test was to evaluate the use of robots in surveying the surface of the canister within the overpack, collection of dust samples was carried out in a qualitative fashion, using paper filters and sponges as the sampling media. The sampling focused mostly on determining the composition of soluble salts present in the dust. It was anticipated that a wet substrate would more effectively extract soluble salts from the surface that was sampled, so both the sponges and the filter paper were wetted prior to being applied to the surface of the metal. Sampling was accomplished by simply pressing the damp substrate against the metal surface for two minutes, and then removing it. It is unlikely that the sampling method quantitatively collected dust or salts from the metal surface; however, both substrates did extract a

77 FR 33005 - Connecticut Yankee Atomic Power Company; Haddam Neck Independent Spent Fuel Storage Installation...

Science.gov (United States)

2012-06-04

... margin of safety nor creates a new or different kind of accident from any accident previously evaluated... probability or consequences of an accident previously evaluated; (ii) granting the exemptions would not... in a significant construction impact because there are no construction activities associated with the...

The Canadian Niagara Power Company story

International Nuclear Information System (INIS)

Ball, N.R.

2005-01-01

This book chronicles the history and contributions of the Canadian Niagara Power Company and its employees toward the establishment of electricity generation and distribution in Niagara Falls and Fort Erie, Ontario, dating back to its founding in 1892. Through historical photographs, maps and drawings, the book demonstrates the impact of electricity on the Niagara region. It emphasizes the many skills and jobs required to run the company that generated electricity and maintained a complete system to deliver power, metering, and billing services through the depression, wars, and postwar booms, even during lightning, snow and ice storms. The company began producing power in 1905 with what had been the world's largest-capacity turbines and generators that supplied power to both sides of the Niagara River. Initially, most of the electricity was exported to New York State. The company eventually expanded its Canadian customer service area from Niagara Falls, Ontario, to Fort Erie, Bridgeburg, Amigari, Ridgeway, Stevensville, Crystal Beach and Point Abino. Throughout its history, the Canadian Niagara Power Company provided power at a lower cost than its neighbouring competitors. The William Birch Rankine Generating Station became an important tourist attraction, showcasing the latest electrical appliances of the time in an effort to promote the use of electricity in homes and offices. Today, the station remains a tribute to the fact that natural beauty can coincide with industry. The book also chronicles the difficult business challenges caused by restructuring in the electric power industry in the 1990s, repairing aging equipment and applying the latest in automation and remote sensing technology. Today, the company as FortisOntario is expanding to other communities around Ontario. refs., tabs., figs

The adaptation of the electric power companies to the power market

International Nuclear Information System (INIS)

Otterstad, B.; Ottosen, R.

1993-02-01

This report describes the challenges met by the Norwegian electric power companies in adapting to a more market oriented business and their possibilities and strategies when facing the uncertainties on the market side. The main principles of adaptation to the market are described and various strategies are illustrated by means of simple calculations and figures. The theoretical basis for analyses of adaptation to the market and for pricing period contracts and options are discussed. The report concludes with a discussion of the de-regulation of the North American gas market and draws parallels to the Norwegian power market. 17 figs

Atomic Energy (Miscellaneous Provisions) Act 1981

International Nuclear Information System (INIS)

1981-01-01

This Act extends the power of the United Kingdom Atomic Energy Authority to dispose of shares held by it in any company, and the power of the Secretary of State for Energy to dispose of shares held by him in companies engaged in activities in the field of atomic energy or radioactive substances. (NEA) [fr

The development strategies of the european electric power companies

International Nuclear Information System (INIS)

Heddebaud, D.

2005-01-01

This study takes stock on the european market of the electric power and of its development perspectives. It details the strategy and the place of the main operators and shows their forces and weaknesses. It provides a comparison of the financial performances of 28 companies (growth, margins, profitability, debt and war chest). (A.L.B.)

Company Secretaries: Their duties and powers

OpenAIRE

2009-01-01

Every company must have a company secretary. Their main role is to: carry out the directors’ instructions; help ensure that the company obeys the law and its own constitutional rules; and prepare and maintain the associated company documents.

Program change management during nuclear power plant decommissioning

International Nuclear Information System (INIS)

Bushart, Sean; Kim, Karen; Naughton, Michael

2011-01-01

Decommissioning a nuclear power plant is a complex project. The project involves the coordination of several different departments and the management of changing plant conditions, programs, and regulations. As certain project Milestones are met, the evolution of such plant programs and regulations can help optimize project execution and cost. This paper will provide information about these Milestones and the plant departments and programs that change throughout a decommissioning project. The initial challenge in the decommissioning of a nuclear plant is the development of a definitive plan for such a complex project. EPRI has published several reports related to decommissioning planning. These earlier reports provided general guidance in formulating a Decommissioning Plan. This Change Management paper will draw from the experience gained in the last decade in decommissioning of nuclear plants. The paper discusses decommissioning in terms of a sequence of major Milestones. The plant programs, associated plans and actions, and staffing are discussed based upon experiences from the following power reactor facilities: Maine Yankee Atomic Power Plant, Yankee Nuclear Power Station, and the Haddam Neck Plant. Significant lessons learned from other sites are also discussed as appropriate. Planning is a crucial ingredient of successful decommissioning projects. The development of a definitive Decommissioning Plan can result in considerable project savings. The decommissioning plants in the U.S. have planned and executed their projects using different strategies based on their unique plant circumstances. However, experience has shown that similar project milestones and actions applied through all of these projects. This allows each plant to learn from the experiences of the preceding projects. As the plant transitions from an operating plant through decommissioning, the reduction and termination of defunct programs and regulations can help optimize all facets of

77 FR 6791 - Combined Notice of Filings #2

Science.gov (United States)

2012-02-09

... Generation Company, Entergy Nuclear Power Marketing, LLC, Entergy Nuclear Vermont Yankee, LLC, Entergy...: Ethical Electric Benefit Co. Description: Ethical Electric Benefit Co. Market Based Rate Filing--Clone to...: Michigan Electric Transmission Company. Description: Filing of Certificate of Concurrence to be effective 2...

Trial application of guidelines for nuclear plant response to an earthquake

International Nuclear Information System (INIS)

Schmidt, W.; Oliver, R.; O'Connor, W.

1993-09-01

Guidelines have been developed to assist nuclear plant personnel in the preparation of earthquake response procedures for nuclear power plants. These guidelines are published in EPRI report NP-6695, ''Guidelines for Nuclear Plant Response to an Earthquake,'' dated December 1989. This report includes two sets of nuclear plant procedures which were prepared to implement the guidelines of EPRI report NP-6695. The first set were developed by the Toledo Edison Company Davis-Besse plant. Davis-Besse is a pressurized water reactor (PWR) and contains relatively standard seismic monitoring instrumentation typical of many domestic nuclear plants. The second set of procedures were prepared by Yankee Atomic Electric Company for the Vermont Yankee facility. This plant is a boiling water reactor (BWR) with state-of-the-art seismic monitoring and PC-based data processing equipment, software developed specifically to implement the OBE Exceedance Criterion presented in EPRI report NP-5930, ''A Criterion for Determining Exceedance of the operating Basis Earthquake.'' The two sets of procedures are intended to demonstrate how two different nuclear utilities have interpreted and applied the EPRI guidance given in report NP-6695

Nuclear power company activity based costing management analysis

International Nuclear Information System (INIS)

Xu Dan

2012-01-01

With Nuclear Energy Industry development, Nuclear Power Company has the continual promoting stress of inner management to the sustainable marketing operation development. In view of this, it is very imminence that Nuclear Power Company should promote the cost management levels and built the nuclear safety based lower cost competitive advantage. Activity based costing management (ABCM) transfer the cost management emphases from the 'product' to the 'activity' using the value chain analysis methods, cost driver analysis methods and so on. According to the analysis of the detail activities and the value chains, cancel the unnecessary activity, low down the resource consuming of the necessary activity, and manage the cost from the source, achieve the purpose of reducing cost, boosting efficiency and realizing the management value. It gets the conclusion from the detail analysis with the nuclear power company procedure and activity, and also with the selection to 'pieces analysis' of the important cost related project in the nuclear power company. The conclusion is that the activities of the nuclear power company has the obviously performance. It can use the management of ABC method. And with the management of the procedure and activity, it is helpful to realize the nuclear safety based low cost competitive advantage in the nuclear power company. (author)

76 FR 41530 - Connecticut Yankee Atomic Power Company, Haddam Neck Plant; Notice of Consideration of Approval...

Science.gov (United States)

2011-07-14

... intervention via electronic submission through the NRC E-filing system. Requests for a hearing and petitions... entities participating under 10 CFR 2.315(c), must be filed in accordance with the NRC E-Filing rule (72 FR 49139, August 28, 2007). The E-Filing process requires participants to submit and serve all adjudicatory...

Structural reliability of atomic power plant

International Nuclear Information System (INIS)

Klemin, A.I.; Polyakov, E.F.

1980-01-01

In 1978 the first specialized technical manual ''Technique of Calculating the Structural Reliability of an Atomic Power Plant and Its Systems in the Design Stage'' was developed. The present article contains information about the main characteristics and capabilities of the manual. The manual gives recommendations concerning the calculations of the reliability of such specific systems as the reactor control and safety system, the system of instrumentation and automatic control, and safety systems. 2 refs

76 FR 59482 - The New Brunswick Railway Company-Continuance in Control Exemption-Maine Northern Railway Company...

Science.gov (United States)

2011-09-26

... requirements of 49 U.S.C. 11323-25, for Eastern Maine Railway, a Class III rail common carrier to continue in... Exemption-- Montreal, Maine & Atlantic Railway, Ltd.; Maine Northern Railway Company--Modified Rail...

Efficiency of Finish power transmission network companies

International Nuclear Information System (INIS)

Anon.

2001-01-01

The Finnish Energy Market Authority has investigated the efficiency of power transmissions network companies. The results show that the intensification potential of the branch is 402 million FIM, corresponding to about 15% of the total costs of the branch and 7.3 % of the turnout. Energy Market Authority supervises the reasonableness of the power transmission prices, and it will use the results of the research in supervision. The research was carried out by the Quantitative Methods Research Group of Helsinki School of Economics. The main objective of the research was to create an efficiency estimation method for electric power distribution network business used for Finnish conditions. Data of the year 1998 was used as basic material in the research. Twenty-one of the 102 power distribution network operators was estimated to be totally efficient. Highest possible efficiency rate was 100, and the average of the efficiency rates of all the operators was 76.9, the minimum being 42.6

The main challenges for manufacturing companies in implementing and utilizing configurators

DEFF Research Database (Denmark)

Kristjansdottir, Katrin; Shafiee, Sara; Hvam, Lars

2018-01-01

Companies providing customized products increasingly apply configurators in supporting sales and design activities, thus improving lead-times, quality, cost, benefits perceived by customers, and customer satisfaction. While configurator advantages have been substantially investigated....... Finally, it is investigated whether the importance of the main categories of challenges varies according to a number of potential context variables. The results of the survey, which studies manufacturing companies that use configurators in providing customized products, offer new insights......, the challenges of implementing and utilizing configurators have less often been considered. By reviewing relevant literature, the present study first categorizes the main challenges faced by manufacturing companies when implementing and utilizing configurators. Six main categories of challenges are identified...

77 FR 2972 - Thunder Bay Power Company, Thunder Bay Power, LLC, et al.

Science.gov (United States)

2012-01-20

... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission Thunder Bay Power Company, Thunder Bay Power, LLC, et al.; Notice of Application for Transfer of Licenses, and Soliciting Comments and Motions To Intervene Thunder Bay Power Company Project No. 2404-095 Thunder Bay Power, LLC Midwest Hydro, Inc...

Survey on the trends of atomic power development and utilization in 1973 fiscal year

International Nuclear Information System (INIS)

1975-01-01

Japanese activities in the atomic power development and utilization during 1973 (FY) were investigated and compared with the previous year. The investigation was done for each type of organization; medical, educational, research institute, private company, and others. The results of the investigation can be summarized as follows. The total number of personnel being engaged in the field of atomic industry increased by 1.2%. About 52.8% of them belong to private companies. The number of trainees during 1973 increased by 7.9%. About 92.3% of them were trained in domestic organizations. The expenditure for research and development was 100 billion yen which is 12.1% larger than that in the previous year. About 73.4% was used by public research institutes including JAERI and PNC. Investment in equipments was 235.2 billion yen which was increase of 20%. Most of this money (215.4 billion yen) was invested for the construction of power plants by electric utilities. Total amount of production was 73 billion yen which was increase of 45.9%. (Aoki, K.)

Teollisuuden Voima Oy - Industrial Power Company Ltd. Local information activity

Energy Technology Data Exchange (ETDEWEB)

Engros, Taina [Department of Information, TVO, Olkiluoto FIN-27160 (Finland)

1989-07-01

There are two nuclear power producers in Finland - the state-owned power company Imatran Voima Oy which operates two 440 MW Soviet-made PWR units in southern Finland, east of Helsinki and the Teollisuuden Voima Oy - Industrial Power Company Ltd, or TVO, owned by Finnish industrial companies. TVO operates two 710 MW ABB ATOM BWR units producing about one fifth of the country's electricity consumption. Operating experiences are extremely good from all Finnish nuclear power plants. The Finns' attitude towards nuclear power has changed into a positive direction in recent times. This can probably be noted as an international trend now that the Chernobyl accident is becoming an incident of the past. The Finnish citizens and politicians are facing two questions; first, what is their attitude towards nuclear power as a source of energy, in other words, do they approve of the plants currently in operation. The second question is how they stand on the building of new plants. It is probably another universal phenomenon that the attitudes of people living in the vicinity of nuclear power plants are less critical than the attitudes of those living farther away. This does not, by any means, result in local information activity being easier or less important than nationwide information activity. On the contrary, local decision-makers, local media and inhabitants are those who can, and through whom we can, influence also wider circles. The Nuclear Energy Act, which became effective in Finland last year, defines that the final decision on whether nuclear power plants can be built inside a municipality, is made at local level. As far as TVO is concerned one factor making local information activity easier is the small size of the locality. The difficulty TVO has to face is the people's suspicion of information activity. All information is considered propaganda, regardless of its form, and only negative news are considered information. Also, a large proportion of people are passive

Teollisuuden Voima Oy - Industrial Power Company Ltd. Local information activity

International Nuclear Information System (INIS)

Engros, Taina

1989-01-01

There are two nuclear power producers in Finland - the state-owned power company Imatran Voima Oy which operates two 440 MW Soviet-made PWR units in southern Finland, east of Helsinki and the Teollisuuden Voima Oy - Industrial Power Company Ltd, or TVO, owned by Finnish industrial companies. TVO operates two 710 MW ABB ATOM BWR units producing about one fifth of the country's electricity consumption. Operating experiences are extremely good from all Finnish nuclear power plants. The Finns' attitude towards nuclear power has changed into a positive direction in recent times. This can probably be noted as an international trend now that the Chernobyl accident is becoming an incident of the past. The Finnish citizens and politicians are facing two questions; first, what is their attitude towards nuclear power as a source of energy, in other words, do they approve of the plants currently in operation. The second question is how they stand on the building of new plants. It is probably another universal phenomenon that the attitudes of people living in the vicinity of nuclear power plants are less critical than the attitudes of those living farther away. This does not, by any means, result in local information activity being easier or less important than nationwide information activity. On the contrary, local decision-makers, local media and inhabitants are those who can, and through whom we can, influence also wider circles. The Nuclear Energy Act, which became effective in Finland last year, defines that the final decision on whether nuclear power plants can be built inside a municipality, is made at local level. As far as TVO is concerned one factor making local information activity easier is the small size of the locality. The difficulty TVO has to face is the people's suspicion of information activity. All information is considered propaganda, regardless of its form, and only negative news are considered information. Also, a large proportion of people are passive

Power Company No 2. Activity Report 1992 - 1994

International Nuclear Information System (INIS)

1995-01-01

The Power Company No.2 is in charge of power generation and distribution for the southern area of Vietnam. Status and development plans of the Company is presented in the report. (NHA). 10 figs, 2 tabs, 17 photos, 2 maps

Summary final report: Contract between the Japan atomic power company and the U.S. Department of Energy Improvement of core safety - study on GEM (III)

International Nuclear Information System (INIS)

Burke, T.M.; Lucoff, D.M.

1997-01-01

This report provides a summary of activities associated with the technical exchange between representatives of the Japan Atomic Power Company (JAPC) and the United States Department of Energy (DOE) regarding the development and testing of Gas Expansion Modules (GEM) at the Fast Flux Test Facility (FFTF). Issuance of this report completes the scope of work defined in the original contract between JAPC and DOE titled ''Study on Improvement of Core Safety - Study on GEM (III).'' Negotiations related to potential modification of the contract are in progress. Under the proposed contract modification, DOE would provide an additional report documenting FFTF pump start tests with GEMs and answer additional JAPC questions related to core safety with and without GEMs

Advance of technological innovations of electric power in 2012

International Nuclear Information System (INIS)

Mayumi, Akihiko; Tanaka, Masanori; Takebe, Toshiro

2013-01-01

Twelve companies in Japan reported on the technological innovations in 2012. The Japan Atomic Power Company mainly studied five projects; (1) control of wall thinning of the secondary system in PWR by injection of molybdic acid, (2) application of pipe test method using electromagnetic acoustic resonance to existing equipment, (3) developed high performance Co-60 crud removal resin for Tsuruga Power Station Unit 2, (4) improvement of technology for safety of core in FBR, and (5) improvement of technology for coolant of FBR by dispersing nano-particles in liquid sodium metal. Tokyo Electric Power Company developed mainly three projects; (1) the support for the mental health care activities by industry protection staff at the Fukushima Daiichi and Daini Nuclear Power Plant, (2) laboratory test method using non-radioactive cesium for performance of decontamination reagent, and (3) decontamination effects estimation code (DeConEP). Hokuriku Electric Power Company reported the operations management measures in accordance with the safety enhancement measures to Shika nuclear power station. Other nine reports are published by Hokkaido Electric Power Co., Inc. Tohoku Electric Power Co., Inc. Chubu Electric Power Co., Inc., The Kansai Electric Power Co., Inc., The Chugoku Electric Power Co., Inc., Shikoku Electric Power Co., Inc., Kyushu Electric Power Co., Inc., Okinawa Electric Power Company Inc. and J-Power. (S.Y.)

Shippingport Atomic Power Station. Quarterly operating report, third quarter 1978

Energy Technology Data Exchange (ETDEWEB)

Jones, T. D.

1978-01-01

A loss of ac power to the station occurred on July 28, 1978 caused by an interaction between Beaver Valley Power Station and Shippingport Atomic Power Station when the main transformer of Unit No. 1 of the Beaver Valley Power Station developed an internal failure and tripped the BVPS. Two environmental studies were continued this quarter. The first involves reduction of main unit condenser chlorination and the second, river intake screen fish impingement sampling. There were no radioactive liquid discharges from the Radioactive Waste Processing System to the river this quarter. During the third quarter of 1978, 874 cubic feet of radioactive solid waste was shipped out of state for burial. At the end of the quarter, the Fall shutdown continued with the plant heated up, the main turbine on turning gear and plant testing in progress prior to Station startup.

The AGS Booster main ring power supply system

International Nuclear Information System (INIS)

Soukas, A.; Hughes, K.; Sandberg, J.; Toldo, F.; Zhang, S.Y.

1989-01-01

The AGS Booster is being designed as a very versatile particle accelerator. Its primary function is to be a high quality injector to the currently operating Alternating Gradient Synchrotron (AGS). The Booster/AGS combination will produce proton intensities greater than 5 x 10 13 protons per pulse (ppp), and accelerate heavy ions, with mass up to 200, to a maximum energy of 15 GeV per atomic mass unit (GeV/amu). The power supply for the Booster Main Ring (BMRPS) has to accommodate a wide range of cycles and a wide range of operating parameters. The cycles range from storage for several seconds to rapid cycling at 7.5 Hz. The peak output power is 18 MW. This paper will describe the AGS Booster machine powering requirements, the choice of power supply, the a.c. circuit tie-in and its associated problems and some of the details of the design of the BMRPS. 9 refs., 2 figs

Environmental impact assessment. Ajka Mining and Power Company

International Nuclear Information System (INIS)

Sipkema, Arjan; De Visser, Petra

1994-01-01

An Environmental Impact Assessment (EIA) is a public document which evaluates the impact of a new company or a new project on the environment and it also lays out the possible alternatives. The present EIA was worked out to get an insight into the polluting effects of the Ajka Mining and Power Company in Ajka, Hungary and to understand what hinders the abatement of the pollution. The Ajka coal has a high sulphur content and is slightly radioactive. The Power Plant is situated in the neighborhood of the town Ajka and the wind usually blows the releases in the direction of the town. The radioactive sludge is also stored at the border of the town and its radioactivity exceeds the limit set for the Paks Power Plant (in Hungary). Alternatives for the present technology are explored. Nil-condensation and/or energy conservation seem to be the best alternatives. Theoretically, the Regional Environmental Inspectorate is responsible for all survey of pollution, which they monitor with their own equipment, with data obtained from the company or from other monitoring companies. However, the pollution of the Ajka Mining and Power Company is not completely monitored. (authors)

Summary final report: Contract between the Japan atomic power company and the U.S. Department of Energy Improvement of core safety - study on GEM (III)

Energy Technology Data Exchange (ETDEWEB)

Burke, T.M.; Lucoff, D.M.

1997-03-18

This report provides a summary of activities associated with the technical exchange between representatives of the Japan Atomic Power Company (JAPC) and the United States Department of Energy (DOE) regarding the development and testing of Gas Expansion Modules (GEM) at the Fast Flux Test Facility (FFTF). Issuance of this report completes the scope of work defined in the original contract between JAPC and DOE titled ''Study on Improvement of Core Safety - Study on GEM (III).'' Negotiations related to potential modification of the contract are in progress. Under the proposed contract modification, DOE would provide an additional report documenting FFTF pump start tests with GEMs and answer additional JAPC questions related to core safety with and without GEMs.

Water-hammer prevention, mitigation, and accommodation: a perspective

International Nuclear Information System (INIS)

Kim, J.H.

1987-01-01

The purpose of this paper is to present an industry perspective on water hammer, revisit the issues, and renew interest in this area with aim to prevent, mitigate, and accommodate water hammer. Water hammer keeps recurring in nuclear power plants and damages plant components and impacts on plant operations and availability through forced outages of plants. The implication is that water hammer in nuclear power plants still needs attention and is a problem that has not been fundamentally resolved. The paper displays statistics of the reported water hammer events between 1969 and 1985. The consequences of these water hammer events were: pipe support damage (hangers, anchors, and snubbers), 60%; component damage (piping, pumps, and valves), 17%; reactor trip, 10%; and plant shutdown, 7%. Reactor trips and plant shutdowns account for 17% of the event consequences. At the request of the nuclear utility industry, a workshop on water hammer was sponsored by the Electric Power Research Institute (EPRI), with cosponsorship from Northeast Utility Service Company, Yankee Atomic Electric Company, and Boston Edison Company, which drew some 90 specialists representing 28 utility companies as well as other nuclear industry, academia, and the NRC. The workshop recommendations are summarized

Main Causes Of Mortality Of Companies In Central Region Of Ecuador

Directory of Open Access Journals (Sweden)

Jorge Vladimir Núñez Grijalva

2015-12-01

Full Text Available Most of the studies concerning trading companies, addressing aspects of the initial stage in the life of these, such as its formation stage. However, few studies have examined the final stage of a company and especially the causes of mortality and closing. This article analyzes the main causes of mortality trading companies from three different and complementary disciplines at once: legal, administrative and financial accounting in commercial companies of the Central Region of Ecuador. This research provides a summary of the major causes of mortality, which should be considered by the current and future employers, in order to strengthen their decisions regarding the survival of companies.

Rotary-Atomizer Electric Power Generator

Science.gov (United States)

Nguyen, Trieu; Tran, Tuan; de Boer, Hans; van den Berg, Albert; Eijkel, Jan C. T.

2015-03-01

We report experimental and theoretical results on a ballistic energy-conversion method based on a rotary atomizer working with a droplet acceleration-deceleration cycle. In a rotary atomizer, liquid is fed onto the center of a rotating flat surface, where it spreads out under the action of the centrifugal force and creates "atomized" droplets at its edge. The advantage of using a rotary atomizer is that the centrifugal force exerted on the fluid on a smooth, large surface is not only a robust form of acceleration, as it avoids clogging, but also easily allows high throughput, and produces high electrical power. We successfully demonstrate an output power of 4.9 mW and a high voltage up to 3120 V. At present, the efficiency of the system is still low (0.14%). However, the conversion mechanism of the system is fully interpreted in this paper, permitting a conceptual understanding of system operation and providing a roadmap for system optimization. This observation will open up a road for building power-generation systems in the near future.

Northeast Empire Limited Partnership No. 2 Alternative Energy, Inc. and Maine Public Service Company (Docket No. EA-95): Environmental Assessment

International Nuclear Information System (INIS)

1992-05-01

This environmental assessment (EA) has been prepared in connection with the application (the Application) by Alternative Energy, Inc. (AEI), Northeast Empire Limited Partnership number-sign 2 (the Partnership) and Maine Public Service Company (MPS and, collectively with AEI and the Partnership, the Applicants), filed on January 6, 1992, for authorization to transmit electric energy to a foreign country. The electric energy to be exported would be produced by a 39-megawatt (MW), wood-fired powerplant (the Project) to be developed by AEI and to be built by the Partnership in Ashland, Maine, which is located in MPS' service territory. In the Application, the Applicants requested authorization for MPS to transmit electricity generated by the Project from Maine through New Brunswick, Canada, on route back to the US for domestic use by Central Maine Power Company (MP). The need to cross the US -Canadian border arises due to the geography of the area and to facilitate access to an existing transmission line. None of the power will be used in Canada. This EA addresses the environmental impacts associated with the export of electric energy and the connected actions which are expected to result from the authorization of those exports. The electricity would be exported over cross-border transmission facilities maintained between MPS and New Brunswick Power Corporation (NB Power). No new cross-border facilities, and no modification of any existing cross-border facilities, are required in connection with the proposed action

Japan and atomic co-operation

International Nuclear Information System (INIS)

1965-01-01

Japan, which is host country for the Ninth Regular Session of the Agency General Conference, has an important programme of nuclear power development to meet future needs. In addition, Japan is active in other applications of atomic energy and is building up a domestic nuclear engineering industry. Japan has profited by the Agency as a channel of international cooperation, and was a party to the first bilateral agreement in which the responsibility for administering safeguards against the diversion of materials to military purposes, was transferred to the Agency. Japan has also lent support to Agency programmes by gifts, training courses, research, and the loan of experts. In 1961, the Japan Atomic Energy Commission (AEC) formulated the 'Long-Range Programme for Development and Utilization of Atomic Energy', on the basis of the economic prospects of nuclear power generation, and the conditions necessary to meet the ever-increasing domestic energy demands. According to this programme, in the light of power reactor development trends overseas, it is expected that nuclear power costs will compete with those of oil burning stations by 1970. On this basis, total nuclear power generating capacity of 1000 MW(e) will be attained by 1970, and 7000 - 9 500M(e) by 1980. As a prelude to the above programme the Japan Atomic Power Company (JAPCO) began construction in 1959 of a graphite-moderated gas-cooled nuclear power station (Improved Calder Hall type) of 165 MW(e) gross capacity. This is now progressing smoothly, and reached criticality in May 1965; it is expected to supply commercial power by the end of this year. The second nuclear power station will be built by the same company on the coast of the Japan Sea, with a light water-moderated reactor of 250 - 300 MW(e) capacity. The construction plan i s currently being pushed forward for completion in 1970. Thereafter three private utility companies - Tokyo, Kansai and Chubu Electric Companies - are doing preparatory work for

Taipower's approach in development of in-house LOCA analysis capability

International Nuclear Information System (INIS)

Wang, L.C.

2004-01-01

One lesson learned from the Three Mile Island (TMI) accident was the analysis methods used by Nuclear Steam Supply System (NSSS) vendors and/or nuclear fuel suppliers for small break Loss Of Coolant Accident (LOCA) analysis for compliance with appendix K to 10CFR50 should be revised, so, a technology transfer program and a training program of a new LOCA analysis methodology for Taipower's engineers is briefly described in this paper. Also, an other lesson learned from the TMI accident was the plant-specific calculations using NRC-approved models for small-break LOCA to show compliance with 10CFR50.46 should be submitted for NRC approval, so, a study by Taiwan Power Company (TPC) under the guidance of Yankee Atomic Electric Company (YAEC) has been undertaken to perform this analysis for Maanshan nuclear power plant. The results of the 4 inch line break LOCA analysis is described in this paper. (author)

Chapter 3. The economical power of the company

International Nuclear Information System (INIS)

1998-01-01

In the third chapter of this CD ROM the economic power of the Slovak Electric, Plc. (Slovenske elektrarne, a.s.), is presented. It consist of next paragraphs (1) Property of Slovak Electric, Plc, the company; (2) Position of the Company; (3) Business performance of the Company (Economic results, Installed capacity, Generation of electricity and heat; Electricity trade, Distribution of electricity and heat trade are reviewed); (4) Shareholdings in other companies and international co-operation

Hamaoka Atomic Energy Hall, Chubu Electric Power Co. , Inc

Energy Technology Data Exchange (ETDEWEB)

Kawasaki, Y [Chubu Electric Power Co. Inc., Nagoya (Japan)

1979-10-01

Hamaoka Nuclear Power Station was constructed in the very large site of about 1.6 million m/sup 2/ surrounded by sand dunes and pine forests at the southern tip of Shizuoka Prefecture. Hamaoka Atomic Energy Hall was built on the right side of this power station. This hall had been planned as a part of the works commemorating the 20th anniversary of the founding of the company, and was opened in August, 1972. The building is of steel frame type, and has two floors of 1135 m/sup 2/ total area. The first floor comprises cinema room, power generation corner and open gallery, and the second floor comprises meeting room, native land corner and observation room. Moreover, there is observation platform on the roof. The purpose of the hall is coexistence and coprosperity with the regional residents, and 13 persons make explanations to visitors having reached to 1.9 million as of the end of June, 1979. It is incorporated in the sightseeing route centering around the Omaezaki lighthouse. The cinema hall accommodates 120 men, and the films concerning nuclear power generation and the construction of a nuclear power plant are shown. In the power generation corner, the explanation on nuclear power generation is made with models and panels. The third hall is being built now as energy corner, and it will be completed in autumn, 1979.

Hamaoka Atomic Energy Hall, Chubu Electric Power Co., Inc

International Nuclear Information System (INIS)

Kawasaki, Yukio

1979-01-01

Hamaoka Nuclear Power Station was constructed in the very large site of about 1.6 million m 2 surrounded by sand dunes and pine forests at the southern tip of Shizuoka Prefecture. Hamaoka Atomic Energy Hall was built on the right side of this power station. This hall had been planned as a part of the works commemorating the 20th anniversary of the founding of the company, and was opened in August, 1972. The building is of steel frame type, and has two floors of 1135 m 2 total area. The first floor comprises cinema room, power generation corner and open gallery, and the second floor comprises meeting room, native land corner and observation room. Moreover, there is observation platform on the roof. The purpose of the hall is coexistence and coprosperity with the regional residents, and 13 persons make explanations to visitors having reached to 1.9 million as of the end of June, 1979. It is incorporated in the sightseeing route centering around the Omaezaki lighthouse. The cinema hall accommodates 120 men, and the films concerning nuclear power generation and the construction of a nuclear power plant are shown. In the power generation corner, the explanation on nuclear power generation is made with models and panels. The third hall is being built now as energy corner, and it will be completed in autumn, 1979. (Kako, I.)

The main factor affecting the competitiveness of Contractor Company

Science.gov (United States)

Nurisra; Malahayati, Nurul; Mahmuddin

2018-05-01

Contractor companies must have the competitive advantage to compete in maintaining the survival of the company. Problems arise because quite a lot of advantages can be used and these advantages must be used appropriately to produce competitiveness for the company to continue to compete and to win the competition. This study aims to determine the main factors affecting the competitiveness of medium-class contractors in Banda Aceh. Data collection was obtained through questionnaires distributed to 31 middle-class contractors in Banda Aceh. Data processing and analysis is done by using descriptive analysis. Based on the result of descriptive analysis, it can be concluded that the most important competitiveness factor with a mean score value 4.52 is the relationship, and the factor that has the highest mean score value is the relationship with the government of 4.97, while the result of the ranking analysis is obtained 25 factor that is critical to the competitiveness of medium-class contractors in Banda Aceh.

Offshore atomic power plants

International Nuclear Information System (INIS)

Anon.

1975-01-01

Various merits of offshore atomic power plants are illustrated, and their systems are assessed. The planning of the offshore atomic power plants in USA is reviewed, and the construction costs of the offshore plant in Japan were estimated. Air pollution problem may be solved by the offshore atomic power plants remarkably. Deep water at low temperature may be advantageously used as cooling water for condensers. Marine resources may be bred by building artificial habitats and by providing spring-up equipments. In the case of floating plants, the plant design can be standardized so that the construction costs may be reduced. The offshore plants can be classified into three systems, namely artificial island system, floating system and sea bottom-based system. The island system may be realized with the present level of civil engineering, but requires the development of technology for the resistance of base against earthquake and its calculation means. The floating system may be constructed with conventional power plant engineering and shipbuilding engineering, but the aseismatic stability of breakwater may be a problem to be solved. Deep water floating system and deep water submerging system are conceivable, but its realization may be difficult. The sea bottom-based system with large caissons can be realized by the present civil engineering, but the construction of the caissons, stability against earthquake and resistance to waves may be problems to be solved. The technical prediction and assessment of new plant sites for nuclear power plants have been reported by Science and Technology Agency in 1974. The construction costs of an offshore plant has been estimated by the Ministry of International Trade and Industry to be yen71,026/kW as of 1985. (Iwakiri, K.)

Power control device of an atomic power plant

International Nuclear Information System (INIS)

Ootsuka, Shiro; Ito, Takero.

1980-01-01

Purpose: To improve the power controllability of an atomic power plant by improving the controllability, response and stability of the recirculation flow rate. Constitution: The power control device comprises a power detector of the reactor, which detects and operates the reactor power from the thermal power, neutron flux or the process quantity controlling the same, and a deviation detector which seeks deviation between the power signal of the power detector and the power set value of the reactor or power station. By use of the power control device constituted in this manner, the core flow rate is regulated by the power signal of the deviation detector thereby to control the power. (Aizawa, K.)

Advance in technologies of electric power in 2008

International Nuclear Information System (INIS)

Hamada, Kenichi; Maekawa, Fumiaki; Nakamura, Akio

2008-01-01

Ten electric power companies and two related companies reported their advance in technologies. The technologies of nuclear power plants were stated by ten companies, which consisted of introduction of new main control board to Tomari-3 in Hokkaido Electric Power Co., Inc., reduction methods of exposure dose of Higashidori-1 in Tohoku Electric Power, hot water based two-phase flow testing device for pipe thinning test by Tokyo Electric Power Company, Guideline for prevention of piping damage caused by combustion of mixture gases in BWR (the second edition) published by Thermal and Nuclear Power Engineering Society, setting up distributor in the low-pressure turbine of Shika-2 in Hokuriku Electric Power Company, development of rapid estimation method of release radioactivity and application of high density neutron source to nuclear transmutation of nuclear fuel cycle and introduction of new core monitor system by The Kansai Electric Power Co., Inc., upgrade of investigation of the effects of hot waste water and development of detector for dropout parts of cooling system in reactor by Shikoku Electric Power Co., Inc., change of transformer in Sendai-1 by Kyushu Electric Power Co., Inc., and reactor core design for Oma ABWR by J-Power. The Japan Atomic Power Company reported four articles such as development of technologies for established nuclear power plants, promotion of Tsuruga-3 and Tsuruga-4, application of clearance system in Japan and development of future reactors. (S.Y.)

76 FR 36910 - Astoria Generating Company, L.P., NRG Power Marketing LLC, Arthur Kill Power LLC, Astoria Gas...

Science.gov (United States)

2011-06-23

... Generating Company, L.P., NRG Power Marketing LLC, Arthur Kill Power LLC, Astoria Gas Turbine Power LLC... Generating Company, L.P., NRG Power Marketing LLC, Arthur Kill Power LLC, Astoria Gas Turbine Power [[Page... subscribed docket(s). For assistance with any FERC Online service, please e-mail [email protected

76 FR 34692 - Astoria Generating Company, L.P., NRG Power Marketing LLC, Arthur Kill Power LLC, Astoria Gas...

Science.gov (United States)

2011-06-14

... Generating Company, L.P., NRG Power Marketing LLC, Arthur Kill Power LLC, Astoria Gas Turbine Power LLC... Generating Company, L.P., NRG Power Marketing LLC, Arthur Kill Power LLC, Astoria Gas Turbine Power LLC... notification when a document is added to a subscribed docket(s). For assistance with any FERC Online service...

Main aspects of the planned reform of the Act on the Peaceful Uses of Atomic Energy and Protection against its Hazards (Atomic Energy Act)

International Nuclear Information System (INIS)

Lukes, R.

1991-01-01

There is no specific reason for planning a reform of the atomic energy law just now; the main idea is to keep the atomic energy law abreast with the developments made in the regime of protective laws pertaining to the sector of science and technology. A further aspect not to be neglected, however, is the nuclear power phase-out currently under debate, and a decision against the abandonment of nuclear power should be taken as an occasion to think about a nuclear law reform. The judiciary has been contributing to the development of nuclear law in the last years, and the decisions of the Federal Constitutional Court and of the Federal Administrative Court have not only set the corner flags for the future development of the nuclear law, but have given concrete shape by final settlement of cases of divergence of judicial decisions, to the protective intents of the law and to the subject-related purposes. Thus the judiciary has been taking into account the idea prevailing today, namely that the scope of duties of the Federal Government certainly includes the task of protecting the citizens against the hazards of technology in general, and of novel technologies in particular, and the task of avoiding hazards. So the main line of orientation to be pursued is to draw level with protective regulations established in other fields of law, and to make the Atomic Energy Act a modern instrument of protection by the law. (orig./HSCH) [de

Atomic power plant

International Nuclear Information System (INIS)

Kawakami, Hiroto.

1975-01-01

Object: To permit decay heat to be reliably removed after reactor shut-down at such instance as occurrence of loss of power by means of an emergency water supply pump. Structure: An atomic power plant having a closed cycle constructed by connecting a vapor generator, a vapor valve, a turbine having a generator, a condenser, and a water supply pump in the mentioned order, and provided with an emergency water supply pump operated when there is a loss of power to the water supply pump, a degasifier pressure holding means for holding the pressure of the degasifier by introducing part of the vapor produced from said vapor generator, and a valve for discharge to atmosphere provided on the downstream side of said vapor generator. (Kamimura, M.)

Practical PRA applications at Consumers Power Company

International Nuclear Information System (INIS)

Blanchard, D.P.

1985-01-01

Consumers Power Company has completed two probabilistic risk assessments (PRAs), one each at its Big Rock Point and Midland plants and is in the process of performing a third study at its Palisades Plant. Each PRA is summarized briefly in this paper. Each PRA has been used to evaluate specific plant design features and make operating and design recommendations to plant and Company management as well as to the regulator. This paper is a sumary of those issues on which Consumers Power Company has applied PRAs to date. The technique used in applying PRA to these issues has varied as more was learned about the plants from the PRA and about PRA itself. Some issue resolutions involved deriving technical arguments from small parts of the PRA only, such as the logic models or consequence analysis. Still others required use of the entire PRA including sequence quantification, plant and containment response, consequence analysis and eventually cost-benefit evaluation of proposed resolutions. The benefits derived from these analyses have also varied and include not only a perceived reduction in the risks associated with plant operation but also economic benefit to the Company in that cost-effective alternatives to resolving safety issues have been permitted

Externalities of energy and atomic power

International Nuclear Information System (INIS)

2006-09-01

Energy technology ensures not only energy supply but also has great impacts on society and environments. Economical value and effect evaluation alone doesn't mean appropriate so the evaluation of 'externalities' should be appreciated. In order to assess atomic power in this context, the Atomic Energy Society of Japan set up a research committee on 'externalities of energy and atomic power' from April 2002 to March 2006, whose activities were described in this report. In addition to environmental effects and environmental externalities, four areas were newly studied as follows: (1) biological effects of low dose rate exposure and externalities, (2) externalities as social/economical effects including stable supply and security, (3) energy technologies evaluation and (4) social choice and decision-making. (T. Tanaka)

Evaluation of efficiency in Japan electric power companies

International Nuclear Information System (INIS)

Ghaderi, F.; Muyajima, M.

2001-01-01

efficiencies drastic. with taking into account some operational non operational parameters as inputs and outputs in the Electric Power Companies in Japan, some insight in the extent of operation could be achieved with which it could be argued on the companies efficiency. Then with comparing them with each other the most efficient company with considering the particular parameter could be introduce. The main focus of the paper will be to evaluate the implementation of the electric companies which could be leaded later to promote efficiency. decreasing the price for the end users and energy-saving opportunities in the operating

The power of PV: one US company shows the potential of solar energy

International Nuclear Information System (INIS)

Wood, L.

2005-01-01

A California-based company, PowerLight, has grown from a one-man shop in 1991 to a company with 100 employees, an annual turnover of $100 million and an impressive client list. The company is one of the USA's fastest growing companies and a leader in large-scale, grid-connected solar systems. Its patented PowerGuard offers a lightweight solar rooftop assembly, while its PowerTracker product is a ground-mounted PV system. Details of some of the company's large projects are given and its plans for new markets highlighted

Design of investment management optimization system for power grid companies under new electricity reform

Science.gov (United States)

Yang, Chunhui; Su, Zhixiong; Wang, Xin; Liu, Yang; Qi, Yongwei

2017-03-01

The new normalization of the economic situation and the implementation of a new round of electric power system reform put forward higher requirements to the daily operation of power grid companies. As an important day-to-day operation of power grid companies, investment management is directly related to the promotion of the company's operating efficiency and management level. In this context, the establishment of power grid company investment management optimization system will help to improve the level of investment management and control the company, which is of great significance for power gird companies to adapt to market environment changing as soon as possible and meet the policy environment requirements. Therefore, the purpose of this paper is to construct the investment management optimization system of power grid companies, which includes investment management system, investment process control system, investment structure optimization system, and investment project evaluation system and investment management information platform support system.

78 FR 43197 - Duke Energy Florida, Inc.; Florida Power & Light Company; Tampa Electric Company; Orlando...

Science.gov (United States)

2013-07-19

... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [ER13-1922-000; ER13-1929-000; ER13-1932-000; NJ13-11-000] Duke Energy Florida, Inc.; Florida Power & Light Company; Tampa Electric Company; Orlando Utilities Commission; Notice of Compliance Filings Take notice that on July 10, 2013, Duke Energy...

Georgia Power Company's college degree program

International Nuclear Information System (INIS)

Coggin, C.L.

1988-01-01

The purpose of this paper is to describe Georgia Power Company's on-site college degree program for nuclear power plant personnel. In February 1986, the US Nuclear Regulatory Commission issued a policy statement concerning engineering expertise on shift (Generic Letter 86-04), which appeared in Volume 50, Number 208 of the October 28, 1985 Federal Register. One of the options available to nuclear power plant personnel to meet the requirement was the combined senior reactor operator/shift technical adviser position. One of the methods for meeting the option included a bachelor's degree in engineering technology for an accredited institution, including course work in the physical, mathematical, or engineering sciences

Progress of innovation of electrical power technology in FY2013

International Nuclear Information System (INIS)

Mayumi, Akihiko; Tanaka, Masanori; Yamaguchi, Hiroshi

2014-01-01

The following is the description of technical innovations at 12 companies including Tokyo Electric Power Company, Chubu Electric Power Company, and Japan Atomic Power Company. Tokyo Electric Power Company presented (1) the developments of a wet-type air decontaminating apparatus for inside/outside of power plant, (2) a robot to be used for field investigation at the Fukushima Daiichi nuclear power plant, (3) a visualization technology using laser for detection, and (4) removal of debris at the power plant. Chubu Electric Power Company presented application of a flap gate to the opening on exterior wall of building as a countermeasure against tsunami at the Hamaoka nuclear power plant. Hokuriku Electric Power Company presented a nuclear reactor operation training simulator for full-scope operation training for the Shika nuclear power station. Chugoku Electric Power Company presented their efforts in implementing a predictive monitoring system at the Shimane Nuclear Power Station. Shikoku Electric Power Company presented the installation of a weir with a flap gate to the interior of seawater pit as a countermeasure against tsunami. Japan Atomic Power Company presented an impact assessment method of fallout during transportation of materials caused by nuclear reactor accident, design and development of a square-type shielding container for radioactive wastes, a strength test on concrete materials for the safety design of Tsuruga Power Station Units 3 and 4, decommissioning of nuclear power plant, and research and development of the fast breeder reactor. (S.Y.)

Framatome advanced nuclear power-benefits for our clients from the new company

International Nuclear Information System (INIS)

Weber, P.

2001-01-01

Framatome ANP (Advanced Nuclear Power) merges the complementary strengths of two global nuclear industry leaders Framatome and Siemens - offering clients the best technological solutions for safe, reliable and economical plant performance. With a combined workforce of 13,300 skilled individuals, Framatome ANP is now the nuclear industry's leading supplier. Serving as Original Equipment Manufacturer (OEM) for more than 90 reactors that provide about 30% of the world's total installed nuclear power capacity, our experienced resources remain focused on the local needs of individual clients, wherever in the world they may be. The Company main business used to be turnkey construction of complete Nuclear Power plants, BWR and PWR capabilities, heavy equipment manufacturing, comprehensive I and C capabilities, and also expertise and knowledge of VVER. Framatome ANP will benefit in all of its fields of activity of the experience gained through Framatome and Siemens' collaboration on the next generation reactor, the EPR, as well as on steam generators replacements and or modernization of VVER. Framatome ANP nuclear fuel designs for both PWR and BWR plants provide innovative features and world-leading performance. Framatome ANP is organized according a matrix organization with: - 4 Business Groups (Project and Engineering, Service, Nuclear Fuel, Mechanical Equipment) - 3 Regional Divisions (Framatome Advanced Nuclear Power S.A.S., France; Framatome Advanced Nuclear Power GmbH, Germany; Framatome Advanced Nuclear Power Inc., USA). By 30th January 2001 Siemens Nuclear Power GmbH, founded in 2000 as successor of the Nuclear Division of Siemens Power Generation Group (KWU), was renamed to Framatome Advanced Nuclear Power GmbH forming the German part of the world wide acting company. Over the past 40 years 23 nuclear power plants all around the world - not only pressurized and boiling water reactors, but also two heavy-watermoderated reactors have been designed, constructed and

Attitudes of the general public and electric power company employees toward nuclear power generation

International Nuclear Information System (INIS)

Komiyama, Hisashi

1997-01-01

We conducted an awareness survey targeted at members of the general public residing in urban areas and in areas scheduled for construction of nuclear power plants as well as employees of electric power company in order to determine the awareness and attitude structures of people residing near scheduled construction sites of nuclear power plants with respect to nuclear power generation, and to examine ways of making improvements in terms of promoting nuclear power plant construction sites. Analysis of those results revealed that there are no significant differences in the awareness and attitudes of people residing in urban areas and in areas near scheduled construction sites. On the contrary, a general sense of apprehension regarding the construction of nuclear power plants was observed common to both groups. In addition, significant differences in awareness and attitudes with respect to various factors were determined to exist between members of the general public residing in urban areas and scheduled construction sites and employees of electric power company. (author)

76 FR 17712 - In the Matter of Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, Inc...

Science.gov (United States)

2011-03-30

... referred to as tritiated water. The detection of tritiated water in the monitoring well indicated abnormal... leakage to the environment had been stopped by isolating the piping and containing the water leaking from... to the NRC that water samples taken from groundwater monitoring well GZ-3 on site at Vermont Yankee...

Nitrogen oxide control at power plants of the ENEL company (Italy)

Energy Technology Data Exchange (ETDEWEB)

Kotler, V.R. (Vserossiiskii Teplotekhnicheskii Institut (Russian Federation))

1993-03-01

Analyzes experiences of the ENEL electricity company in Italy in controlling pollutant emission from fossil-fuel power plants. In 1990, the company produced 87% of the country's electricity. Until the year 2000, ENEL plans to increase coal use for power generation by 23.5% and install 9,300 MW of new coal-fired power plant capacity. New European and Italian emission standards require ENEL to reduce NO[sub x] emissions by 30% from 1986 to 1998. NO[sub x] emission values from various fuel-oil and pulverized-coal fired steam generators operated by the company are given. Modifications to existing combustion technologies and equipment installed to lower NO[sub x] content in flue gases at various ENEL power plants are considered. The most promising coal combustion technologies and ongoing research programs are pointed out. 4 refs.

75 FR 16524 - FirstEnergy Nuclear Operating Company, Perry Nuclear Power Plant; Exemption

Science.gov (United States)

2010-04-01

... Company, Perry Nuclear Power Plant; Exemption 1.0 Background FirstEnergy Nuclear Operating Company (FENOC... the Perry Nuclear Power Plant, Unit 1 (PNPP). The license provides, among other things, that the... date for all operating nuclear power plants, but noted that the Commission's regulations provide...

Application of wire electrodes in electric discharge machining of metal samples of reactor blocks of the operative atomic power station

International Nuclear Information System (INIS)

Gozhenko, S.V.

2007-01-01

Features of application of electroerosive methods are considered during the process of direct definition of properties of metal of the equipment of power units of the atomic power station. Results of development of a complex of the equipment for wire electric discharge machining of metal templet and its use are presented at the control of the basic metal of the main circulating pipelines over blocks of the atomic power station of Ukraine over long terms of operation

Engineering for change

International Nuclear Information System (INIS)

Shreiner, S.C.; Modoono, S.A.

1991-01-01

In 1989 Vermont Yankee Nuclear Power Corporation began implementing a large-scale information technology (IT) change program. Prior to 1990 Vermont Yankee maintained two separate computer facilities and organizations: information systems, and reactor engineering. Pressure on corporate and plant computer systems triggered an external consultant's review of company-wide computing, and a visiting Swedish nuclear plant manager stressed the benefits of automated maintenance planning. Vermont Yankee management decided to aim for company-wide office automation and automation of the plant equipment maintenance function. The change was modeled on the following re-engineering principles: organize around outcomes, not tasks; have those who use the output of the process perform the process; subsume information processing work into the real work that produces the information; treat geographically dispersed resources as though they were centralized; link parallel activities instead of integrating their results; put the decision point where the work is performed, and build control into the process; capture information once, at the source. The conceptual structure of the purchased software necessitated some changes in organizational structure and in work flow, although the software had to be modified in cases where work flow or organizational structure could not be modified due to regulatory or audit concerns. The introduction of company-wide electronic mail has changed the structure of communications. The successful implementation of an IT plan requires a strategy for addressing organizational impacts. (L.L.)

Construction permit of nuclear power plants in case of leasing

International Nuclear Information System (INIS)

Anon.

1983-01-01

Guiding lines (unofficial): 1. A leasing company can be founded to finance and to operate a nuclear power plant. 2. The leasing company does not require a license according to section 7 of the Atomic Energy Act, for it neither constructs nor posesses the nuclear power plant. 3. This also applies if the proprietor, and later on operator, of the nuclear power plant holds an interest in this leasing company as a shareholder. Section 7, and 19 subsection 3 of the Atomic Energy Act. Higher Administrative Court of Rhineland Palatinate, Decision of July 20sup(th), 1982. (orig.) [de

Tarapur Atomic Power Station - - an overview of experience

International Nuclear Information System (INIS)

Shah, J.C.

1979-01-01

A broad overview of the experience and performance of the Tarapur Atomic Power Station (TAPS) in its role as the developing world's first foray in commercial atomic power has been attempted. The prime objective was not just generation of power but assimilation of an advanced technology on an economically viable basis in the underdeveloped environment compounded with governmental organisational culture. Scientific and technical advances registered through the TAPS experience in the area of design, operation and maintenance are mentioned. Aspects of station performance, management and even economics are also covered. (auth.)

Role of Dividend of Power to Buy Shares in Companies in Indonesia Stock Exchange

Directory of Open Access Journals (Sweden)

Iskandar Muda

2017-06-01

Full Text Available This study aims to determine the role of the Purchasing Power Shares on manufacturing companies in Indonesia Stock Exchange Period 2014-2015. The variables used in this study as an Independent Variable Dividend and Purchasing Power Shares as Dependent Variables. Power Buy Stocks in this study was measured by the volume of stock sales every year. This research was conducted in Manufacturing company listed on the Indonesia Stock Exchange. The population of this study were 144 companies with purposive sampling as many as 19 of the Company's Manufacturing Company listed on the Indonesia Stock Exchange with the study of the 2014-2015 period in order to obtain 38 units of analysis. Data of this research are secondary data from the financial statements of 19 companies published in the Indonesia Stock Exchange. This research data processing method using the Test Statistics Deskribtif, Classical Assumption Test, Test Linear Regression using SPSS. The results of this study demonstrate that the role of the Dividend has significant influence on the Purchasing Power Shares in Manufacturing Company in Indonesia Stock Exchange (BEI.

Seismic considerations in the design of atomic power plants

International Nuclear Information System (INIS)

Arya, A.S.; Chandrasekaran, A.R.; Thakkar, S.K.

1975-01-01

A seismic design is one of the most important factors for the safety of nuclear power plants constructed in seismic areas. The various considerations in the design of atomic power plant structures and components to achieve high degree (near absolute) of safety during future probable earthquakes is described as follows: (a) determination of design earthquake parameters for SSE and OBE (b) fixing time history accelerograms and acceleration response spectra (c) mathematical modelling of the reactor building considering soil-structure interaction (d) deciding allowable stresses, damping factors and serviceability limits like drift, displacements and crack widths (e) tests for determining stiffness and damping characteristics of components in-situ before commissioning of plant. The main questions that arise under various items requiring further research investigations or development work are pointed out for discussion. (author)

Least cost planning within the service concept of power supply companies

International Nuclear Information System (INIS)

Lueschen, H.; Sonntag, J.; Werner, R.

1995-01-01

In discussing the implementation of energy service concepts, German power supply companies are gradually adopting categories originating from the USA, namely integrated resources planning (IRP), least cost planning (LCP), and demand-side management (DSM). While the activities of German power supply companies are more encompassing than those of their US counterparts in the traditional features of DSM such as load management, information, and consulting, further-going measures such as direct investment and financial incentive programmes for exploiting energy-saving potentials play a less important role and are controversial in the energy-political debate. The article presents the concept of power supply companies for implementing IRP/LCP and makes a concrete assessment of the worth and efficiency of consulting compared with the newer type of financial incentive programmes. (orig.) [de

Atomic power in space: A history

International Nuclear Information System (INIS)

1987-03-01

''Atomic Power in Space,'' a history of the Space Isotope Power Program of the United States, covers the period from the program's inception in the mid-1950s through 1982. Written in non-technical language, the history is addressed to both the general public and those more specialized in nuclear and space technologies. 19 figs., 3 tabs

Company of the month: French EDF opts for nuclear power

International Nuclear Information System (INIS)

Jansen, Siw Linnea

2006-01-01

EDF is Europe's largest power company with 640 TWh produced in 2005 and 36,7 million customers in Europe. On a global scale the company has more than 40 million customers. EDF has significant positions in the four big energy markets in Europe: Germany, France, Great Britain and Italy. EDF has an ambitious investment program in the area of nuclear power, and holds that increased investments in this sector is the best and most beneficial way of keeping up with Europe's increasing energy demand (ml)

Power of Companies in Supply Chains and Their Effect on Network Development

OpenAIRE

Tamás Brányi; László Józsa

2015-01-01

A general supply chain functions as a closed cluster and consists of at least three companies: supplier, producer and buyer. In an optimal case the companies within a supply chain are well integrated, partnership rests on trust which results in common strategic decisions. Business practices show that there is a stronger company within the chain that uses its power position to influence network development. The objective of the research is to measure how and what kind of power position is need...

Pressurized thermal shock probabilistic fracture mechanics sensitivity analysis for Yankee Rowe reactor pressure vessel

International Nuclear Information System (INIS)

Dickson, T.L.; Cheverton, R.D.; Bryson, J.W.; Bass, B.R.; Shum, D.K.M.; Keeney, J.A.

1993-08-01

The Nuclear Regulatory Commission (NRC) requested Oak Ridge National Laboratory (ORNL) to perform a pressurized-thermal-shock (PTS) probabilistic fracture mechanics (PFM) sensitivity analysis for the Yankee Rowe reactor pressure vessel, for the fluences corresponding to the end of operating cycle 22, using a specific small-break-loss- of-coolant transient as the loading condition. Regions of the vessel with distinguishing features were to be treated individually -- upper axial weld, lower axial weld, circumferential weld, upper plate spot welds, upper plate regions between the spot welds, lower plate spot welds, and the lower plate regions between the spot welds. The fracture analysis methods used in the analysis of through-clad surface flaws were those contained in the established OCA-P computer code, which was developed during the Integrated Pressurized Thermal Shock (IPTS) Program. The NRC request specified that the OCA-P code be enhanced for this study to also calculate the conditional probabilities of failure for subclad flaws and embedded flaws. The results of this sensitivity analysis provide the NRC with (1) data that could be used to assess the relative influence of a number of key input parameters in the Yankee Rowe PTS analysis and (2) data that can be used for readily determining the probability of vessel failure once a more accurate indication of vessel embrittlement becomes available. This report is designated as HSST report No. 117

Connecicut River ecological study: a synopsis

International Nuclear Information System (INIS)

Merriman, D.

1976-01-01

This paper recounts some salient features of an extensive study of the thermal effects of the Connecticut Yankee Atomic Power Company's electric generating plant on biota of the lower Connecticut River. The work includes a description of the plume, an examination of the anadromous shad population, a discussion of the affected ichthvofauna and entrainment, and an account of alterations in benthic fauna. This study has several distinctive attributes, among them that it was begun before the Water Quality Act (1965) and that it had a long-term before-and-after character, beginning in 1965 before the plant began operating and continuing during operation (1968-1973). Ecological alterations observed to date appear to be well within the limits of acceptability, and in large measure, wrought by mechanical rather than thermal factors

DETERMINANTS AFFECTING THE SUCCESS OF DISTRIBUTION GRID PROJECTS IN BINH THUAN POWER COMPANY, VIETNAM

OpenAIRE

Pham Van Tai* & Le Duc Thu

2017-01-01

The research identified the critical factors affecting the success of the distribution grid project in Binh Thuan Power Company, clarify the mutual relationship between the critical factors affecting the success of the distribution grid project in Binh Thuan Power Company and recommended and rated the solution to enhance the success of the distribution grid project in Binh Thuan Power Company. The research had found fours critical factors: External factors of project, Controlling and coordina...

Innovation projects of atomic energy institute of national nuclear center RK in the area of peaceful use of atomic energy

International Nuclear Information System (INIS)

Kenzhin, E.; Tazhibayeva, I.; Vasiliyev, Y.; Kolodeshnikov, A.; Vurim, A.

2010-01-01

Institute of Atomic Energy of National Nuclear Center RK (IAE NNC RK) is located in Kurchatov. The city is situated at the border of former Semipalatinsk test site. The institute includes two reactor complexes - IGR and Baikal-1, which are rather distant from Kurchatov. Main activities of IAE NNC RK are: 1. Experimental researches of the nuclear power reactors safety; 2. Experimental researches of behavior of the structural materials for fusion and fission facilities under reactor irradiation; 3. Management of radioactive wastes; 4. Participation in the projects on decommissioning of the fast neutron reactor BN-350; 5. innovation projects: creation of first Kazakhstan's fusion reactor - tokamak KTM for materials; research and testing; development of new technologies (irradiated Be-recycling); development of new reactor technologies - project on creation of high temperature gas-cooled reactor KHTR. IAE NNC RK jointly with Japanese Atomic Energy Agency and with participation of Japanese Atomic Power Company is performing the activities on experimental substantiation of design of active core of prospective fast neutron reactor. Main goal of out-of-pile experiments at the EAGLE facility is obtaining of the information on fuel movement processes under conditions simulating the accident with melting of fast reactor core containing tube-design fuel assembly. Batch mixture is loaded into graphite crucible; then it is melded into electric melting furnace and poured into melt top trap. The outlet pipe is melted by the melt, which is poured into bottom melt trap through the pipe with sodium

THE ANALYSIS OF STRUCTURAL RELIABILITY OF THE MAIN ELECTRIC CONNECTION CIRCUITS OF NUCLEAR POWER PLANTS

Directory of Open Access Journals (Sweden)

M. A. Korotkevich

2017-01-01

Full Text Available The reliability of the main circuit of electrical connections at a nuclear electric power plant that has two units with a capacity of 1,200 MW each has been determined. Reliability, economical, maneuverable properties of the atomic power plant under study are largely determined by its main circuit, so the choice of the circuit for the design and its status in the process of operation occur to be critical objectives. Main electrical connection circuits in nuclear electric power plants are selected on the basis of the schematic networks of the energy system and the land attached to the plant. The circuit of the connection of a nuclear power plant to the grid in the original normal operating modes at all stages of the construction of such a plant should provide the outcome of the full added capacity of a nuclear power plant and the preservation of its stability in the power system without the influence of the emergency system automatics when any outgoing transmission line is disabled. When selecting the main circuit the individual capacity of the installed units and their number are taken into account as well as the order of development of the plant and power supply system; the voltage on which the power of a plant is delivered; a shortcircuit current for switchgear high voltage and the need for their limitation by circuit means; the most power that can be lost when damage to any switch. A model of reliability of the main circuit of electrical connections is designed to detect all types of accidents that are possible at the coincidence of failures of elements with the repair and operational modes that differs in composition and damageability of the equipment, as well as under conditions of the development of accidents due to failure of operation of devices of relay protection and automation.

Atomic power in space: A history

Energy Technology Data Exchange (ETDEWEB)

1987-03-01

''Atomic Power in Space,'' a history of the Space Isotope Power Program of the United States, covers the period from the program's inception in the mid-1950s through 1982. Written in non-technical language, the history is addressed to both the general public and those more specialized in nuclear and space technologies. 19 figs., 3 tabs.

Inquiry relating to modifications of reactor installation in Ikata No. 1 and 2 nuclear power plants of Shikoku Electric Power Company, Inc

International Nuclear Information System (INIS)

1979-01-01

Application was made to the Minister of International Trade and Industry for the license relating to the modifications of reactor installation in the Ikata No. 1 and 2 nuclear power plants of the Shikoku Electric Power Company, Inc., on February 13, 1979, from the president of the company. After the safety evaluation was finished by the Ministry of International Trade and Industry, inquiry was conducted to the Atomic Energy Safety Commission (AESC) on June 15, 1979, from the Minister of International Trade and Industry. The investigation and discussion were commenced by the AESC on June 19, 1979. The modifications of the reactor installation are the increase of new fuel storage capacity from about 1/3 to about 2/3 of in-core fuel for No. 1 plant and the modification of driving mechanism from the roller nut type to the magnetic jack type for the control rod cluster for adjusting power distribution in the No. 2 plant. The contents of the safety examination for each item written above are presented. The prevention of criticality is carefully practiced for the new fuel storage by putting fuel assemblies in stainless steel can type racks and locating the fuel assemblies at the proper distance. Relating to the driving mechanism for the control rod cluster adjusting power distribution, the driving speed is not modified and the reliability is kept by carrying out the continuous operation test and the electric power black out test as the demonstration test. The magnetic jack type mechanism has the locking device to prevent reactor tripping at the time of electric power black out, and the cluster is held at the location where the cluster existed at the time of black out. (Nakai, Y.)

Burning issue of energy problem after Fukushima disaster of TEPCO's atomic power stations

International Nuclear Information System (INIS)

Harada, Shoji

2012-01-01

Strikes of unanticipated enormous earthquake and subsequent tsunami brought unbelievable disaster in eastern Japan on March 11, 2012. In particular, collapse of cooling system of TEPCO's Fukushima atomic power stations resulted in IAEA-defined level7 accident including heavy radiation, hydrogen explosion -induced collapse of the building of power station No.2 and No.4 and melt through of nuclear pressure vessel No1.3.4 At an initial stage of the disaster, nobody knew precisely what happened at the power stations. According to the recent report of the national investigation committee, precise reason of the collapse of the cooling system whether it was induced by the strike of huge earthquake or tsunami is still unclear. Due to poor risk management of the government and TEPCO and closure of the precise disaster information, people became suspicious and nervous about the atomic power station. Fifty four atomic power stations have been constructed for these forty years in Japan. On last May 04, all the atomic power stations were shut down due to periodic inspection. However, restart of them became hot discussion. Although atomic power station was regarded as a powerful tool to reduce carbon dioxide several years ago, this situation after March 11 completely changed. In many countries which possess atomic power station, making a road map to develop recyclable energy is a burning issue. It should be noted that German spent about thirty years to declare atomic energy free society. Finally necessity of succession of technology of utilizing atomic power is emphasized. Politics on depending atomic power differs in each country. Therefore, study from Fukushima disaster should be widely used to prevent from unexpected accident of atomic power station.

Carolina Power and Light Company's computerized Radiological Information Management System

International Nuclear Information System (INIS)

Meyer, B.A.

1987-01-01

Carolina Power and Lignt Company has recently implement a new version of their computerized Radiological Information management System. The new version was programmed in-house and is run on the Company's mainframe computers. In addition to providing radiation worker dose histories and current dose updates, the system provides real-time access control for all three of the Company's nuclear plants such as respirator and survey equipment control and inventory, TLD QC records, and many other functions

Countermeasure to plant life management of the nuclear power plants out of Japan

International Nuclear Information System (INIS)

1999-01-01

Some investigations on countermeasure to plant life management of the nuclear power plants were begun since beginning of 1990s under cooperation with Ministry of International Trade and Industry and all electric power companies under consideration of recent state on abroad and at concept of preventive conservation implementation against the plant life management. As a result, the Tokyo Electric Power Company, the Kansai Electric Power Company and the Japan Atomic Power Company settled each program on countermeasure to plant life management of the Fukushima-1 Power Plant, the Mihama-1 Power Plant and the Tsuruga-1 Power Plant, respectively, which were reported to the Atomic Energy Safety Commission to issue on February, 1999, after deliberation in the Adviser Group of Ministry of International Trade and Industry. Such investigations on countermeasure to the plant life management are also conducted out of Japan in parallel to those in Japan, which contain programs reflecting states of operation and maintenance of nuclear power plants and atmosphere around atomic energy in each country. Here were described on some present states of the countermeasures to plant life management in U.S.A., France, Germany, Sweden, England and so forth. (G.K.)

A study of public acceptance of construction of atomic power plant

International Nuclear Information System (INIS)

Harada, Kazunori; Matsuhashi, Ryuji; Yoshida, Yoshikuni

2011-01-01

In June 2010, Basic Energy Plan was approved in a Cabinet meeting. It says that Japan aims to construct more than 14 atomic power plants by 2030. Today, there are 12 plans of construction of atomic power plant, but it is hard to say that their plans easily come off. That's because public acceptance of atomic power plant is low in Japan, for example local residents wage opposition campaigns. This study conducts a survey in the form of a questionnaire and analyzes it by Analytical Hierarchical Process (AHP). Analytic Hierarchy Process is a structured technique for dealing with complex decisions. A questionnaire using AHP is very easy to answer and analyze. This survey was conducted in 2 areas. First area is Hohoku-cho, Yamaguchi Pref. that had a plan of construction of atomic power plant and the plan was demolished by opposition campaigns. Second area is Kaminoseki-cho, Yamaguchi Pref. that has a plan of construction of atomic power plant now and the plan is working order. Public acceptance can be calculated from survey data of 2 areas, and it helps to understand why first area disapproved a plan of atomic power plant and second area approves it. We consider a model to analyze public acceptance. (author)

FINAL–REPORT NO. 2: INDEPENDENT CONFIRMATORY SURVEY SUMMARY AND RESULTS FOR THE ENRICO FERMI ATOMIC POWER PLANT, UNIT 1, NEWPORT, MICHIGAN (DOCKET NO. 50 16; RFTA 10-004)

Energy Technology Data Exchange (ETDEWEB)

Erika Bailey

2011-07-07

The Enrico Fermi Atomic Power Plant, Unit 1 (Fermi 1) was a fast breeder reactor design that was cooled by sodium and operated at essentially atmospheric pressure. On May 10, 1963, the Atomic Energy Commission (AEC) granted an operating license, DPR-9, to the Power Reactor Development Company (PRDC), a consortium specifically formed to own and operate a nuclear reactor at the Fermi 1 site. The reactor was designed for a maximum capability of 430 megawatts (MW); however, the maximum reactor power with the first core loading (Core A) was 200 MW. The primary system was filled with sodium in December 1960 and criticality was achieved in August 1963.

75 FR 80547 - Carolina Power & Light Company, Shearon Harris Nuclear Power Plant, Unit No. 1; Exemption

Science.gov (United States)

2010-12-22

..., Shearon Harris Nuclear Power Plant, Unit No. 1; Exemption 1.0 Background Carolina Power & Light Company... operation of the Shearon Harris Nuclear Power Plant (HNP), Unit 1. The license provides, among other things... request to generically extend the rule's compliance date for all operating nuclear power plants, but noted...

Present status and future perspective of development of atomic energy

International Nuclear Information System (INIS)

Takuma, Masao

1990-01-01

The last year was the 50th year from the discovery of the nuclear fission of uranium in 1939. The utilization of atomic energy made the unfortunate start as atomic bombs, but after the 'Atoms for Peace' declaration of President Eisenhauer, it has become to contribute to the development of mankind as nuclear power generation and radiation utilization. In Japan, the Atomic Energy Act was instituted in 1955, and the utilization of atomic energy has been eagerly promoted. As to nuclear power generation, as of the end of June, 1989, 423 power plants were in operation in the world, which generated 333 million kW, equivalent to 17 % of the total generated electric power. The nuclear power plants under construction and at planning stage were 199 with 190 million kW capacity, in this way, the development is advanced actively. At present in Japan, 38 nuclear power plants are in operation, generating 29.46 million kW, which has reached 30 % of the total generated electric power. The social environment surrounding atomic energy and the basic way of thinking on atomic energy development are discussed. The demand and supply of electric power in 21st century and atomic energy, and the policy of electric power companies to cope with it are explained. (K.I.)

76 FR 54259 - Virginia Electric and Power Company, Docket Nos. 50-338 and 50-339, North Anna Power Station...

Science.gov (United States)

2011-08-31

... NUCLEAR REGULATORY COMMISSION [NRC-2011-0185] Virginia Electric and Power Company, Docket Nos. 50.... NPF-4 and NPF-7, issued to Virginia Electric Power Company (the licensee), for operation of the North...) and (d) during declarations of severe weather conditions involving tropical storm or hurricane force...

Atomic Power | Taylor | Zede Journal

African Journals Online (AJOL)

Zede Journal. Journal Home · ABOUT THIS JOURNAL · Advanced Search · Current Issue · Archives · Journal Home > Vol 3 (1968) >. Log in or Register to get access to full text downloads. Username, Password, Remember me, or Register. Atomic Power. D Taylor. Abstract. No Abstract. Full Text: EMAIL FREE FULL TEXT ...

An overview of training and technical communication of Chinese representative nuclear power engineering company of EPC mode

International Nuclear Information System (INIS)

Qi Ting; Zhang Xiangyu

2015-01-01

After the Fukushima severe accident, nuclear power development has been in stagnation in all over the world. The Chinese nuclear industry has a slowdown on new NPP construction. As a result, high level technique on safety and effective communication are required. For nuclear power engineering company with EPC mode, high quality on training and technical communication is the principal investment in order to achieve better service on engineering design, environmental impact assessment, environmental engineering design, and equipment supervision and so on. EPC mode requires wide range knowledge on almost every field related to nuclear on nuclear power engineering. In this paper, the author investigated the case of the only nuclear power engineering EPC company (CNPE) in China and present an overview on its training and technical communication both domestic and abroad. Basically, there are 4 main branches of training. The internal training focuses on specifically task (both management and technique), such as HSE training, QC training and quality and safety training. Long term education in the university is organized by cooperated mechanism. Code and platform training is partly carried out by international organization or company, and the experienced engineers coach makes up the other part. The communication is a large part since the EPC mode needs the information and requirements from the NPP entity, authority, and the other institutes, international organizations (like IAEA, NINE, IRSN, OECD, NRC and CEA etc.) and sometimes the public. The overview of the training and communication of the EPC company prevails the outline of its advantage on domestic communication and disadvantage on international technical communication. The paper can be a tool on the soft strength construction of company under EPC mode to broaden its business like consultation and training. Some advice is given by the author on the consultation and global communication in the future. (author)

Interim report on the accident at Fukushima Nuclear Power Stations of Tokyo Electric Power Company

International Nuclear Information System (INIS)

2011-12-01

The Investigation Committee on the Accident at the Fukushima Nuclear Power Stations (the Investigation Committee) of Tokyo Electric Power Company (TEPCO) was established by the Cabinet decision on May 24, 2011. Its objectives are: to conduct investigation for finding out the causes of accidents at the Fukushima Dai-ichi Nuclear Power Station (Fukushima Dai-ichi NPS) and Fukushima Dai-ni Nuclear Power Station (Fukushima Dai-ni NPS) of TEPCO as well as the causes of accident damage; and to make policy recommendations for limiting the expansion of damage and preventing reoccurrence of similar accidents. The Investigation Committee has conducted its investigation and evaluation since its first meeting on June 7, 2011. Its activities included: site visits to the Fukushima Dai-ichi and Dai-ni NPSs, as well as to other facilities; hearing of heads of local governments around the Fukushima Dai-ichi NPS; and hearing of people concerned through interviews mainly arranged by the Secretariat. As of December 16, 2011, the number of interviewees reached 456. The investigation and evaluation by the Investigation Committee are still ongoing and the Interim Report does not cover every item that the Committee aims at investigating and evaluating. Fact-finding of even some of those items discussed in the Interim Report are not yet completed. The Investigation Committee continues to conduct its investigation and evaluation and will issue its Final Report in the summer of 2012. This brief executive summary covers mainly considerations and evaluation of the issues in Chapter VII of the Interim Report, with brief reference to Chapters I to VI. The Investigation Committee recommendations are printed in bold. (author)

Experience of electric power conservation in COELBA (Bahia Electric Company)

International Nuclear Information System (INIS)

Bastos, A.C.F.

1990-01-01

The electric power crisis of Brazilian north-east in 1987 imposes the Bahia Electric Company-COELBA to management a electric power conservation. The institutional, organizational and operational aspects are presented, including the tariff system, the market, the consumption and the relation with public. (author)

VG-400 atomic power and technological installation. Possible core design

International Nuclear Information System (INIS)

Komarov, E.V.; Laptev, F.V.; Lyubivyj, A.G.; Mitenkov, F.M.; Samojlov, O.B.; Sukhachevskij, Yu.B.

1979-01-01

The main characteristics, basic circuit and configuration of equipment of the VG-400 atomic power and technological installation are considered. This installation is intended for supplying with highly-potential heat of thermal electrochemical hydrogen production and for power generation in the steam-turbine cycle. The main installation characteristics: HTGR reactor heat power 1100 MW, electric power 300 MW, helium coolant pressure 50 atm, output temperature 950 deg C, steam pressure in the second contour 175 atm, temperature 535 deg C, core diameter and height 6.4 m and 4 m, respectively, number of spherical fuel elements 8.5x10 5 . The installation can ensure hydrogen production of 10 5 Nxm 3 /h. For the VG-400 reactor block the integral arrangement of the first circuit equipment in the reinforced concrete is chosen. Two versions of the reactor core with prismatic and spherical fuel elements are compared. It is shown that taking into account great potentialities of the spherical zone in a case of further temperature increase and its positive qualities with respect to construction and processing of fuel elements and graphite blocks, the utilization of simplier units and mechanisms in the overloading system and in the process of profiling of energy distribution the choice of the spherical configuration for the VG-400 pilot plant installation seems to be valid

Stainless steel pool constructing technology and management of Fangjiashan Nuclear Power Company

International Nuclear Information System (INIS)

Wei Lianfeng; Wang Qun

2013-01-01

The construction of Fangjiashan nuclear power plant stainless steel cladding has been taken much attention. Based on the careful analysis of stainless steel cladding welding and construction main issues; Many measures have been taken such as welding technology, construction process, the stress control of welding deformation, the cleanliness control of construction process, install precision control, improvements of Non-destructive testing, product protection, etc. And installation methods and techniques have been improved and innovative, the installation quality of stainless steel cladding has been enhanced. At the same time, as owners of the plants, we explored the methods of quality supervision and control, together with the relevant units; and sense of quality management has been unified effectively, made stainless steel cladding quality getting better and better. Fangjiashan nuclear power stainless steel cladding construction quality and management experience has been highly recognized by every company. (authors)

Atomic Power in Space: A History

Science.gov (United States)

1987-03-01

"Atomic Power in Space," a history of the Space Isotope Power Program of the United States, covers the period from the program's inception in the mid-1950s through 1982. Written in non-technical language, the history is addressed to both the general public and those more specialized in nuclear and space technologies. Interplanetary space exploration successes and achievements have been made possible by this technology, for which there is no known substitue.

Establishment of professional nuclear power architectural engineering company

International Nuclear Information System (INIS)

Guo Dongli; Chen Hua

2006-01-01

The rapid development of nuclear power industry in China requires specialized management for the nuclear power engineering projects. It is necessary to establish the nuclear power architectural engineering company to meet the increasing market needs by providing the owner with specialized nuclear engineering project management and overall contracting services. It is imperative that the purpose of establishing the corporation and enterprise core competitiveness should be clearly identified when it is established. Its organizational structure should be geared to the enterprise operation management and development to facilitate the intensified project management and control, and improve its risk-proof ability. (authors)

An FAHP-TOPSIS framework for analysis of the employee productivity in the Serbian electrical power companies

Directory of Open Access Journals (Sweden)

Snezana Pavle Knezevic

2017-09-01

Full Text Available The aim of this paper is to apply an integrated model, which combines methods of classical and fuzzy Multi-criteria decision making (MCDM in selected six large equity companies from the Serbian energy sector. The data considered are retrieved from the official financial statements. Four main criteria were analyzed, identified by the previous researchers and pointing to the employees productivity: Operating income/Number of employees, Equity/Number of employees, Net income/Number of employees and Total assets/Number of employees. The contribution of this paper lies in the application of a hybrid model that integrates two MCDM methods: Fuzzy Analytic Hierarchy Process (FAHP and Technique for Order Performance by Similarity to Ideal Solution (TOPSIS to analyse the employee productivity in selected D-Electrical power supply companies operating in Serbia. The FAHP is an effective method for mathematical representation of uncertain and imprecise evaluations made by humans, while the TOPSIS method is an efficient way to rank the alternatives. Results show that operating income is of highest importance for estimating employee productivity and decision making, while equity is of the weakest. Furthermore, the most productive operations in large enterprises from selected companies of the sector D-Electrical power supply are found in the company PC EPS Beograd, and the lowest are in the ED Center llc Kragujevac.

Harmonic and power balance tools for tapping-mode atomic force microscope

International Nuclear Information System (INIS)

Sebastian, A.; Salapaka, M. V.; Chen, D. J.; Cleveland, J. P.

2001-01-01

The atomic force microscope (AFM) is a powerful tool for investigating surfaces at atomic scales. Harmonic balance and power balance techniques are introduced to analyze the tapping-mode dynamics of the atomic force microscope. The harmonic balance perspective explains observations hitherto unexplained in the AFM literature. A nonconservative model for the cantilever - sample interaction is developed. The energy dissipation in the sample is studied and the resulting power balance equations combined with the harmonic balance equations are used to estimate the model parameters. Experimental results confirm that the harmonic and power balance tools can be used effectively to predict the behavior of the tapping cantilever. [copyright] 2001 American Institute of Physics

Mercury and selenium concentrations in biofilm, macroinvertebrates, and fish collected in the Yankee Fork of the Salmon River, Idaho, USA, and their potential effects on fish health

Science.gov (United States)

Rhea, Darren T.; Farag, Aïda M.; Harper, David D.; McConnell, Elizabeth; Brumbaugh, William G.

2013-01-01

The Yankee Fork is a large tributary of the Salmon River located in central Idaho, USA, with an extensive history of placer and dredge-mining activities. Concentrations of selenium (Se) and mercury (Hg) in various aquatic trophic levels were measured in the Yankee Fork during 2001 and 2002. Various measurements of fish health were also performed. Sites included four on the mainstem of the Yankee Fork and two off-channel sites in partially reclaimed dredge pools used as rearing habitat for cultured salmonid eggs and fry. Hg concentrations in whole mountain whitefish and shorthead sculpin ranged from 0.28 to 0.56 μg/g dry weight (dw), concentrations that are generally less than those reported to have significant impacts on fish. Biofilm and invertebrates ranged from 0.05 to 0.43 μg Hg/g dw. Se concentrations measured in biota samples from the Yankee Fork were greater than many representative samples collected in the Snake and Columbia watersheds and often exceeded literature-based toxic thresholds. Biofilm and invertebrates ranged from 0.58 to 4.66 μg Se/g dw. Whole fish ranged from 3.92 to 7.10 μg Se/g dw, and gonads ranged from 6.91 to 31.84 μg Se/g dw. Whole-body Se concentrations exceeded reported toxicological thresholds at three of four sites and concentrations in liver samples were mostly greater than concentrations shown to have negative impacts on fish health. Histological examinations performed during this study noted liver abnormalities, especially in shorthead sculpin, a bottom-dwelling species.

75 FR 52523 - Bowersock Mills and Power Company; Notice of Availability of Environmental Assessment

Science.gov (United States)

2010-08-26

... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 13526-002-KS] Bowersock Mills and Power Company; Notice of Availability of Environmental Assessment August 19, 2010. In... reviewed the application for an original license for the Bowersock Mills and Power Company's Expanded...

Influence of thermal loading on the ecology of intertidal algae

International Nuclear Information System (INIS)

Vadas, R.L.; Keser, M.; Rusanowski, P.c.

1976-01-01

Thermal effluents from the Maine Yankee Atomic Power Company (operating intermittently from October 1972 to December 1974) increased water temperatures in the discharge area by 7 to 15 0 C. Plant operation and the removal of a causeway increased mixing and salinities in Montsweag Bay. Four small red algae immigrated into the area, but no species were lost from the system. Distribution and abundance patterns of the dominant algae, Ascophyllum nodosum and Fucus vesiculosus, were altered by the thermal discharge. The cover of F. vesiculosus decreased, whereas that of A. nodosum increased in 1973 but declined significantly in 1974. Reductions in biomass and percent cover were accompanied by changes in the growth dynamics of A. nodosum. Growth and survival in the discharge area were enhanced in 1973 but reduced in 1974. Growth was initiated earlier at all sites affected by the warm water. Plants at experimental sites not directly in the discharge channel grew at accelerated rates during the two years, but stressed plants in the discharge produced few or no viable apexes in 1974. The net effect has been a compression and reduction of intertidal algae into a narrower and less dense band

76 FR 36914 - Astoria Generating Company, L.P., NRG Power Marketing LLC, Arthur Kill Power LLC, Astoria Gas...

Science.gov (United States)

2011-06-23

... Generating Company, L.P., NRG Power Marketing LLC, Arthur Kill Power LLC, Astoria Gas Turbine Power LLC... Power Marketing LLC, Arthur Kill Power LLC, Astoria Gas Turbine Power LLC, Dunkirk Power LLC, Huntley... when a document is added to a subscribed docket(s). For assistance with any FERC Online service, please...

75 FR 11149 - Bowersock Mills and Power Company; Notice of Application Tendered for Filing With the Commission...

Science.gov (United States)

2010-03-10

... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 13526-001] Bowersock Mills...: Bowersock Mills Power Company (Bowersock). e. Name of Project: Bowersock Mills and Power Company Expanded....S.C. 791(a)-825(r). h. Applicant Contact: Sarah Hill-Nelson, The Bowersock Mills and Power Company...

'Nuclearelectrica' Company messages for a broadly acceptable nuclear power program

International Nuclear Information System (INIS)

Stiopol, Mihaela; Bilegan, C. Iosif

2001-01-01

Romania started the nuclear power program about 20 years ago, by a high level Government decision. After 1989 the former Ministry of Electrical Power was transformed into a state owned company, RENEL, in which nuclear activities were also included. RENEL was a monopoly system responsible for production, transport and distribution of electricity in Romania. The deregulation process in the power sector was many times asked by the World Bank and International Monetary Fund, to split this monopoly system in separately activities: Production, Transport and Distribution. The first step occurred in July 1998, when the nuclear activities were externalized from RENEL. In nuclear sector two new entities were created: SN 'Nuclearelectrica' SA, a state own company that includes three branches: - Nuclear Power Production - Cernavoda NPP Unit 1; - Nuclear Fuel Plant-Pitesti; - Project Development Branch - Cernavoda Units 2-5. The second entity is the so-called Romanian Authority (Autonomous Reggie) for Nuclear Activities (RAAN), including as branches the heavy water fabrication plant 'ROMAG PROD', the Nuclear Research Institute (ICN) Pitesti and the Nuclear Engineering and Design Institute (CITON) Bucharest. The rest of conventional power sector was renamed, namely, CONEL. The organization process continued and in August 2000, by a Government Ordinance the CONEL was split into the following companies: - one for hydropower production 'HIDROELECTRICA'; - one for thermal power production 'TERMOELECTRICA'; - one for transport 'TRANSELECTRICA'; - one for distribution 'ELECTRICA'. The goal of a third step of restructuring process is the privatization in the power field. The steps of Romanian Power Sector Restructuring are presented. Since 1991 a Public Information program has been established. Depending on the evolution of the construction of the first Romanian nuclear power station, during the years, the messages changed. Everybody working in the nuclear field knows how difficult is

New maintenance strategy of Tokyo Electric Power Company and Fukushima Dai-ichi Nuclear Power Plant for effective ageing management and safe long-term operation

International Nuclear Information System (INIS)

Inagaki, Takeyuki; Yamashita, Norimichi

2009-01-01

Fukushima Dai-ichi Nuclear Power Plant is the oldest among three nuclear power plants owned and operated by Tokyo Electric Power Company, which consists of six boiling water reactor units. The commercial operation of Unit 1 was commenced in 1971 (37 years old) and Unit 6 in 1978 (29 years old). Currently ageing degradations of systems, structures and components are managed through maintenance programs, component replacement/refurbishment programs and long-term maintenance plans. The long-term maintenance plans are established through ageing management component replacement/refurbishment programs reviews performed before the 30th year of operation and they are for safe and reliable operation after 30 years (long-term operation). However the past maintenance actions and past component replacement/refurbishment programs were not always proactive and past operational experience and maintenance practices suggest that effective/proactive ageing management programs be introduced in earlier stage of the plant operation. In this circumstance, Tokyo Electric Power Company and Fukushima Dai-ichi Nuclear Power Plant are setting up a new maintenance strategy that includes 1) improving the normal maintenance programs by using ageing degradation data, 2) effective use of information on internal/external operational experience and maintenance practices related to ageing, and 3) proactive component/equipment refurbishment programs during a refreshment outage for safe and reliable long-term operation. To accomplish the goal of this strategy, strengthening engineering capability of plant staff members is a crucial required for the plant. The objective of this paper is to briefly explain main results ageing management reviews, past and current significant ageing issues and management programs against them, and the new maintenance strategy established by Tokyo Electric Power Company and Fukushima Dai-ichi Nuclear Power Plant. (author)

77 FR 77073 - York Haven Power Company, LLC; Notice of Meeting

Science.gov (United States)

2012-12-31

... Company, LLC; Notice of Meeting On Wednesday, January 9, 2013, Commission staff will meet with York Haven Power Company, LLC (applicant) in Washington, DC. The purpose of the meeting is to discuss the required... begin at 10 a.m. at the Federal Energy Regulatory Commission headquarters building located at 888 First...

The Argentine nuclear policy: evaluation and proposals of the National Atomic Energy Commission

International Nuclear Information System (INIS)

2001-01-01

The document summarizes de medium term plan for the nuclear activities of the country proposed to the Government by the National Atomic Energy Commission (CNEA). An analysis of the present situation is followed by the consideration of the main topics: nuclear power generation, regulatory activities, fuel cycle, radioisotopes and ionizing radiations, radioactive wastes and spent fuels, research, development and human resources, international relations, and the role of the CNEA and its associate companies in the implementation of the plan. A short review is made of the economical aspects of the Argentine nuclear sector

Beaver Valley Power Station and Shippingport Atomic Power Station. 1977 annual environmental report: radiological. Volume 2

International Nuclear Information System (INIS)

1978-01-01

The environmental monitoring conducted during 1977 in the vicinity of the Beaver Valley Power Station and the Shippingport Atomic Power Station is described. The environmental monitoring program consists of onsite sampling of water, gaseous, and air effluents, as well as offsite monitoring of water, air, river sediments, and radiation levels in the vicinity of the site. The report discusses releases of small quantities of radioactivity to the Ohio River from the Beaver Valley Power Station and Shippingport Atomic Power Station during 1977

Development of management systems for nuclear power plant of Hokuriku Electric Power Company

International Nuclear Information System (INIS)

Nakamura, Tatsuaki; Hasunuma, Junichi; Suzuki, Shintaro

2009-01-01

Hokuriku Electric Power Company has been operating the Shika Nuclear Power Station that it constructed in Shika city, Ishikawa prefecture, for over 15 years since bringing Unit 1 of this plant online in July 1993. In addition to electricity generation, maintenance and inspection tasks constitute a big part of operating a large-scale nuclear power plant, and in recent years, problems at power stations in the nuclear power industry have led to several revisions of nationally regulated maintenance and inspection systems. This paper describes the background, objectives, development method, and features of the Maintenance Management System and Maintenance History Management System that make effective use of information technology to promote safer and more efficient maintenance work at large-scale nuclear power plants. (author)

Taming the atom: facing the future with nuclear power

International Nuclear Information System (INIS)

Blair, I.M.

1983-01-01

The subject is discussed under the headings: the mythology of the atom; what is nuclear power (the atom and its nucleus; radioactivity; nuclear fission; breeding nuclear fuel; how a reactor works; the natural reactor at Oklo; the fast reactor; nuclear fusion); the nuclear industry in profile (uranium mining; isotope enrichment; reactor fuel fabrication; types of reactor; decommissioning redundant stations; transport of spent nuclear fuel; reprocessing the spent fuel; management of waste products); nuclear power in the energy scene (energy in man's development; the impending crisis; the need for energy conservation; the role of nuclear power; status of the fast reactor programme; atoms by wire; other possible sources; the question of economics; the next few decades); matters of public concern (biological effects of radiation; probability and consequences of accidents; worries about waste disposal; no free lunches; the technological imperative; the centralisation of power; fears about terrorism; threats to civil liberties; proliferation of nuclear weapons); the great nuclear debate (depth of public concern; lack of public knowledge; differing national techniques; put it somewhere else; a question of credibility). (U.K.)

Service life monitoring of the main components at the Temelin nuclear power plant

International Nuclear Information System (INIS)

Hahn, J.; Vincour, D.

2007-01-01

Knowledge and experience gained from the introduction and periodical implementation of life assessment of the major components of the Temelin nuclear power plant is summarized. The initial Soviet technical design of the plant did not incorporate lifetime monitoring and evaluation, therefore it was completed with demonstrative strength and lifetime calculations from Czech companies. Moreover, a Westinghouse primary circuit diagnosis and monitoring system, including the monitoring of temperature and pressure cycles for low-cycle fatigue evaluation, was installed at the plant. The DIALIFE code for the calculation of mainly the low-cycle fatigue of the key pressure components, was developed and installed subsequently as a superstructure to the monitoring system. (author)

Memorial 1997 - ENDESA (Chilean Electricity Company)

International Nuclear Information System (INIS)

1998-01-01

This report provides a comprehensive survey, in depth assessment of the activities overview of ENDESA, Chilean Electricity Company, highlighting economical information and including historical and technical aspects. Economics is its focal point, but other relevant data are shown, like technical data on hydroelectric and thermoelectric power plants. Main activities developed by ENDESA are described, such in Chile as in the foreign. Data on power generation, transmission and transport are also presented and an economical balance of each colligated company are done and analysed

77 FR 108 - Lockhart Power Company, Inc.; Notice Soliciting Scoping Comments

Science.gov (United States)

2012-01-03

... affect any federal lands. g. Filed Pursuant to: Federal Power Act 16 U.S.C. 791 (a)-825(r). h. Applicant Contacts: Bryan D. Stone, Chief Operating Officer, Lockhart Power Company, Inc., 420 River Street, P.O. Box...

75 FR 57299 - First Energy Nuclear Operating Company; Notice of Receipt and Availability of Application for...

Science.gov (United States)

2010-09-20

... NUCLEAR REGULATORY COMMISSION [NRC-2010-0298; Docket No. 50-346] First Energy Nuclear Operating Company; Notice of Receipt and Availability of Application for Renewal of Davis Besse Nuclear Power...Energy Nuclear Operating Company, filed pursuant to Section 104(b) of the Atomic Energy Act of 1954, as...

Observations of Crassostrea virginica cultured in the heated effluent and discharged radionuclides of a nuclear power reactor

International Nuclear Information System (INIS)

Price, A.H.; Hess, C.T.; Smith, C.W.

1976-06-01

American oysters (Crassostrea virginica) were rafted for 26 months at four sites in the effluent waters near Maine Yankee Nuclear Power Reactor in Montsweag Bay and at a control site in the adjacent Damariscotta River. In an evaluation of the thermal effluent for aquaculture, comparisons are made among the sites of the effects of heated effluent on oyster growth and condition, and the uptake and retention of gamma-ray emitting radionuclides. Growth and uptake of radionuclides were observed to be accelerated at the warmer water sites. Both experimental results and calculations for 58 Co and 54 Mn are presented

Own power: Motives of having electricity without the energy company

International Nuclear Information System (INIS)

Leenheer, Jorna; Nooij, Michiel de; Sheikh, Omer

2011-01-01

New technologies will enable households to generate an increasing amount of their own electricity. Intentions to generate own power are a preliminary step towards actual behavior. Because own generation is still very limited and the behavior of early adopters may not be representative for the complete population, our study focuses on intentions rather than actual behavior. A consumer survey among 2047 Dutch households reveals that environmental concerns are the most important driver of a household's intention to generate its own power. Affinity with technology and energy and the reputation of electricity companies are also significant drivers, but financial factors and power outages are not. About 40% of Dutch households have an intention to generate their own power, with an overrepresentation of young households. This group falls apart in two sub segments; for the 'generating savers' (21%) a high intention to generate own power coincides with a high intention to save energy, whereas generating users (18%) combine a high intention to generate own power with a low intention to save energy. - Highlights: → A consumer survey studies household intentions to generate own power. → Environmental concerns are the most important motive for generating own power. → Other drivers are affinity with technology and reputation of electricity companies. → About 40% of Dutch households feel a need to generate their own electricity.

DESIGN, INNOVATION AND PERSONALIZATION – THE MAIN ASSET COMPANY “SIMPO”, VRANJE

Directory of Open Access Journals (Sweden)

Ljiljana Stošić Mihajlović

2013-07-01

Full Text Available The company "Simpo" – Vranje, is the largest exporter of Serbian furniture and more than four decades has been present on the international market, in almost every continent. And today in about 30 countries worldwide exports 65% of production. Its main advantages are a business emphasis on modern design, the constant innovation of products and materials, and personalization.

Containment pressure analysis model using CONTEMPT-LT

International Nuclear Information System (INIS)

Gupta, R.N.

1975-09-01

An analytical model for evaluating the reactor containment pressure transient following a loss-of-coolant accident (LOCA) is presented. The model uses the CONTEMPT-LT computer program developed by Aerojet Nuclear Company. The sample problem studied is the containment response following the most severe postulated LOCA at the Yankee Rowe Nuclear Power Station. The results show good agreement with the response predicted by Westinghouse Electric Corporation. (auth)

Vermont Yankee Nuclear Power Station. Annual operating report, 1975

International Nuclear Information System (INIS)

1976-01-01

Net electrical power generated was 3,560,206 MWh(e) with the reactor on line 7,689 hrs. Information is presented concerning operations power generation, shutdowns, corrective maintenance, primary coolant chemistry, occupational radiation exposure, reportable occurrences, core spray welds inspection, loss of start-up transformer, and union strike

15 years of information and educational programme of Czech Power Company CEZ

International Nuclear Information System (INIS)

Dufkova, M.

2007-01-01

The education program is the most important long-term communication programme of CEZ. It was established in 1992 shortly after an establishment of Czech Power Company. The support of education and talented students is doubtless a positive activity bringing a benefit to the company, especially in the field of nuclear energy. Students, who have been currently addressed with this program, are future consumers of electricity and as voters and politicians they shall decide on further development of power industry and nuclear installations. We care for them to make qualified decisions. CEZ has so far been the only Czech industrial company, which offers such program to schools. Education is the most important activity in the gaining support for nuclear energy. (author)

Biomass utilization at Northern States Power Company

International Nuclear Information System (INIS)

Ellis, R.P.

1994-01-01

Northern States Power Company (open-quotes NSPclose quotes) generates, transmits and distributes electricity and distributes natural gas to customers in Minnesota, Wisconsin, North Dakota, South Dakota and Michigan. An important and growing component of the fuel needed to generate steam for electrical production is biomass. This paper describes NSP's historical use of biomass, current biomass resources and an overview of how NSP plans to expand its use of biomass in the future

The Gyllingnaes investigation - a survey of altitudes in the Gylling postal area towards atomic power

International Nuclear Information System (INIS)

Boldsen, N.; Buelow, W.

1977-01-01

An investigation of the altitudes of the local population towards the possible construction of an atomic power station at Gyllingnaes in Denmark. It is primarily based on questionnaries, secondarily on interviews. To put the results in better perspective, similar investigations from 1974-1976 are also dealt with. It is concluded that the majority of the population are against atomic power; not only do they oppose the erection of an atomic power station at Gyllingnaes but they oppose the building of atomic power stations in general. An attempt is made to characterize the ''typical'' opponent and the ''typical'' supporter of atomic power. (B.P.)

Effect of laser power and specimen temperature on atom probe analyses of magnesium alloys

International Nuclear Information System (INIS)

Oh-ishi, K.; Mendis, C.L.; Ohkubo, T.; Hono, K.

2011-01-01

The influence of laser power, wave length, and specimen temperature on laser assisted atom probe analyses for Mg alloys was investigated. Higher laser power and lower specimen temperature led to improved mass and spatial resolutions. Background noise and mass resolutions were degraded with lower laser power and higher specimen temperature. By adjusting the conditions for laser assisted atom probe analyses, atom probe results with atomic layer resolutions were obtained from all the Mg alloys so far investigated. Laser assisted atom probe investigations revealed detailed chemical information on Guinier-Preston zones in Mg alloys. -- Research highlights: → We study performance of UV laser assisted atom probe analysis for Mg alloys. → There is an optimized range of laser power and specimen temperature. → Optimized UV laser enables atom probe data of Mg alloys with high special resolution.

Prospects of Foreign Capital Raising for Russian Power Grid Companies

Directory of Open Access Journals (Sweden)

N. N. Shvets

2015-01-01

Full Text Available The power sector reform in Russia saw capital raising as one of the key objectives. Additional investments are necessary, in particular, for renovation of fixed assets which are ca. 70% worn out. The official Strategy for the development of the Russian power grid also provides for privatization of certain companies and foreign investors are considered among others as the target audience. Upon prospective privatization the sector is expected not only to experience a certain increase in capital expenditures, but also to benefit from foreign expertise and efficiency enhancement. At the moment, however, the privatization plans are hard to implement due to a number of obstacles. Prospective investors are mostly concerned about the lack of transparent regulation and clear development strategy of the industry. This is particularly relevant to the tariff system, which has been continuously altered in recent years. This might be explained by the need of the state support by other sectors, which is often provided at the expense of the power industry. Furthermore, the prospects of foreign capital raising are negatively influenced by the conflict in Ukraine and the corresponding negative perception of potential investors. The above factors result in the decrease in value of power grid companies as well as in the lack of visibility regarding the prospects of the sector development. Privatization thus becomes unreasonable both for the state and prospective investors. At the same time, despite the sector specifics, there are precedents of successful sale of power grid assets to private investors by international peers. Particularly, Vatenfall and Forum have recently closed relevant transactions, nothing to say about the power grid sector of Brazil, majorly controlled by private owners. Transparent regulation, clear pricing rules and well-balanced economic policy are, indeed, indispensable prerequisites for successful privatization. Those might back up a

Advertising the atom: federal promotion of nuclear power, 1953-1984

Energy Technology Data Exchange (ETDEWEB)

Smith, M.

1984-01-01

The public relations strategies of the Atomic Energy Commission (AEC) and the nuclear power industry reveal both public and official perceptions of nuclear power and the social uses of technology in general during the first 15 years after passage of the Atomic Energy Act of 1954. The relation between nuclear promotion and regulation also helps explain the environmental crisis of the 1969-1984 years. Project Plowshare coincides roughly with the early promotional years, and provides a case study of the relation of regulatory standards to promotion in AEC policymaking. The author examines the environmentalists challenge to nuclear power that emerged in 1969 alongside government and industry response. He concludes with an assessment of the present state of federal nuclear power policy and of the nuclear power industry.

Advertising the atom: federal promotion of nuclear power, 1953-1984

International Nuclear Information System (INIS)

Smith, M.

1984-01-01

The public relations strategies of the Atomic Energy Commission (AEC) and the nuclear power industry reveal both public and official perceptions of nuclear power and the social uses of technology in general during the first 15 years after passage of the Atomic Energy Act of 1954. The relation between nuclear promotion and regulation also helps explain the environmental crisis of the 1969-1984 years. Project Plowshare coincides roughly with the early promotional years, and provides a case study of the relation of regulatory standards to promotion in AEC policymaking. The author examines the environmentalists challenge to nuclear power that emerged in 1969 alongside government and industry response. He concludes with an assessment of the present state of federal nuclear power policy and of the nuclear power industry

The correlation between management power and risk in the Italian companies

Directory of Open Access Journals (Sweden)

Raffaella Scarabino

2013-03-01

Full Text Available The shareholders can not directly manage the business but they have powers of pulse and control by voting right that is essential for the correct functioning of the company. In 1942 the Italian legislature, although with some exceptions, adopted One share – One vote rule. The legal framework changed significantly after the enactment of corporate law reform in 2003. The objective of this research is to examine the status of the principle of correlation between management power and risk in the context of the regulatory framework of Italian public companies, as it emerged after the enactment of above mentioned corporate law reform in 2003.

[Preliminary study on main impacting factors on brand equity of listed traditional Chinese medicine companies].

Science.gov (United States)

Tan, Wei; Geng, Dong-Mei; Rong, Xue; Li, Zi; Liu, Wei; Yang, Li; Xu, Si-Qun; Jie, Xiao-Qian

2013-05-01

The brand equity is valuable intangible assets of traditional Chinese medicine companies, who are excellent representatives of traditional Chinese medicine enterprises and the most promising ones to good international medicine brands. However, there is still no systematic study on how to correctly evaluate the brand equity of listed traditional Chinese medicine companies at present. To make it clear, the main impacting factors on brand equity of listed traditional Chinese medicine companies, both structured open outline pre-research and closed questionnaire research were adopted for the field survey, and some suggestions for how to protect and enhance the brand equity were also presented on the basis of survey and analysis, in the hope of improving the brand management level of listed traditional Chinese medicine companies, and making a beneficial exploration for the development of brand theory of the traditional Chinese medicine industry.

Final-Report No. 2: Independent Confirmatory Survey Summary And Results For The Enrico Fermi Atomic Power Plant, Unit 1, Newport, Michigan (Docket No. 50 16; RFTA 10-004) DCN 2018-SR-02-0

International Nuclear Information System (INIS)

Bailey, Erika

2011-01-01

The Enrico Fermi Atomic Power Plant, Unit 1 (Fermi 1) was a fast breeder reactor design that was cooled by sodium and operated at essentially atmospheric pressure. On May 10, 1963, the Atomic Energy Commission (AEC) granted an operating license, DPR-9, to the Power Reactor Development Company (PRDC), a consortium specifically formed to own and operate a nuclear reactor at the Fermi 1 site. The reactor was designed for a maximum capability of 430 megawatts (MW); however, the maximum reactor power with the first core loading (Core A) was 200 MW. The primary system was filled with sodium in December 1960 and criticality was achieved in August 1963.

Beaver Valley Power Station and Shippingport Atomic Power Station. 1984 Annual environmental report, radiological. Volume 2

International Nuclear Information System (INIS)

1985-01-01

This report describes the Radiological Environmental Monitoring Program conducted during 1984 in the vicinity of the Beaver Valley Power Station and the Shippingport Atomic Power Station. The Radiological Environmental Program consists of on-site sampling of water and gaseous effluents and off-site monitoring of water, air, river sediments, soils, food pathway samples, and radiation levels in the vicinity of the site. This report discusses the results of this monitoring during 1984. The environmental program outlined in the Beaver Valley Power Station Technical Specifications was followed throughout 1984. The results of this environmental monitoring program show that Shippingport Atomic Power Station and Beaver Valley Power Station operations have not adversely affected the surrounding environment. 23 figs., 18 tabs

Main Characteristics of Nuclear Power Plants in the European Union and Candidate Countries

International Nuclear Information System (INIS)

Lillington, J.N.; Turland, B.D.; Haste, T.J.; Seiler, J.M.; Tapia, J.; Carretero, A.; Perez, T.; Geutges, A.; Sehgal, B.R.; Mattila, L.; Holmstrom, H.; Karwat, H.; Maroti, L.; Husarcek, J.

2001-10-01

The main objective was to advise the EC on future challenges and opportunities in terms of enhanced co-operation in the area of nuclear safety and harmonization of safety requirements and practices in an enlarged European Union Part of this activity was to provide a summary of the plant characteristics of the operating civil nuclear power plants in the EU Member and Candidate Countries. The present report provides these data in three formats: A reference table which lists the main characteristics of nuclear power-producing reactors operating in the European Union (EU) and Candidate Countries, as at 31 December 1999. Also included, for the sake of completeness, are data for reactors in the former Soviet Union, such as Russia and the Ukraine. The format adopted follows that in the annual International Atomic Energy Agency (IAEA) reference data report ''Nuclear Power Reactors of the World'', from which much of the information was taken; A summary table indicating totals by reactor type covering Western and Eastern Europe separately, again from IAEA sources, giving number of plant, total generating capacity and total years in operation. A list of the abbreviations for different reactor types is also provided; A set of detailed data sheets giving main plant characteristics for different reactor types ordered by country. These data sheets cover reactors in EU Member and Candidate Countries only. Details are provided on the origin of the data where these are available, so that further information may be obtained if desired and where permitted by commercial and/or proprietary considerations. (author)

Environmental management in companies: an analysis of the scientific production on environmental management in companies published in the main journals on administration between 1996 and 2005

Directory of Open Access Journals (Sweden)

Fernando César Almada Santos

2008-07-01

Full Text Available The aim of this article is to analyse the scientific production on environmental management in companies published in the six main journals on administration in Brazil (RAE, RAEE, RAUSP, RAP, REAd and RAC, during the period between 1996 and 2005. The following aspects were used in order to examine this academic production: quantitative progress of production; source of authorship; methodological profile; publication content and breadth; and internationalization level of references. The main concerns of this diagnosis are: the academic production on environmental management in companies corresponds to only 2,30% of the total production in administration; a significant part of this production is stimulated by international studies, mainly Hunt and Auster (1990 and Porter and Linde (1995; Brazilian research is restricted to small group of researchers and institutions, as almost 60% of the analyzed articles were published by only five institutions. Thus, this article contributes to the systematization of the academic production on environmental management in companies, as well as it provides insights for this field of research in Brazil.

Yankee Nuclear Power Station. Semiannual operating report, January--June 1975

International Nuclear Information System (INIS)

1975-01-01

The plant operated at power with brief shutdowns and load reductions during this period. Net electrical power generated was 741,551,035 MWh with the generator on line 4,271.30 hrs. Data is presented concerning power generation, shutdowns, corrective maintenance, chemistry and radiochemistry, occupational personnel radiation exposures, release of radioactive materials, and abnormal occurrences. (FS)

Annual report 2007 - CPFL Energy - Light and Power Company from Sao Paulo, SP, Brazil

International Nuclear Information System (INIS)

2008-01-01

This document presents the balance of the economic, social, environmental performance of the Sao Paulo Light and Power Company (CPFL), during the year of 2007 as follows: highlights of 2007; profile of the CPFL Energy group; corporative performance; strategy of the company; performance in 2007 (the best year of the company); social responsibility

77 FR 43071 - MPS Customer Group v. Maine Public Service Company; Notice of Complaint

Science.gov (United States)

2012-07-23

..., MPS Customer Group (Complainant) filed a formal complaint against Maine Public Service Company (MPS or... document is added to a subscribed docket(s). For assistance with any FERC Online service, please email... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Docket No. EL12-84-000] MPS Customer...

YAEC's view of the cause and control of escalating nuclear plant O and M costs

International Nuclear Information System (INIS)

Haseltine, J.D.; Lessard, L.P.

1990-01-01

This paper provides insights on this issue in terms of both the genesis and effective long-term control of O and M costs. Yankee Atomic Electric Company's (YAEC's) insights stem not only from an analysis of certain industry data, but also from its unique position within the nuclear industry in terms of its age, plant size, and organization. First, at 30 yr of age, the YAEC plant has endured the full swing of the regulatory/institutional pendulum and the associated impact on O and M costs. Second, with a size of only 185 MW(electric), YAEC's imperative since start-up has been the strict control of O and M costs while still achieving operational excellence. Finally, YAEC is an organization strictly focused on nuclear power operations and has not been distracted by fossil plant operations or other utility requirements like distribution, retail sales, etc., that may have plagued other plant operators

Atomic power engineering under falsified safety standards

International Nuclear Information System (INIS)

Ackerman, A.J.

1974-01-01

In July 1970 the United States Department of Justice accused the American Society of Mechanical Engineers (ASME) of violating the Sherman Antitrust Act and of acting in restraint of trade by restricting the ASME Certificate of Authorization and the use of the Code Symbol Stamps to boilers and pressure vessels manufactured in the United States and Canada. During the succeeding two years attorneys for the parties in the case formulated a Consent Decree without a public confrontation in the Court. Furthermore, the membership of ASME was kept uninformed until October of 1972, after the Consent and Final Judgment had become effective and new procedures had been developed for allowing foreign manufacturers to apply the ASME Code Symbol Stamps to their products. As a consequence, a breakdown in engineered safety standards has been sanctioned and this is undermining the engineering profession's overriding reponsibility to protect the public health and safety. This breakdown of professional responsibility is especially serious in the new technology of atomic power. American insurance companies, which have traditionally written 100% insurance coverage for property damage and third party liability against explosions of high pressure steam boilers bearing the ASME Code Stamp, have refused to write such insurance coverage on nuclear reactors. In the author's opinion there is evidence that the Consent was formulated under collusive proceedings and he calls on the members and the Council of ASME to appeal for dismissal of the Consent Decree. 24 refs

Atom chief calls for decision on N-power

International Nuclear Information System (INIS)

Hughes, N.

1982-01-01

A decision must be made, on whether South Africa is going to build more nuclear power stations. The Atomic Energy Corporation and the Electricity Supply Commission should come together, to present a nuclear development plan to the Government. If the nuclear power industry is going to expand, everything must be co-ordinated and this should be done in the immediate future

78 FR 28835 - Salton Sea Power Generation Company; Supplemental Notice That Initial Market-Based Rate Filing...

Science.gov (United States)

2013-05-16

... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Docket No. ER13-1271-000] Salton Sea Power Generation Company; Supplemental Notice That Initial Market-Based Rate Filing Includes Request for... Salton Sea Power Generation Company's application for market-based rate authority, with an accompanying...

THE MAIN OPERATIONS OF REORGANIZATION THROUGH MERGERS OF TRADING COMPANIES

Directory of Open Access Journals (Sweden)

Alexandra-Gabriela Rolea

2013-11-01

Full Text Available Notwithstanding the optimistic forecasts issued by experts a couple of years ago, the economic predicaments of the European Union’s member states, including Romania, are far from being settled. The extension of the economic and financial dowturn, the continuing process of globalization and the financial markets’ volatility have imposed an unparalleled flexibility upon the economic agents, in that the amount of mergers and acquisitions has risen at a both national and international level. This background calls for a detailed but nonetheless approachable study of the reorganization of the trading companies though mergers, aimed mainly at the business environment. In order to reach the aforementioned objectives, the theoretical endeavor seeks to explore the relevant legal provisions, including the European Directives. The juridical and accounting operations of mergers, their legal consequences and concrete implications on the activity of the trading companies will also be analysed. Some particular approaches embraced by the legal practice are to be presented, as in Romania mergers are submitted to the control of the court. The study will have a positive impact on the economic agents, who are fostered to conclude this type of restructuring, by altering the line of thought shaped a few years ago, according to which mergers are difficult, isolated and sometimes even unacceptable operations.

75 FR 21286 - Bowersock Mills and Power Company; Notice of Application Accepted for Filing, Soliciting Motions...

Science.gov (United States)

2010-04-23

... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 13526-002] Bowersock Mills... License. b. Project No.: 13526-002. c. Date Filed: February 8, 2010. d. Applicant: Bowersock Mills Power Company (Bowersock). e. Name of Project: Bowersock Mills and Power Company Expanded Kansas River...

Applications of MAAP at Duke Power Company

International Nuclear Information System (INIS)

Barrett, M.

1991-01-01

The Modular Accident Analysis Program (MAAP) is a fast running, easy to use code for modeling accidents at nuclear power plants. These attributes make MAAP ideal for a number of applications. At Duke Power Company, MAAP has been used extensively in the performance of probabilistic risk assessment (PRA). Applications have also been found in the areas of emergency preparedness, training, and severe accident management. Specific applications of MAAP are presented in this paper with special attention to examples in the area of PRA success criteria development and severe accident management strategies selection. The application of MAAP to developing success criteria for ECCS performance during a large LOCA is presented. Additionally, an example of how MAAP has been used in the assessment of an alternative feed and bleed strategy is provided

A survey on the application of robot techniques to an atomic power plant

International Nuclear Information System (INIS)

Hasegawa, Tsutomu; Sato, Tomomasa; Hirai, Shigeoki; Suehiro, Takashi; Okada, Tokuji

1982-01-01

Tasks of workers in atomic power plants have been surveyed from the viewpoint of necessity and possibility of their robotization. The daily tasks are classified into the following: (1) plant operation; (2) periodical examination; (3) patrol and inspection; (4) in-service inspection; (5) maintenance and repaire; (6) examination and production of the fuel; (7) waste disposal; (8) decommission of the plant. The necessity and present status of the robotization in atomic power plants are investigated according to the following classification: (1) inspection robots; (2) patrol inspection/maintenance robots; (3) hot cell robots; (4) plant decommission robots. The following have been made clear through the survey: (1) Various kinds of tasks are necessary for an atomic power plant: (2) Because of most of the tasks taking place in intense radiation environments, it is necessary to introduce robots into atomic power plants: (3) In application of robots in atomic power plant systems, it is necessary to take account of various severe conditions concerning spatial restrictions, radioactive endurance and reliability. Lastly wide applicability of the techniques of knowledge robots, which operate interactively with men, has been confirmed as a result of the survey. (author)

75 FR 22772 - Cargill Power Markets, LLC, Complainant v. Public Service Company of New Mexico, Respondent...

Science.gov (United States)

2010-04-30

... Markets, LLC, Complainant v. Public Service Company of New Mexico, Respondent; Notice of Complaint April... of the Federal Power Act (FPA), 16 U.S.C. 824e (2006), Cargill Power Markets, LLC (Complainant) filed a formal complaint against Public Service Company of New Mexico (Respondent) alleging that...

Activities of the EMAG Mine Automation Company in development of control systems for powered supports

Energy Technology Data Exchange (ETDEWEB)

Sikora, W; Sobczyk, J

1986-10-01

Research programs are evaluated of the EMAG Mine Automation Company on electrohydraulic control systems and remote control for powered supports manufactured in Poland. A control system for the FAZOS-12/28-Oz and FAZOS-15/31-Oz supports is characterized by: reduced length of hydraulic pipes (by 1/3), increased reliability, increased number of commands, less complicated design and lower maintenance and repair cost. A scheme of the system and its main elements (electrohydraulic executive units, control panels and their position, power supply system, and electric cables) is given. After operational tests in the Murcki mine, EMAG will start manufacturing the systems on a commercial scale (about 35 units per year). The research program for development of a remote control system for the 1990s is characterized (computerized control, microprocessors complementary MOS units, etc.).

The new generation of nuclear power stations. A new trend in atomic power?

International Nuclear Information System (INIS)

Hohlefelder, W.

2006-01-01

According to the author, all options for future power supply should be followed, including atomic power provided that it can be made technically safe and treated with a maximum safety culture. On the one hand, power supply is an elementary human need, deciding on public welfare, economic development and technical progress. On the other hand, there is an impending shortage of power owing to depletion of resources and the emergence of new industrialized nations especially in south east Asia. For this reason, all options should be considered, from renewable energy sources to coal and nuclear power. (orig.)

About connection between atomic and hydrogen energy power

International Nuclear Information System (INIS)

Avdeeva, M.Zh.; Vecher, A.A.; Pan'kov, V.V.

2008-01-01

Possible interaction between atomic and hydrogen energy power has been discussed. The analysis of the result held shows that the electrical energy produced by the atomic reactor during the of-load hours can be involved into the process of obtaining hydrogen by electrolysis. In order to optimize the transportation and storage of hydrogen it is proposed to convert it into ammonia. The direct uses of ammonia as a fuel into the internal combustion engine and fuel cells are examined. (authors)

Inquiry relating to modification of reactor installation of Hamaoka No. 2 nuclear power plant of Chubu Electric Power Company, Inc

International Nuclear Information System (INIS)

1979-01-01

Application was made to the Minister of International Trade and Industry for the license relating to the modification of reactor installation of the Hamaoka No. 2 nuclear power plant, Chubu Electric Power Company, Inc., on February 8, 1979, from the president of the company. After the safety evaluation in the Ministry of International Trade and Industry was finished, inquiry was conducted to the head of the Atomic Energy Safety Commission (AESC) on May 25, 1979, from the Minister of International Trade and Industry. The investigation and discussion were commenced by the AESC on May 28, 1979. The modification of the reactor installation is the increase of spent fuel storage capacity from about 220% of in-core fuel at present to about 325%. The fundamental philosophy of the safety evaluation includes the following items; 1) the storage capacity of spent fuel is adequate, 2) the design is such that the criticality is prevented under any assumed condition, 3) the sufficient cooling capacity is kept for decay heat removal, 4) and others required for the safety. The contents of the safety examination for each philosophical item written above are presented. The increased spent fuel storage capacity is equivalent to the quantity produced in about eight years. The prevention of criticality in the spent fuel storage is carefully practiced by putting fuel assemblies in the stainless steel racks with large neutron absorption cross section and locating spent fuel assemblies at the proper distances. The effective multiplication factor is less than 0.95 at the most severe arrangement in the fuel pool. The water temperature in the pool is less than 65 deg C at about 325% core storage by operating the spent fuel pool water cooling system. The spent fuel storage racks are designed as the A class aseismatic structure. (Nakai, Y.)

Appreciation analysis for power supply companies; Wertsteigerungsanalyse fuer Energieversorgungsunternehmen

Energy Technology Data Exchange (ETDEWEB)

Muche, T. [Hochschule Zittau/Goerlitz (Germany)

2007-08-15

In view of the probable future consolidation in the energy economy with municipal undertakings increasingly becoming subject to takeovers and participations issues of shareholder value are a matter of growing interest for power supply companies. Amongst other advantages, having a high shareholder value guards against unwanted takeovers. However, it is not enough for companies merely to know their shareholder value; they must rather have their entire operative and strategic planning and control instruments geared to it. This forms the background to a pilot project at Goerlitz/Zittau University which was dedicated to an analysis of the shareholder value of municipal undertakings on the basis of year-end financial and capital market data.

Use of waste heat from nuclear power plants

International Nuclear Information System (INIS)

Olszewski, M.

1978-01-01

The paper details the Department of Energy (DOE) program concerning utilization of power plant reject heat conducted by the Oak Ridge National Laboratory (ORNL). A brief description of the historical development of the program is given and results of recent studies are outlined to indicate the scope of present efforts. A description of a DOE-sponsored project assessing uses for reject heat from the Vermont Yankee Nuclear Station is also given

Where U.S. utilities seek fuel to power reactors after 1985

International Nuclear Information System (INIS)

Anon.

1977-01-01

How utilities try to assure uranium supplies emerged Feb. 25 at a press conference in Canberra with four representatives of utilities that supply 20% of the operating nuclear capacity in the United States. Earlier, the speakers indicated that American import requirements would far exceed Australian estimates of the potential export market for Australian uranium. Australia, with the world's largest uncommitted uranium reserves, is wary of exporting because the opposition Labor Party adamantly opposes uranium development. If Labor returns to power, it could decide not to honor contracts by the present government. Participants included: Bernard Cherry, fuel manager at General Public Utilities; Colin Campbell of the Yankee Atomic Service Co., which provides engineering and fuel-supply service for seven New England nuclear plants; Jack Gilleland, assistant manager of power at the Tennessee Valley Authority; and Ralph Bostian, manager for systems results and fuel management at the Duke Power Co. When asked about available uranium supplies from Africa, the participants were dubious about those supplies; this led to a discussion on why the utilities are seeking their own sources. The answers are obvious. ERDA has indicated that about one-half of the operating reactors have fuel coverage beyond six reloads and about one-half of the reactors under construction have fuel coverage beyond two reloads

Application of wind power systems to the Service Area of the Minnesota Power and Light Company. Final report, July 1975--August 1976

Energy Technology Data Exchange (ETDEWEB)

Lindquist, O.H.; Malver, F.S.

1976-01-01

Honeywell, in a joint effort with Minnesota Power and Light Company (MP and L), Boeing Vertol Company, and Dr. C.G. Justus, Georgia Institute of Technology, has conducted a regional application study of wind energy systems. Minnesota Power and Light Company, an investor-owned company with 853-MW owned capacity, has served as the case study subject utility. An initial system definition was developed based on available wind information and near-term wind turbine generator (WTG) technology. The system was tailored to fit MP and L's forecasted generation needs and the company's existing transmission and distribution system. Honeywell developed a WECS simulation to convert wind data to wind energy available for input to the utility's grid. The simulation was used to evaluate the performance of preliminary design wind turbine generators developed for ERDA/NASA by the General Electric Company and Kaman Aerospace Corporation, and to evaluate the performance of a wind turbine optimized for the Northern Minnesota wind regime and developed by the Boeing Vertol Company under subcontract to Honeywell.

Yankee Nuclear Power Station. Semiannual operating report, July--December 1975

International Nuclear Information System (INIS)

1976-01-01

Net electrical power generated was 1,193,419,764 MWh(e) with the reactor on line 7,214.13 hrs. Information is presented concerning operation, power generation, shutdowns, corrective maintenance, primary coolant chemistry, occupational radiation exposure, release of radioactive materials, and reportable occurrences

The law governing power generation and the atomic energy law in Japan, with special regard to the current situation in the energy sector

International Nuclear Information System (INIS)

Fujiwara, J.

1984-01-01

This contribution characterises Japanese legislation on power generation and supply, goes into detail with regard to the current Atomic Energy Law within the framework of the overall legal concept governing power supply, and presents an outlook on future developments. A table summarizes the main problems in this field. (orig./HSCH) [de

Yankee Nuclear Power Station. Annual operating report: January--December 1976

International Nuclear Information System (INIS)

1977-01-01

Net electrical power generated was 1,251,255 MWH with the reactor on line 7887 hrs. Information is presented concerning operations, power generation, shutdowns, corrective maintenance, chemistry and radiochemistry, occupational radiation exposure, release of radioactive materials, reportable occurrences, containment penetration tests, and fuel performance

Influence of laser power on atom probe tomographic analysis of boron distribution in silicon

Energy Technology Data Exchange (ETDEWEB)

Tu, Y., E-mail: ytu@imr.tohoku.ac.jp [The Oarai Center, Institute for Materials Research, Tohoku University, Oarai, Ibaraki 311-1313 (Japan); Takamizawa, H.; Han, B.; Shimizu, Y.; Inoue, K.; Toyama, T. [The Oarai Center, Institute for Materials Research, Tohoku University, Oarai, Ibaraki 311-1313 (Japan); Yano, F. [The Oarai Center, Institute for Materials Research, Tohoku University, Oarai, Ibaraki 311-1313 (Japan); Tokyo City University, Setagaya, Tokyo 158-8557 (Japan); Nishida, A. [Renesas Electronics Corporation, Hitachinaka, Ibaraki 312-8504 (Japan); Nagai, Y. [The Oarai Center, Institute for Materials Research, Tohoku University, Oarai, Ibaraki 311-1313 (Japan)

2017-02-15

The relationship between the laser power and the three-dimensional distribution of boron (B) in silicon (Si) measured by laser-assisted atom probe tomography (APT) is investigated. The ultraviolet laser employed in this study has a fixed wavelength of 355 nm. The measured distributions are almost uniform and homogeneous when using low laser power, while clear B accumulation at the low-index pole of single-crystalline Si and segregation along the grain boundaries in polycrystalline Si are observed when using high laser power (100 pJ). These effects are thought to be caused by the surface migration of atoms, which is promoted by high laser power. Therefore, for ensuring a high-fidelity APT measurement of the B distribution in Si, high laser power is not recommended. - Highlights: • Influence of laser power on atom probe tomographic analysis of B distribution in Si is investigated. • When using high laser power, inhomogeneous distributions of B in single-crystalline and polycrystalline Si are observed. • Laser promoted migration of B atoms over the specimen is proposed to explain these effects.

Electron scattering by trapped fermionic atoms

International Nuclear Information System (INIS)

Wang Haijun; Jhe, Wonho

2002-01-01

Considering the Fermi gases of alkali-metal atoms that are trapped in a harmonic potential, we study theoretically the elastic and inelastic scattering of the electrons by the trapped Fermi atoms and present the corresponding differential cross sections. We also obtain the stopping power for the cases that the electronic state as well as the center-of-mass state are excited both separately and simultaneously. It is shown that the elastic scattering process is no longer coherent in contrast to the electron scattering by the atomic Bose-Einstein condensate (BEC). For the inelastic scattering process, on the other hand, the differential cross section is found to be proportional to the 2/3 power of the number of the trapped atoms. In particular, the trapped fermionic atoms display the effect of ''Fermi surface,'' that is, only the energy levels near the Fermi energy have dominant contributions to the scattering process. Moreover, it is found that the stopping power scales as the 7/6 power of the atomic number. These results are fundamentally different from those of the electron scattering by the atomic BEC, mainly due to the different statistics obeyed by the trapped atomic systems

Progress of technological innovation on electric power in FY2014

International Nuclear Information System (INIS)

Nishikawa, Yoshikazu; Fujii, Yutaka; Sasagawa, Toshiro

2015-01-01

This paper overviews the technological development in FY2014 at Tokyo Electric Power Company, Chubu Electric Power Company, Hokuriku Electric Power Company, Shikoku Electric Power Company, and Electric Power Development Company. In this overview, further breakdown was made for the following departments of each company: nuclear power generation, thermal power generation, hydraulic power generation, power transmission, power distribution, transformation, research and development and technological development, and information and communication. In addition, this paper outlines the achievement of technological development at Japan Atomic Power Company, such as the technological development related to the existing power station, development of new technology, and the development of future reactor. Fukushima Daiichi Nuclear Power Station has developed an investigative system using a high altitude survey robot and a movable monitoring system. Hamaoka Nuclear Power Station examined the feasibility of state diagnostic technique based on multi-point analysis, and studied stress corrosion cracking at the newly established Nuclear Safety Research Laboratory. Shika Nuclear Power Station (Unit 1) applied a pipe stress improvement process by means of high frequency induction heating as a stress corrosion cracking countermeasure. Ikata Nuclear Power Station newly adopted high degree cross-linking cation resin, and high cracking strength anion resin as the primary resins. Oma Nuclear Power Station worked on the all reactor core utilization technology of MOX fuel. (A.O.)

Purification of ammonia-containing trap waters from atomic power plant by ozone treatment

International Nuclear Information System (INIS)

Grachok, M.A.; Prokudina, S.A.; Shulyat'ev, M.I.

1990-01-01

The aim of research was to study the process of ozonation of ammonia-containing trap waters from the Kursk Atomic Power Plant both on the model solutions and on real ones. Different factors (pH of the medium, temperature, concentration of the initial substances) have been studied for their effect on ozonation of aqueous ammonia solutions, model solutions of trap waters from the Kursk Atomic Power Plant as well as ammonia-containing trap waters and liquid radioactive wastes delivered to special water treatment at the Kursk Atomic Power Plant. It is shown that in all the cases the highest rate of ammonia oxidation by ozone is observed in the alkaline medium (pH 1.4-11.0) and at 55 deg C. The obtained results have shown that a method of ozonation followed by evaporation of water to be purified can be used to treat ammonia-containing waters from atomic power plant

Main unit electrical protection at Sizewell 'B' power station

International Nuclear Information System (INIS)

Fischer, A.; Keates, T.

1992-01-01

For any power station, reliable electrical protection of the main generating units (generators plus generator transformers) has important commercial implications. Spurious trips cause loss of generation and consequent loss of revenue, while failure to rapidly isolate a fault leads to unnecessary damage and again, loss of generation and revenue. While these conditions apply equally to Sizewell B there are additional factors to be taken into consideration. A spurious trip of a main generating unit may lead to a trip of the reactor with an associated challenge to the shutdown and core cooling plant. The generator transformers, besides exporting power from the generators to the 400 kV National Grid, also import power from the Grid to the 11 kV Main Electrical System, which in turn is the preferred source of supply to the Essential Electrical System. The Main Unit Protection is designed to clear generator faults leaving this off-site power route intact. Hence failure to operate correctly could affect the integrity of the Essential Electrical Supplies. (Author)

Concept of electric power output control system for atomic power generation plant utilizing cool energy of stored snow

International Nuclear Information System (INIS)

Kamimura, Seiji; Toita, Takayuki

2003-01-01

A concept of the SEAGUL system (Snow Enhancing Atomic-power Generation UtiLity) is proposed in this paper. Lowering the temperature of sea water for cooling of atomic-power plant will make a efficiency of power generation better and bring several ten MW additional electric power for 1356 MW class plant. The system concept stands an idea to use huge amount of seasonal storage snow for cooling water temperature control. In a case study for the Kashiwazaki-Kariwa Nuclear Power Station, it is estimated to cool down the sea water of 29degC to 20degC by 80 kt snow for 3 hours in a day would brought 60 MWh electric power per a day. Annually 38.4 Mt of stored snow will bring 1800 MWh electric power. (author)

76 FR 13173 - Jersey Central Power & Light Company and PSEG Fossil, LLC; Notice of Application Tendered for...

Science.gov (United States)

2011-03-10

... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 2309-019] Jersey Central Power & Light Company and PSEG Fossil, LLC; Notice of Application Tendered for Filing With the.... Date Filed: February 18, 2011. d. Applicant: Jersey Central Power & Light Company and PSEG Fossil, LLC...

76 FR 66333 - Carolina Power & Light Company, H.B. Robinson Steam Electric Plant, Unit No. 2; Environmental...

Science.gov (United States)

2011-10-26

... NUCLEAR REGULATORY COMMISSION [Docket No. 50-261; NRC-2011-0247] Carolina Power & Light Company, H.B. Robinson Steam Electric Plant, Unit No. 2; Environmental Assessment and Finding of No Significant... Facility Operating License No. DPR-23, issued to Carolina Power & Light Company (the licensee), for...

VUJE, Inc. Company mission

International Nuclear Information System (INIS)

2008-01-01

VUJE is an engineering company that performs design, supply, implementation, research and training activities, particularly in the field of nuclear and conventional power generation. Our earlier research specialization in the field of nuclear power generation has gradually diversified into design and engineering activities during performing particular tasks. Nowadays we are able to provide all activities related to construction, operation, modernisation and finally termination of operation mainly of power generating facilities. Our objective is to offer complex, professional and quality solutions according to our customers' needs and thus assist to show real asset of nuclear energy generation. (author)

Nuclear Regulatory Commission issuances

International Nuclear Information System (INIS)

1996-04-01

This report includes the issuances received during the April 1996 reporting period from the Commission, the Atomic Safety and Licensing Boards, the Administrative Law Judges, the Directors' Decisions, and the Decisions on Petitions for Rulemaking. Included are issuances pertaining to: (1) Yankee Nuclear Power Station, (2) Georgia Tech Research Reactor, (3) River Bend Station, (4) Millstone Unit 1, (5) Thermo-Lag fire barrier material, and (6) Louisiana Energy Services

Nuclear Regulatory Commission issuances

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-04-01

This report includes the issuances received during the April 1996 reporting period from the Commission, the Atomic Safety and Licensing Boards, the Administrative Law Judges, the Directors` Decisions, and the Decisions on Petitions for Rulemaking. Included are issuances pertaining to: (1) Yankee Nuclear Power Station, (2) Georgia Tech Research Reactor, (3) River Bend Station, (4) Millstone Unit 1, (5) Thermo-Lag fire barrier material, and (6) Louisiana Energy Services.

Duke Power Company's control rod wear program

International Nuclear Information System (INIS)

Culp, D.C.; Kitlan, M.S. Jr.

1990-01-01

Recent examinations performed at several foreign and domestic pressurized water reactors have identified significant control rod cladding wear, leading to the conclusion that previously believed control rod lifetimes are not attainable. To monitor control rod performance and reduce safety concerns associated with wear, Duke Power Company has developed a comprehensive control rod wear program for Ag-In-Cd and boron carbide (B 4 C) rods at the McGuire and Catawba nuclear stations. Duke Power currently uses the Westinghouse 17 x 17 Ag-In-Cd control rod design at McGuire Unit 1 and the Westinghouse 17 x 17 hybrid B 4 C control rod design with a Ag-In-Cd tip at McGuire Unit 2 and Catawba Units 1 and 2. The designs are similar, with the exception of the absorber material and clad thickness. There are 53 control rods per unit

78 FR 16490 - Jersey Central Power and Light Company, PSEG Fossil, LLC; Notice of Authorization for Continued...

Science.gov (United States)

2013-03-15

... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 2309-000] Jersey Central Power and Light Company, PSEG Fossil, LLC; Notice of Authorization for Continued Project Operation On February 18, 2011, the Jersey Central Power and Light Company and PSEG Fossil LLC, licensees for the Yards...

Isolated systems with wind power. Main report

Energy Technology Data Exchange (ETDEWEB)

Lundsager, P.; Bindner, H.; Clausen, N.E.; Frandsen, S.; Hansen, L.H.; Hansen, J.C.

2001-06-01

The overall objective of this research project is to study the development of methods and guidelines rather than 'universal solutions' for the use of wind energy in isolated communities. The main specific objective of the project is to develop and present a more unified and generally applicable approach for assessing the technical and economical feasibility of isolated power supply systems with wind energy. As a part of the project the following tasks were carried out: Review of literature, field measurements in Egypt, development of an inventory of small isolated systems, overview of end-user demands, analysis of findings and development of proposed guidelines. The project is reported in one main report and four topical reports, all of them issued as Risoe reports. This is the Main Report Risoe-R-1256, summing up the activities and findings of the project and outlining an Implementation Strategy for Isolated Systems with Wind Power, applicable for international organisations such as donor agencies and development banks. (au)

Evaluating perceived quality of CELPE service: A Brazilian power company case study

International Nuclear Information System (INIS)

Paes de Barros Filho, Joao; Fritsch Damasio da Silva, Cleriston; Nascimento Melo, Maria Auxiliadora do; Dumke de Medeiros, Denise

2009-01-01

This paper presents an application of a methodology for the diagnosis and analysis of the service quality perceived by a Particular Group of CELPE Corporate Customers, a Brazilian power company at Pernambuco State. Concepts, on the power sector, of Quality in Services, Performance Objectives and Critical Factors of Success have been used to develop the analysis. Next, the Critical Factors for a power company were determined and classified in accordance with the performance objectives: Quality, Dependability, Speed and Flexibility. From the factors established, a questionnaire was created to collect data. The case studied involves quantitative research on CELPE's private corporate principal customers using statistical tests to measure internal consistency reliability of the questionnaire scales and to identify underlying concepts, in the four groups analyzed, through which the private corporate customers perceive quality in the given services. Among the goals of this study are to improve the relationship with principal Private Corporate Clients, to create customer loyalty, and to maximize efforts in providing the power supply service, all of them with a view to improving and determining the Global Satisfaction Index

Evaluating perceived quality of CELPE service: A Brazilian power company case study

Energy Technology Data Exchange (ETDEWEB)

Paes de Barros Filho, Joao [Federal University of Pernambuco (UFPE), Center of Technology and Geosciences, 5th floor, Academico Helio Ramos av., Cidade Universitaria, Recife, PE 50.670-901 (Brazil)], E-mail: joaopaes@celpe.com.br; Fritsch Damasio da Silva, Cleriston [Federal University of Pernambuco (UFPE), Center of Technology and Geosciences, 5th floor, Academico Helio Ramos av., Cidade Universitaria, Recife, PE 50.670-901 (Brazil)], E-mail: cleriston_silva@yahoo.com.br; Nascimento Melo, Maria Auxiliadora do [Federal University of Pernambuco (UFPE), Center of Technology and Geosciences, 5th floor, Academico Helio Ramos av., Cidade Universitaria, Recife, PE 50.670-901 (Brazil)], E-mail: manmelo@ufpe.br; Dumke de Medeiros, Denise [Federal University of Pernambuco (UFPE), Center of Technology and Geosciences, 5th floor, Academico Helio Ramos av., Cidade Universitaria, Recife, PE 50.670-901 (Brazil)], E-mail: ddm@ufpe.br

2009-04-15

This paper presents an application of a methodology for the diagnosis and analysis of the service quality perceived by a Particular Group of CELPE Corporate Customers, a Brazilian power company at Pernambuco State. Concepts, on the power sector, of Quality in Services, Performance Objectives and Critical Factors of Success have been used to develop the analysis. Next, the Critical Factors for a power company were determined and classified in accordance with the performance objectives: Quality, Dependability, Speed and Flexibility. From the factors established, a questionnaire was created to collect data. The case studied involves quantitative research on CELPE's private corporate principal customers using statistical tests to measure internal consistency reliability of the questionnaire scales and to identify underlying concepts, in the four groups analyzed, through which the private corporate customers perceive quality in the given services. Among the goals of this study are to improve the relationship with principal Private Corporate Clients, to create customer loyalty, and to maximize efforts in providing the power supply service, all of them with a view to improving and determining the Global Satisfaction Index.

Evaluating perceived quality of CELPE service. A Brazilian power company case study

Energy Technology Data Exchange (ETDEWEB)

De Barros Filho, Joao Paes; Da Silva, Cleriston Fritsch Damasio; Do Nascimento Melo, Maria Auxiliadora; De Medeiros, Denise Dumke [Federal University of Pernambuco (UFPE), Center of Technology and Geosciences, 5th floor, Academico Helio Ramos av., Cidade Universitaria, Recife, PE 50.670-901 (Brazil)

2009-04-15

This paper presents an application of a methodology for the diagnosis and analysis of the service quality perceived by a Particular Group of CELPE Corporate Customers, a Brazilian power company at Pernambuco State. Concepts, on the power sector, of Quality in Services, Performance Objectives and Critical Factors of Success have been used to develop the analysis. Next, the Critical Factors for a power company were determined and classified in accordance with the performance objectives: Quality, Dependability, Speed and Flexibility. From the factors established, a questionnaire was created to collect data. The case studied involves quantitative research on CELPE's private corporate principal customers using statistical tests to measure internal consistency reliability of the questionnaire scales and to identify underlying concepts, in the four groups analyzed, through which the private corporate customers perceive quality in the given services. Among the goals of this study are to improve the relationship with principal Private Corporate Clients, to create customer loyalty, and to maximize efforts in providing the power supply service, all of them with a view to improving and determining the Global Satisfaction Index. (author)

Radiotoxicity of Actinides During Transmutation in Final Stage of Atomic Power

International Nuclear Information System (INIS)

Gerasimov, Aleksander S.; Bergelson, Boris R.; Myrtsymova, Lidia A.; Tikhomirov, Georgy V.

2002-01-01

Characteristics of a transmutation mode in final stage of atomic power are analyzed. In this stage, transmutation of actinides accumulated in transmutation reactors is performed without feed by actinides from other reactors. The radiotoxicity during first 20 years of transmutation is caused mainly by 244 Cm. During following period of time, 252 Cf is main nuclide. Contribution of 246 Cm and 250 Cf is 5-7 times less than that of 252 Cf. During 50 years of a transmutation, the total radiotoxicity falls by 50 times. Long-lived radiotoxicity decreases slowly. During the period between T=50 years and T=100 years, long-lived radiotoxicity falls by 3.7 times. For each following 50 years after this period, long-lived radiotoxicity falls by 3.2 times. These results corresponding to neutron flux density 10 14 neutr/(cm 2 s) in transmutation reactor demonstrate that the final stage of a transmutation should be performed with use of high flux transmutation facilities which provide shorter time of transmutation. (authors)

Atomic power engineering as military and nuclear deterrence

International Nuclear Information System (INIS)

Koryakin, Yu.I.

2000-01-01

The legislative aspects of the nuclear power facilities protection during military actions are discussed. The IAEA position on this question is considered. Absence in the IAEA subject scope of the works on preparation of the treaty on prohibiting the destruction of nuclear power facilities means that the IAEA countries differently understand the necessity for introducing the legislative positions of the international atomic law. However, observation of the unwritten codex of mutual nuclear deterrence gives rise to the hope for the wise solution of the problem on the nuclear power objects protection during the military actions [ru

Atomic power project, Kakrapar, Gujarat

International Nuclear Information System (INIS)

Varadarajan, G.

1992-01-01

The atomic power project at Kakrapar, comprising of two units of 235 MW each, went critical very recently in September 1992. The work consisted of construction of reactor and turbine buildings, outer and inner containment walls, calandria vault, natural draught cooling tower, etc. Nearly 152,000m 3 of normal aggregate concrete and 3,500m 3 of heavy aggregate concrete were produced and poured. The paper describes salient innovative construction features of the project. Incidentally, the project received a Certificate of Merit in the Excellence in Concrete competition held by the Maharashtra India Chapter of the American Concrete Institute. (author). 7 figs

The Chip-Scale Atomic Clock - Low-Power Physics Package

Science.gov (United States)

2004-12-01

36th Annual Precise Time and Time Interval (PTTI) Meeting 339 THE CHIP-SCALE ATOMIC CLOCK – LOW-POWER PHYSICS PACKAGE R. Lutwak ...pdf/documents/ds-x72.pdf [2] R. Lutwak , D. Emmons, W. Riley, and R. M. Garvey, 2003, “The Chip-Scale Atomic Clock – Coherent Population Trapping vs...2002, Reston, Virginia, USA (U.S. Naval Observatory, Washington, D.C.), pp. 539-550. [3] R. Lutwak , D. Emmons, T. English, and W. Riley, 2004

Memorial 1997 - ENDESA (Chilean Electricity Company); ENDESA - Memoria 1997

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-12-31

This report provides a comprehensive survey, in depth assessment of the activities overview of ENDESA, Chilean Electricity Company, highlighting economical information and including historical and technical aspects. Economics is its focal point, but other relevant data are shown, like technical data on hydroelectric and thermoelectric power plants. Main activities developed by ENDESA are described, such in Chile as in the foreign. Data on power generation, transmission and transport are also presented and an economical balance of each colligated company are done and analysed 35 figs., 115 tabs.

Environmental Disclosure of Electric Power Companies Listed in the Corporate Sustainability Index (CSI

Directory of Open Access Journals (Sweden)

Clésia Ana Gubiani

2012-12-01

Full Text Available The study aimed to verify the level of disclosure of environmental information in the administration reports of the energy companies listed in the Corporate Sustainability Index (CSI. A descriptive and quantitative research was done, using the content analysis technique on the administration reports from 2006 to 2008. The sample consisted of 11 electric power companies listed in the CSI. For quantitative analysis of the disclosure index, the data collection instrument was based on the study of Rover, Murcia and Borba (2008, which proposes eight environmental categories and 36 subcategories. For the whole analysis of the data were elaborated networks of the items disclosed in each company, using the software UNICET ®. The survey results showed that there is satisfactory disclosure in the categories of environmental policies and education, training and research environment. However, it was found that there is need for greater disclosure of categories of products impacts and processes in the environment, power polices and financial environmental information. It was concluded that the information disclosed in the administration reports of the companies surveyed about the environmental information do not respect the principle of full disclosure.

Performance of on-power fuelling equipment at Rajasthan Atomic Power Station

International Nuclear Information System (INIS)

Jayabarathan, S.; Gopalakrishnan, S.

1977-01-01

Natural uranium reactors on account of their intrinsically low reactivity need frequent refuelling. The Rajasthan Atomic Power Station based on natural uranium reactors has, therefore, been provided with on-power fuel handling system which was installed in 1972. Its performance has met the design intent and operational objectives which are enumerated. However, continuous fuelling 7 to 10 days has not been possible because frequent maintenance of refuelling system is needed on account of certain deficiencies major of which is the heavy water leakage. For better performance, installation of a programmable logic controller is suggested. Mention has also been made of inadequate number of skilled man-power required for maintenance which leads to quick depletion of man-rem of all the available personnel trained for maintenance work. (M.G.B.)

Ownership relations and cooperation in the Norwegian power market

International Nuclear Information System (INIS)

Singh, Balbir; Skjeret, Frode

2006-01-01

The Norwegian Competition Authority (KT) under a grant from The Ministry for Government Administration and Reform (FAD) commissioned a study in December 2005 to outline the extent and nature of cooperation among the power production companies in the Norwegian Power market. The main objective of the study was to establish an updated data set that documents the status with respect to distribution of ownership of generation capacity, and to identify the main forms of cooperation and information exchange among the power generation companies in Norway. Both secondary and primary sources have been used in the study. Data related to the distribution of generation capacity is mainly based on secondary sources and covers the total population consisting of 622 power plants and 183 companies in the Norwegian power market. In addition, requests for information were sent to a sample of power companies to collect primary information that could shed light on the status, trend, motivations, behavioral constraints, and exchange of information associated with different forms of cooperation between the power producers. The complete data set and results are modeled in a spread sheet based database (OPS) that accompanies this report. This report summarizes the main findings of the study. The primary data collected from the power companies during the sample survey is not included in this report. Only the main conclusions drawn on the basis of the analysis of the information provided by the respondents are presented in this report. It is important to emphasize that this publication reports data and information as collected from the primary and secondary sources in this project. The material presented in this publication reports a summary of the collected information and is not meant to draw any conclusions about the existence or otherwise of any form of collusion among the responding companies (author) (ml)

(Shippingport Atomic Power Station). Quarterly operating report, third quarter 1980

Energy Technology Data Exchange (ETDEWEB)

Zagorski, J. F.

1980-01-01

At the beginning of the third quarter of 1980, the Shippingport Atomic Power Station was operating with the 1A, 1B, 1C, and 1D reactor coolant loops and the 1AC and 1BD purification loops in service. During the quarter, the Station was operated for Duquesne Light Company System grid including base load and swing load operation. Twelve (12) planned swing load operations were performed on the LWBR Core this quarter to complete the LWBR operating plan of fifty (50) during this operating phase. The Station was shutdown on September 12 for the Fall 1980 Shutdown and remained in this mode through the end of the quarter. The LWBR Core has generated 18,297.98 EFPH from start-up through the end of the quarter. There were no radioactive liquid discharges from the Radioactive Waste Processing System to the river this quarter. The radioactive liquid waste effluent line to the river remained blanked off to prevent inadvertent radioactive liquid waste discharges. During the quarter, approximately 0.001 curies of Xe 133 activity were released from the station. The radioactivity released from Shippingport Station is far too small to have any measurable effect on the general background environmental radioactivity outside the plant.

Final Technical Report. Upgrades to Alabama Power Company Hydroelectric Developments

Energy Technology Data Exchange (ETDEWEB)

Crew, James F. [Southern Company Generation, Birmingham, AL (United States). Hydro Services; Johnson, Herbie N. [Southern Company Generation, Birmingham, AL (United States). Hydro Services

2015-03-31

From 2010 to 2014, Alabama Power Company (“Alabama Power”) performed upgrades on four units at three of the hydropower developments it operates in east-central Alabama under licenses issued by the Federal Energy Regulatory Commission (“FERC”). These three hydropower developments are located on the Coosa River in Coosa, Chilton, and Elmore counties in east-central Alabama.

Summary of main points

International Nuclear Information System (INIS)

2006-01-01

In conjunction with its 6. annual meeting, the WPDD in close co-operation with the FSC held a Topical session on 'Stakeholder Involvement in Decommissioning' on November 14, 2005. The session was attended by 36 participants totally representing 14 NEA member countries and 2 international organisations. Two keynote addresses were given at the Topical Session. The first one treated of what is needed for robust decisions and how to bring all stakeholders into the debate. In the second keynote address a summary was made on what have been said on stakeholder involvement in decommissioning during earlier meetings of the WPDD. The main part of the session was then devoted to views from different stakeholders regarding their role and their involvement. This part contained viewpoints from local communities (Kaevlinge in Sweden and Port Hope in Canada), authorities (Scottish Executive and CSNC) and operators (EDF from France and EWN from Germany). Case studies from the decommissioning of Dounrey in the UK and from Trojan and Main Yankee in the USA were presented in the end part of the Topical session followed by a summary and lessons learnt report by the Rapporteur. A detailed programme of the Topical session can be seen in Appendix 1

Inquiry relating to modifications of reactor installation in Genkai No. 1 and 2 nuclear power plants of Kyushu Electric Power Company, Inc

International Nuclear Information System (INIS)

1979-01-01

Application was made to the Minister of International Trade and Industry for the license relating to the modifications of reactor installation in the Genkai No. 1 and 2 nuclear power plants, Kyushu Electric Power Company, Inc., on February 27, 1979, from the president of the company. After the safety evaluation was finished by the Ministry of International Trade and Industry, inquiry was conducted to the head of the Atomic Energy Safety Commission (AESC) on June 15, 1979 from the Minister of International Trade and Industry. The investigation and discussion were commenced by the AESC on June 19, 1979. The modifications of the reactor installation are the increase of new fuel storage capacity from about 1/3 to about 2/3 of in-core fuel for each plant, the new establishment of a miscellaneous solid waste incinerator which is common to both plants, and the enlargement of a solid waste storage which is also common to both plants. The contents of the safety examination for each item written above are presented. The prevention of criticality is carefully practiced for the new fuel storage by putting fuel assemblies in stainless steel can type racks and locating the fuel assemblies at the proper distance. The miscellaneous solid waste incinerator building is designed as the B class aseismatic structure and also as the controlled area with adequate shielding and ventilating facilities. The decontamination factor of the incinerator facility is more than 10 5 , and the necessary monitoring system is provided in the building. Concerning the solid waste storage, the additional storage area is about 1600 m 2 , and the storage capacity is about ten years quantity. This building is designed as the B class aseismatic structure. (Nakai, Y.)

Analysis of relationship between the local governments and the power companies through the changes of safety agreements

International Nuclear Information System (INIS)

Sugawara, Shin-etsu; Inamura, Tomoaki; Kimura, Hiroshi; Madarame, Haruki

2009-01-01

In Japan, safety of nuclear facilities is regulated by the central government and local governments are responsible for protecting the local public. To operate nuclear facilities in local communities, local governments would conclude safety agreements with power companies. In recent years, local governments have used the safety agreements as excuse for delaying the operations of nuclear facilities. The legal basis of the safety agreements was questioned by some who considered that this was the cause of the stranded relationship between local governments and power companies, and in some cases, the interrupted nature of electricity supply. To understand the sources of this difficult relationship, safety agreements must be analyzed, although these documents may have undergone revisions, and various regulations may have changed. By analyzing the safety agreements and revisions, we found that the relationship between local governments and power companies gradually changed over time, which can be divided into the following 3 stages: (1) in the early 70s, the dawn stage when local governments groped with the situation of nuclear facilities built in their communities; (2) from late 70s to 90s, the stage when local governments demanded information, and (3) from late 90s to present, the stage when local governments demand information and trustworthiness. This paper shows the results of analyzing the relationship changes between local governments and power companies. We conclude that viewpoints of local governments on nuclear power evolve, as social responsibilities of power companies stipulated in safety agreements also evolve over time. (author)

Financing the electric power utilities, especially the nuclear power in Japan

International Nuclear Information System (INIS)

Tajima, T.

1975-04-01

Electric power demands in Japan have shown a remarkable growth at an annual rate of 12% since 1965. Nine electric power companies have invested large amounts of money so far, amounting to over 1 trillion yen every year since 1972. A survey of the electric power supply system and an estimation of the electric power demands in 1980 and in 1985 are given. It is expected that the main portion of electric power in the future will gradually be generated by nuclear plants. Financial features of the electrical power utilities, the credit risk of the electric power utilities, and the raising of funds by electric power utilities are discussed. It is concluded that it will be necessary (1) to expand the capital market, (2) to enable the electric power companies to issue a sufficient amount of bonds, (3) to make the Government financing institutions, such as the Japan Development Bank, provide the electric power companies with larger funds on a long-term and low-interest rate basis, and (4) even to take such drastic steps as subsidizing interest on private loans to the electric power companies. (B.P.)

A proposal for human factors education in a power plant company

International Nuclear Information System (INIS)

Hikono, Masaru

2004-01-01

The author was asked by a power plant company to investigate how to change the actual education system concerning human factor education for the plant staff. First, the problems faced by actual education system were investigated based on the results of a large number of surveys conducted in educational fields, and various documents. In the present paper, the author describes the newly proposed educational program., using as illustration a case study. The findings of the present study suggests that, concerning the content of the educational program, it is indispensable for each company to develop a curriculum based on its specific needs. (author)

78 FR 32385 - Exelon Generation Company, LLC; CER Generation II, LLC; Constellation Mystic Power, LLC...

Science.gov (United States)

2013-05-30

... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Docket No. EL13-64-000] Exelon Generation Company, LLC; CER Generation II, LLC; Constellation Mystic Power, LLC; Constellation NewEnergy...) Rules of Practice and Procedure, 18 CFR 385.207, Exelon Generation Company, LLC, CER Generation II, LLC...

Interim safety evaluation report related to operation of Enrico Fermi Atomic Power Plant, Unit 2, Detroit Edison Company

International Nuclear Information System (INIS)

1977-09-01

This interim report summarizes the scope and results of the radiological safety review performed to date by the NRC staff with respect to the operating license phase for the Enrico Fermi Atomic Power Plant, Unit 2. The major effort was the review of the facility design and proposed operating procedures described in applicant's Final Safety Analysis Report. In the course of the review, several meetings were held with representatives of the applicant to discuss plant design, construction and proposed operation. Additional information was requested, which the applicant provided through Amendment 7 to the Final Safety Analysis Report. A chronology of the principal actions relating to the review of the application is attached as Appendix A to the report. The Final Safety Analysis Report and amendments thereto are available for public inspection at the Nuclear Regulatory Commission Public Document Room, 1717 H Street, N. W., Washington, D.C. and at Monroe County Library System, 3700 South Custer Road, Monroe, Michigan 48161

Perspectives at the East European engineering companies in the field of power industry in the power-plant construction globalization conditions

International Nuclear Information System (INIS)

Ganchev, R.

2001-01-01

A large group of companies, institutes, boiler and power engineering work ect. from East European countries, currently in process of reorganization or already transformed into new-established private companies and corporations possess significant intellectual property in the field of thermal power technologies and equipment and broad experience in the design and the erection of thermal power plants. In many cases this know-how is not only competitive to that of the large companies of the West and of the Far East, but frequently it also proves to have a number of advantages. However, in the years of transition in these countries and simultaneous globalization, the owners of this potentials meet with difficulties and restrictions to realize it fully. Large investment projects - for new or replacement capacities or comprehensive rehabilitation or refurbishment of TPPs - are accessible only for the financially powerful EPC-contractors and key equipment suppliers, for which large bank credits are accessible. The near future perspective, for the scientists and experts that have accumulated this capital, is in the opportunity to employ the extensive experience and know-how of this firms in the forthcoming large-scale rehabilitation projects in these countries, and primarily, in the solution of specific problems, that have not been solved so far, provided that the projects are awarded not on the basis of the financial power of the contractors but on the basis of the efficiency of the proposed original solutions

Nuclear industrial and power complex of Kazakhstan

International Nuclear Information System (INIS)

Shemanskiy, V.A.; Cherepnin, Yu.S.; Zelenski, D.I.; Papafanasopulo, G.A.

1997-01-01

While selecting the national power supply strategy of economic potential development four factors are laid in the basis of discussions and technical and economic decisions: effect either power complexes on people health, consequences environmental, economics and resources existence. Atomic power requires the balanced approach to power politics which, by that, avoids the dependence on any energy source. The existing electric power generation structure in Kazakhstan is Featured by the following numbers: -TEPP on coal - 79%; - TEPP on gas-black-oil fuel - 12-13%; - HEPP - 6-7%; - Atomic PP - about 0.7%. The ground for nuclear power development is considerable uranium deposits and rather developed atomic industry. Kazakhstan atomic industry includes: - uranium extractive enterprise - State Holding Company 'Tselinnyi Mining-Chemical Plant' (SHC 'TCMP'), Stepnoy Ore Division (SOD), Central ore Division 6 (COD 6), KASKOR (Aktau); - plant on fuel pellets production for APP (JSC 'UMP'); - plants on production of rare and rare-earth metals - Irtysh Chemical and Metallurgical (JSC 'CMP') and Ulba Metallurgical Plant (JSC 'UMP'); - Mangyshlak Power Plant (MAEK); - Scientific Complex of NNC RK of Ministry of Science-Academy of Science. About 25% of world deposits and uranium resources are concentrated in Kazakhstan bowels. The scientific potential of atomic production complex of the Republic of Kazakhstan is concentrated in NNC RK divisions (IAE and INP) and at JSC 'UMP' and MAEK enterprises. Ministry Energy and Nature Resources is a Board responsible for the development of atomic industry and power branches. Atomic Energy Agency of the Republic Kazakhstan performs the independent effective state supervision and control providing safety of atomic industry power installations operation

Measures associated with the dose limitation system at the TVO Power Company

International Nuclear Information System (INIS)

Ruuskanen, A.T.; Sundell, R.O.

1982-01-01

The paper discusses radiation protection practices at the TVO Power Company, which owns and operates two BWR units of Asea-Atom design at Olkiluoto, Finland. The installed electric power of each unit is 660MW. The full power operation of TVO I and TVO II began in 1979 and 1980, respectively. The dose limitation system calls for an organization which is responsible for radiation protection. This organization at the plant site is described. To limit doses a good knowledge of the work activities which cause doses is needed. There is a very up-to-date microprocessor-based work dosimetry system at the TVO power plant. The system provides a practicable means of measuring personal doses from various work activities. It also makes the allocation of radiation protection measures possible. The system and experience in applying it are discussed. The dose limitation system presupposes the realization of the optimization principle. The practice applied at TVO in order to limit internal contamination is presented. Owing to this practice, workers' internal doses have remained at a considerably low level. The paper discusses the ALARA values of different kinds of respiratory equipment. These values, which vary from 2x10 4 to 1x10 6 FIM/man.Sv (1 FIM=approx. US$ 0.22), can be used in the evaluation of different measures in avoiding internal doses. The operating policy of movable lead shields is presented. The ALARA value of this activity is evaluated to be about 5x10 4 FIM/man.Sv and on that basis it can be concluded that the use of movable lead shields is very efficient. The dose statistics for TVO's plant are presented. The doses have been less than 0.001 man.Sv/MW.a. Although the dose statistics for TVO are very good it is not realistic to consider solely the optimization aspect of radiation protection. The costs must also be kept in mind; these are presented in the paper. Problems in assessing the level of radiation protection practices on an annual basis are briefly discussed

Innovation in electric power technologies in 2009

International Nuclear Information System (INIS)

Ohfusa, Takahiro; Hayasaka, Eiji; Ino, Hiroyuki

2010-01-01

This is a report of the title by Tokyo Electric Power Company, Kansai Electric Power Co., Inc, Tohoku Electric Power and other nine enterprises in Japan. The outline is as follows. Tokyo Electric Power Company stated pipe thinning by the hot water based two-phase flow testing device, development of technologies for corrosion protection of nuclear reactor using titanium oxide, evaluation of fatigue damage by EBSD, and study of duty on the nuclear power plant. Japan Atomic Power Company (JAPC) stated the mechanism of decrease in exposure dose of the primary coolant system by zinc infusion, outline of Air Operated Valve Intelligent Diagnostic Analysis System (AVIDAS) and the grand packing system, development of SAPLS, the automatic search program of fuel position for design of PWR related core, development of compact containment water reactor (CCR) and FBR cycle system, investigation of the chain destruction of active fault under consideration of dynamic interaction of active faults and decommissioning of Tokai Nuclear Power Plant. Electric Power Development Company reported construction of the Oma Nuclear Power Plant, a future nuclear plant in Oma, Aomori. The reactor will be capable of using 100% MOX fuel core (MOX-ABWR). The operation will start November 2014. (S.Y.)

77 FR 16026 - Cargill Power Markets, LLC v. Public Service Company of New Mexico; Notice of Compliance Filing

Science.gov (United States)

2012-03-19

... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Docket No. EL10-61-002] Cargill Power Markets, LLC v. Public Service Company of New Mexico; Notice of Compliance Filing Take notice that on March 12, 2012, Public Service Company of New Mexico and Cargill Power Markets, LLC submitted a...

The Tokai-mura JCO criticality accident and the activities of the accident countermeasure support team of Electric Power Companies, Japan

International Nuclear Information System (INIS)

Ogawa, Junko

2000-01-01

A criticality accident occurred at the JCO Tokai-mura nuclear fuel processing plant on September 30, 1999. This accident brought the damages which were unrivaled in the history of atomic energy development in Japan, seriously influencing the citizen life to such an extent as requesting for 320,000 inhabitants within 10 kilometers radius to stay indoors for as long as 18 hours. However, it could be said that though three workers suffered fatal injuries, no substantial hazards were made upon the regional inhabitants due to little release of radioactive substances. This video recorded the activities of the Accident Countermeasure Support Team of the Electric Power Companies immediately after the accident occurred, showing the chronological overview of the particulars of the accident. (author)

Experience of Minas Gerais Energetic Company (CEMIG) in feasibility studies from hydroelectric power plants: energetic-economic studies

International Nuclear Information System (INIS)

Ramos, O.C.; Bras, A.J.F.; Batista Neto, R.P.; Salles Filho, M.P.

1989-01-01

The experience of Minas Gerais Energetic Company (CEMIG) - Brazil, on the use of dimensioning methodology for hydroelectric power plant from the Coordinated Group of Planning System was described, showing the problems with its use and the solutions, mainly the reservoir and the dimension of installed potential. It was concluded that the calculation procedures of the marginal costs for dimensioning, so as to become these costs more representative in future structure of the Brazilian generator park and less dependent to the oscillation due to conjuncture problems, must be re-evaluated. (C.G.C.). 7 refs, 3 figs, 1 tab

Influence of Various Pulp Properties on the Adhesion Between Tissue Paper and Yankee Cylinder Surface

Directory of Open Access Journals (Sweden)

Jonna Boudreau

2014-02-01

Full Text Available The strength of the adhesion between the paper and the drying Yankee cylinder is of great importance with respect to the final properties of a tissue paper product. Therefore, the effects of a few potentially important pulp properties have been evaluated in laboratory experiments. Four highly different kraft pulps were used, and the adhesion strength was measured by means of the force required when scraping off a paper from a metal surface with a specifically designed knife mounted on a moving cart. The adhesion strength was observed to increase with increasing grammage and increasing degree of beating of the pulp. It was also found that pulps containing more fines, or with higher hemicellulose content, gave rise to higher adhesion strength.

Nuclear Regulatory Commission issuances, March 1975

International Nuclear Information System (INIS)

1975-04-01

Reactor licensing actions taken by the Nuclear Regulatory Commission, the Atomic Safety and Licensing Appeal Board and the Atomic Safety and Licensing Boards for March 1975 are presented. Action was included for the following reactors: Big Rock Point Nuclear Plant; West Valley Reprocessing Plant; Limerick Generating Station, Units 1 and 2; Midland Plants, Units 1 and 2; Wolf Creek Generating Station, Unit 1; Monticello Nuclear Generating Plant, Unit 1; Douglas Point Nuclear Generating Station, Units 1 and 2; Seabrook Station, Units 1 and 2; Vermont Yankee Nuclear Power Station; and WPPSS Hanford Units 1 and 4. (U.S.)

The advanced main control console for next japanese PWR plants

International Nuclear Information System (INIS)

Tsuchiya, A.; Ito, K.; Yokoyama, M.

2001-01-01

The purpose of the improvement of main control room designing in a nuclear power plant is to reduce operators' workload and potential human errors by offering a better working environment where operators can maximize their abilities. In order to satisfy such requirements, the design of main control board applied to Japanese Pressurized Water Reactor (PWR) type nuclear power plant has been continuously modified and improved. the Japanese Pressurized Water Reactor (PWR) Utilities (Electric Power Companies) and Mitsubishi Group have developed an advanced main control board (console) reflecting on the study of human factors, as well as using a state of the art electronics technology. In this report, we would like to introduce the configuration and features of the Advanced Main Control Console for the practical application to the next generation PWR type nuclear power plants including TOMARI No.3 Unit of Hokkaido Electric Power Co., Inc. (author)

Dall’anticolonialismo all’anti-imperialismo yankee nei movimenti terzomondisti di fine anni Sessanta

Directory of Open Access Journals (Sweden)

Marica Tolomelli

2016-12-01

Full Text Available The article focuses on the rise of third-worldism as a form of political solidarity with many decolonization conflicts spread in the 1950s and 1960s and its transformation in a one-sided idea of anti-imperialism that put the US foreign politics at the centre of the international stage. This kind of selective criticism – addressing the so-called yankee imperialism – grounded principally on the US military intervention in Vietnam since 1965 but eventually it evolved in a kind of ideological paradigm that made of the USA the unique cause of all problems affecting states emerged from decolonization. This ideological turn hindered a deep and wide understanding of the complex and manifold forms of entanglements that followed, replaced and in some cases occurred as new factors within the world order established in the second half of the 20th century.

Power grid, mains filtering and power line communications ... a root cause for incompatibilities

NARCIS (Netherlands)

Coenen, Mart

2013-01-01

The power grid is intentionally meant to distribute electrical energy at the mains frequency, as produced by the electricity generating plants, towards the end-users. The three-phase low-voltage distribution network can be utilized more efficiently when a power factor of 1 is achieved and no

Development on power distribution technologies of four electric power companies in Japan. The Tokyo Electric Power Co. , Inc

Energy Technology Data Exchange (ETDEWEB)

1989-07-01

Electric power companies have been needed to cope with various needs in accordance with the progress of highly information-oriented society, the improvement of industrial technology, and the advancement and diversification of the living environment. In such situation, the power distribution section of Tokyo Electric Power has promoted technical development, setting up following priority items to put into operation: to reduce power failure caused by works and accidents, to improve reliability in supply, to reduce costs of construction and all over business management, to serve customers to answer various needs, to develop new technology and new methods based on the medium- and long-term prospect, and so forth. Several examples of recent technical development are introduced here. They are as follows; compact equipment and materials for electric poles to match the circumstances of cities and to simplify the construction method for power distribution, a 750kVA large high-voltage power-generation truck to make provision against an emergency such as a disaster by a typhoon, a compact transformer used on the ground, a high-voltage automatic cabinet, and a detector to find the failure of indoor power distribution works in resistances in a short time. 8 figs.

Forecasted electric power demands for the Delmarva Power and Light Company. Volume 1 and Volume 2. Documentation manual

International Nuclear Information System (INIS)

Estomin, S.L.; Beach, J.E.

1990-10-01

The two-volume report presents the results of an econometric forecast of peak load and electric power demands for the Delmarva Power and Light Company (DP ampersand L) through the year 2008. Separate sets of models were estimated for the three jurisdictions served by DP ampersand L: Delaware, Maryland and Virginia. For both Delaware and Maryland, econometric equations were estimated for residential, commercial, industrial, and streetlighting sales. For Virginia, equations were estimated for residential, commercial plus industrial, and streetlighting sales; separate industrial and commercial equations were not estimated for Virginia due to the relatively small size of DP ampersand L's Virginia Industrial load. Wholesale sales were econometrically estimated for the DP ampersand L system as a whole. In addition to the energy sales models, an econometric model of annual (summer) peak demand was estimated for the Company

An approach for obtaining high availability at Madras Atomic Power Station

International Nuclear Information System (INIS)

Subramanian, K.S.; Murthy, K.S.N.; Hariharan, K.

1977-01-01

Causes of unavailability of nuclear power plants are described, with special reference to the Madras Atomic Power Plant (MAPP). Design inadequacies, component failures, installation errors, etc. encountered at the MAPP are enumerated. Systems testing followed as well as recruitment and training efforts resorted to are also reported. (K.B.)

Atom for peace, code for war. The technology policy of the atomic power solution in Finland between 1955-1970

International Nuclear Information System (INIS)

Sarkikoski, T.

2011-01-01

This dissertation investigates the atomic power solution in Finland between 1955 - 1970. During these years a national arrangement for atomic energy technology evolved. The foundations of the Finnish atomic energy policy; the creation of basic legislation and the first governmental bodies, were laid between 1955 - 1965. In the late 1960's, the necessary technological and political decisions were made in order to purchase the first commercial nuclear reactor. A historical narration of this process is seen in the international context of 'atoms for peace' policies and Cold War history in general. The geopolitical position of Finland made it necessary to become involved in the balanced participation in international scientific-technical exchange and assistive nuclear programs. The Paris Peace Treaty of 1947 categorically denied Finland acquisition of nuclear weapons. Accordingly, from the 'Geneva year' of 1955, the emphasis was placed on peaceful purposes for atomic energy as well as on the education of national professionals in Finland. An initiative for the governmental atomic energy commission came from academia but the ultimate motive behind it was an anticipated structural change in the supply of national energy. Economically exploitable hydro power resources were expected to be built within ten years and atomic power was seen as a promising and complementing new energy technology. While importing fuels like coal was out of the question, because of scarce foreign currency, domestic uranium mineral deposits were considered as a potential source of nuclear fuel. Nevertheless, even then nuclear energy was regarded as just one of the possible future energy options. In the mid-1960 s a bandwagon effect of light water reactor orders was witnessed in the United States and soon elsewhere in the world. In Finland, two separate invitations for bids for nuclear reactors were initiated. This study explores at length both their preceding grounds and later phases. An

Use of MCNP for characterization of reactor vessel internals waste from decommissioned nuclear reactors

International Nuclear Information System (INIS)

Love, E.F.; Pauley, K.A.; Reid, B.D.

1995-09-01

This study describes the use of the Monte Carlo Neutron-Photon (MCNP) code for determining activation levels of irradiated reactor vessel internals hardware. The purpose of the analysis is to produce data for the Department of Energy's Greater-Than-Class C Low-Level Radioactive Waste Program. An MCNP model was developed to analyze the Yankee Rowe reactor facility. The model incorporates reactor geometry, material compositions, and operating history data acquired from Yankee Atomic Electric Company. In addition to the base activation analysis, parametric studies were performed to determine the sensitivity of activation to specific parameters. A component sampling plan was also developed to validate the model results, although the plan was not implemented. The calculations for the Yankee Rowe reactor predict that only the core baffle and the core support plates will be activated to levels above the Class C limits. The parametric calculations show, however, that the large uncertainties in the material compositions could cause errors in the estimates that could also increase the estimated activation level of the core barrel to above the Class C limits. Extrapolation of the results to other reactor facilities indicates that in addition to the baffle and support plates, core barrels may also be activated to above Class C limits; however the classification will depend on the specific operating conditions of the reactor and the specific material compositions of the metal, as well as the use of allowable concentration averaging practices in packaging and classifying the waste

10CFR61 waste form conformance program for asphalted radwaste

International Nuclear Information System (INIS)

Kobran, M.J.; Guarini, W.J.

1987-01-01

With the enactment of Title 10, Code of Federal Regulation, Part 61, ''Licensing Requirements for Land Disposal of Radioactive Waste'' came the imposition of new requirements on licensees who dispose of radioactive waste via shallow land burial. Specifically, 10CFR61 both imposed a waste classification system requiring segregation of waste according to hazard and established waste performance characteristics required to enhance stability of the burial site. In order to provide licensees with guidance regarding implementation of applicable requirements of 10CFR61, the NRC low level Waste Licensing Branch issued two Technical Positions. To demonstrate compliance of asphalted radwaste produced with oxidized asphalt with 10CFR61 criteria and the NRC's Technical Position, five utilities combined resources. The five utilities sponsoring the program were Public Service Electric and Gas Company, Niagara Mohawk Power Company, Detroit Edison Company, New Hampshire Yankee, and Consumers Power Comany

Operation and maintenance experience at the General Atomic Company's TRIGA reactor facility at San Diego, California

International Nuclear Information System (INIS)

Whittemore, W.L.; Stout, W.A.; Shoptaugh, J.R.; Chesworth, R.H.

1982-01-01

Since the startup of the original 250 kW TRIGA Mark I reactor in 1958, General Atomic Company has accumulated nearly 24 years of operation and maintenance experience with this type of reactor. In addition to the nearly 24 years of experience gained on the Mark I, GA has operated the 1.5 MW Advanced Prototype Test Reactor (Mark F) for 22 years and operated a 2 MW below-ground TRIGA Mark III for five years. Information obtained from normal and abnormal operation are presented. (author)

Northern States Power Company's open transmission tariff from a customer's perspective

International Nuclear Information System (INIS)

Marietta, K.E.; Achinger, S.K.

1993-01-01

In October of 1990, Northern States Power Company (NSP or Company), filed a unique open transmission tariff for both captive customers and through-system transactions. This is an important step towards expanding transmission services in the United States. Many individuals in the utility industry, who may be considering Imposing generation costs on transmission services, have been closely monitoring NSP's case which is currently before the Federal Energy Regulatory Commission (FERC). NSP's innovative generation costs include charges for reactive power production, frequency control, load dispatching, and load following. The results of this case may also have an important impact on the future of open transmission tariffs. Rates for these services depend on the customer's classification as either a captive or through-system consumer. The proposed tariff raises critical issues related to the costing of these transmission services. NSP's methodology has caused serious concern because the proposed tariff would increase transmission costs by an average of 53%. This paper will discuss the benefits of transmission, proposed rates, contract terms, and costing methodologies of NSP's plan

Clean coal technology project to Polk Power Station, Tampa Electric Company, Florida, Volume 1: Report

International Nuclear Information System (INIS)

1994-06-01

Tampa Electric Company proposes to construct and operate a 1,150-MW power station in southwestern Polk County, Florida. The proposed Polk Power Station would require an EPA NPDES permit for a new source and would include a 260-MW IGCC unit as a DOE Clean Coal Technology demonstration project. This EIS document assesses the proposed project and alternatives with respect to environmental impacts. Mitigative measures are also evaluated for the preferred alternative. Included in this Volume I are the following: alternatives including Tampa Electric Companies proposed project (preferred alternative with DOE financial assistance); affected environment; environmental consequences of the alternatives

The low-temperature water-water reactor for district heating atomic power plant (DHPP)

International Nuclear Information System (INIS)

Skvortsov, S.A.; Sokolov, I.N.; Krauze, L.V.; Nikiporetz, Yu.G.; Philimonov, Yu.V.

1977-01-01

The district heating atomic power plant in the article is distinguished by the increased reliability and safety of operation that was provided by the use of following main principles: relatively low parameters of the coolant; the intergral arrangement of equipment and accordingly the minimum branching of the reactor circuit; the natural circulation of coolant of the primary circuit in the steady-state, transient and emergency regimes of reactor operation; the considerable reserves of cold water of the primary circuit in the reactor vessel, providing the emergency cooling; the application of two shells each of which is designed for the total working pressure, the second shell is made of prestressed reinforced concrete that eliminates its brittle failure. (M.S.)

Remote calibration of Resistance Temperature Devices (RTDs): Final report

International Nuclear Information System (INIS)

Blalock, T.V.; Roberts, M.J.

1988-02-01

Johnson noise power measuring techniques have been used to calibrate platinum resistance temperature detectors (RTDs) installed in an operating nuclear plant - Connecticut Yankee Atomic Power Company's Haddam Neck Nuclear Plant - achieving agreement with the dc calibration from better than 0.1% to as much as 1% (0.54 to 9.7 0 F) at the normal operating temperature of 585 0 F. Tests were also conducted at plant shutdown conditions. In this application, RTDs with an ice point resistance of 200 Ω were connected with four-wire extension cables approximately 100-ft long to a test station in containment. Methods were developed for in situ characterization of the extension cables and for quantitative measurement of and correction for nonthermal induced noise. Analysis of dc calibration methods showed that resistance-temperature tables used with industrial PRTs may be in error by 0.2 0 F or 0.02% A (expressed as a percentage of absolute temperature in either Kelvin or degrees Rankine) at 540 0 F. Recalibration of the RTDs measured in the plant tests showed differences of about 2.5 0 F or 0.2% A at 540 0 F from calibration tables used in the plant

Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites

Energy Technology Data Exchange (ETDEWEB)

Maheras, Steven J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Best, Ralph E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Ross, Steven B. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Buxton, Kenneth A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); England, Jeffery L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McConnell, Paul E. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Massaro, Lawrence M. [Federal Railroad Administration (FRA) (United States); Jensen, Philip J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2014-10-01

This report presents a preliminary evaluation of removing used nuclear fuel (UNF) from 12 shutdown nuclear power plant sites. At these shutdown sites the nuclear power reactors have been permanently shut down and the sites have been decommissioned or are undergoing decommissioning. The shutdown sites are Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, Zion, Crystal River, Kewaunee, and San Onofre. The evaluation was divided into four components: characterization of the UNF and greater-than-Class C low-level radioactive waste (GTCC waste) inventory; a description of the on-site infrastructure and conditions relevant to transportation of UNF and GTCC waste; an evaluation of the near-site transportation infrastructure and experience relevant to shipping transportation casks containing UNF and GTCC waste, including identification of gaps in information; and, an evaluation of the actions necessary to prepare for and remove UNF and GTCC waste. The primary sources for the inventory of UNF and GTCC waste are the U.S. Department of Energy (DOE) RW-859 used nuclear fuel inventory database, industry sources such as StoreFUEL and SpentFUEL, and government sources such as the U.S. Nuclear Regulatory Commission. The primary sources for information on the conditions of site and near-site transportation infrastructure and experience included observations and information collected during visits to the Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, and Zion sites; information provided by managers at the shutdown sites; Facility Interface Data Sheets compiled for DOE in 2005; Services Planning Documents prepared for DOE in 1993 and 1994; industry publications such as Radwaste Solutions; and Google Earth. State and Regional Group representatives, a Tribal representative, and a Federal Railroad Administration representative participated in six of the shutdown site

Bettis Atomic Power Laboratory

International Nuclear Information System (INIS)

1992-01-01

The Bettis Atomic Power Laboratory (Bettis) is owned by the US Department of Energy (DOE) and has been operated under Government contract by the Westinghouse Electric Corporation since 1949. The Bettis Site in West Mifflin, Pennsylvania conducts research and development work on improved nuclear propulsion plants for US Navy warships and is the headquarters for all of the Laboratory's operations. For many years, environmental monitoring has been performed to demonstrate that the Bettis Site is being operated in accordance with environmental standards. While the annual report describes monitoring practices and results, it does not describe the nature and environmental aspects of work and facilities at the Bettis Site nor give a historical perspective of Bettis' operations. The purpose of this report is to provide this information as well as background information, such as the geologic and hydrologic nature of the Bettis Site, pertinent to understanding the environmental aspects of Bettis operations. Waste management practices are also described

Technology transfer for reduced environmental pollution in the former USSR - the role of Western companies

Energy Technology Data Exchange (ETDEWEB)

Hill, M.R.

1995-12-01

The paper is divided into two main sections, the first presenting information on the volumes of Western exports of power engineering products to the former USSR, and the second describing the technology transfer experiences of a sample of Western power generation, fuels, and power engineering companies. The information relating to those companies was obtained from published information and press reports, and visits for discussions with senior executives during 1994 and 1995. Companies involved in technology transfer and investment activities described in the report are: IVO International Ltd., CRE Group Ltd., Asea Brown Boveri, Siemens Kraftwerkunion, GEC Alsthorn Rolly Royce Industrial Power Group, Babcock Energy, Deutsche Babcock AG, Alsthom Boilers, and GE Corporation. 35 refs., 5 tabs.

Atomic power development in USA

International Nuclear Information System (INIS)

Wiggin, E.

1976-01-01

Many problems concerning the atomic power development in USA are investigated and discussed. (Introduction of fast breeder reactors is not considered in this paper). The first problem is the raising of capital for plant construction. The second problem is the supply of uranium. Estimated amount of yellow cake and its price are presented and compared with estimated demands. It is concluded that 3.5x10 6 tons of yellow coke is sufficient for generating 7x10 8 KW of electric power up to about 2000. The third problem is the enrichment service. Balance of supply and demand is discussed together with the projected extension of existing plants and the construction of new plants. The completion of nuclear fuel cycle is discussed as the fourth problem. According to the author's opinion, technological problems of reprocessing, storing, waste disposal, and the utilization of mixed oxide fuel are not difficult to solve. Definite judgement of NRC and ERDA is strongly required. The last problem discussed in this paper is the public acceptance. The movements of anti-nuclear groups and the opinion of general public are analyzed and the role of AIF in presenting paper informations is discussed. (Aoki, K.)

Engineering grouts - materials and applications with specific examples from Ra asthan Atomic Power Pro ect

International Nuclear Information System (INIS)

Singha Roy, P.K.; Sachchidanand; Sukhthankar, K.D.

1978-01-01

Grouting, though not very significant costwise, is an important aspect6 of construction in most of the major projects. According to modern construction technology, grouts have very stringent and diverse uses. The materials and practices generally found in India for grouting, mainly for structural grouts upto the middle of this decade are outlined along with details of specific grouts used in the construction of the twin reactor (440 MWe) of Rajasthan Atomic Power Station, one reactor of which is already operational. Some guidance and tables for selection of grout for a specific use have also been given. (auth.)

Nuclear power station main control room habitability

International Nuclear Information System (INIS)

Paschal, W.B.; Knous, W.S.

1989-01-01

The main control room at a nuclear power station must remain habitable during a variety of plant conditions and postulated events. The control room habitability requirement and the function of the heating, ventilating, air-conditioning, and air treatment system are to control environmental factors, such as temperature, pressure, humidity, radiation, and toxic gas. Habitability requirements provide for the safety of personnel and enable operation of equipment required to function in the main control room. Habitability as an issue has been gaining prominence with the Advisor Committee of Reactor Safeguards and the Nuclear Regulatory Commission since the incident at Three Mile Island. Their concern is the ability of the presently installed habitability systems to control the main control room environment after an accident. This paper discusses main control room HVAC systems; the concern, requirements, and results of NRC surveys and notices; and an approach to control room habitability reviews

Electric Holding Company Areas

Data.gov (United States)

Department of Homeland Security — Holding companies are electric power utilities that have a holding company structure. This vector polygon layer represents the area served by electric power holding...

Climate change and energy - 2004. European carbon factor. Comparison of CO2 emissions of the main European electric utilities

International Nuclear Information System (INIS)

2004-01-01

This joint PWC/Enerpresse brochure publishes the 2003 results of a study about the greenhouse gas (GHG) emissions of the 23 main European electric power producers. The study shows an increase by 5% of the cumulated emissions of power companies with respect to 2002. These 23 companies represent 55% of the emissions of the power/heat sector in Europe (25 countries). The first 10 companies are responsible of 43% of the GHG emissions of this sector in Europe. Among those, 2 show stable emissions while 3 have reduced their emissions. (J.S.)

Climate change and electricity - 2008. European carbon factor. Comparison of CO2 emissions of the main European electric utilities

International Nuclear Information System (INIS)

2008-01-01

This joint PWC/Enerpresse brochure publishes the 2007 results of a study about the greenhouse gas (GHG) emissions of the 22 main European electric power producers. The study shows an increase by 3% of the cumulated emissions of power companies with respect to 2006. These 22 companies represent 59% of the emissions of the power/heat sector in Europe (27 countries). The first 10 companies are responsible of 50% of the GHG emissions of this sector in Europe. Among those, 7 show stable emissions while the others have increased their emissions. (J.S.)

Climate change and electricity - 2006. European carbon factor. Comparison of CO2 emissions of the main European electric utilities

International Nuclear Information System (INIS)

2006-01-01

This joint PWC/Enerpresse brochure publishes the 2005 results of a study about the greenhouse gas (GHG) emissions of the 23 main European electric power producers. The study shows an increase by 1.7% of the cumulated emissions of power companies with respect to 2001. These 23 companies represent 55% of the emissions of the power/heat sector in Europe (25 countries). The first 10 companies are responsible of 45% of the GHG emissions of this sector in Europe. Among those, 7 show stable emissions while 3 have reduced their emissions. (J.S.)

Climate change and electricity - 2003. European carbon factor. Comparison of CO2 emissions of the main European electric utilities

International Nuclear Information System (INIS)

2003-01-01

This joint PWC/Enerpresse brochure publishes the 2002 results of a study about the greenhouse gas (GHG) emissions of the 21 main European electric power producers. The study shows an increase by 0.8% of the cumulated emissions of power companies with respect to 2001. These 21 companies represent 75% of the emissions of the power/heat sector in Europe (25 countries). The first 10 companies are responsible of 60% of the GHG emissions of this sector in Europe. Among those, 7 have increased their emissions while 3 have reduced them. (J.S.)

Demonstration test for reliability of valves for atomic power plants

International Nuclear Information System (INIS)

Hosaka, Shiro

1978-01-01

The demonstration test on the reliability of valves for atomic power plants being carried out by the Nuclear Engineering Test Center is reported. This test series is conducted as six-year project from FY 1976 to FY 1981 at the Isogo Test Center. The demonstration test consists of (1) environmental test, (2) reaction force test, (3) vibration test, (4) stress measurement test, (5) operational characteristic test, (6) flow resistance coefficient measuring test, (7) leakage test and (8) safety valve and relief valve test. These contents are explained about the special requirements for nuclear use, for example, the enviornmental condition after the design base accident of PWRs and BWRs, the environmental test sequence for isolation valves of containment vessels under the emergency condition, the seismic test condition for valves of nuclear use, the various stress measurements under thermal transient conditions, the leak test after 500 cycles between the normal operating conditions for PWRs and BWRs and the start up conditions and so on. As for the testing facilities, the whole flow diagram is shown, in which the environmental test section, the vibration test section, the steam test section, the hot water test section, the safety valve test section and main components are included. The specifications of each test section and main components are presented. (Nakai, Y.)

DEVELOPMENT OF RUSSIAN FEDERATION POWER SELLING COMPANY STRATEGIC MANAGEMENT

Directory of Open Access Journals (Sweden)

S. V. Grishkevich

2011-01-01

Full Text Available Strategic for power selling companies (PSC are buying, selling and investment activities. Buying activities are to be planned, selling activities predicted and both optimized by PSC on the basis of price and consumer number dynamics with due account of other factors. Very important is to develop the market of derivative instruments (derivatives as part of the risk management mechanism at all levels including that of the state, to use up-to-date and ecologically favorable technologies as well as renewable energy sources with due account of ecology improvement measurement costs.

TQC works in newly-built nuclear power plant and main electric power system plannings

International Nuclear Information System (INIS)

Akiyama, Yoshihisa; Kawakatsu, Tadashi; Hashimoto, Yasuo

1985-01-01

In the Kansai Electric Power Co., Inc., TQC has been introduced to solve such major problems in nuclear power generation as the securing of nuclear power reliability, the suppression of rises in the costs, the reduction in long periods of power failure and the promotion in siting of nuclear power plants. It is thus employed as a means of the ''creation of a slim and tough business constitution''. The state of activities in Kansai Electric are described in quality assurance of a newly-built nuclear power plant and in raising the reliability of the main electric power system to distribute the generated nuclear power and further the future prospects are explained. (Mori, K.)

Maintenance experience on reactor recirculation pumps at Tarapur Atomic Power Station

International Nuclear Information System (INIS)

Singh, A.K.

1995-01-01

Reactor recirculation pumps at Tarapur Atomic Power Station (TAPS) are vertical, single stage centrifugal pumps having mechanical shaft seals and are driven by vertical mounted 3.3 kV, 3 phase, 1500 h.p. electric motors. During these years of operation TAPS has gained enough experience and expertise on the maintenance of reactor recirculation pumps which are dealt in this article. Failure of mechanical shaft seals, damage on pump carbon bearings, motor winding insulation failures and motor shaft damage have been the main areas of concern on recirculation pump. A detailed procedure step by step with component sketches has helped in eliminating errors during shaft seal assembly and installation. Pressure breakdown devices in seal assembly were rebuilt. Additional coolant water injection for shaft seal cooling was provided. These measures have helped in extending the reactor recirculation pump seal life. Pump bearing problems were mainly due to failure of anti-rotation pins and dowel pins of bearing assembly. These pins were redesigned and strengthened. Motor stator winding insulation failures were detected. Stator winding replacement program has been taken up on regular basis to avoid winding insulation failure due to aging. 3 refs., 2 tabs., 7 figs

Isolated systems with wind power. Main report

DEFF Research Database (Denmark)

Lundsager, P.; Bindner, Henrik W.; Clausen, Niels-Erik

2001-01-01

The overall objective of this research project is to study the development of methods and guidelines rather than "universal solutions" for the use of wind energy in isolated communities. The main specific objective of the project is to develop and present amore unified and generally applicable...... approach for assessing the technical and economical feasibility of isolated power supply systems with wind energy. As a part of the project the following tasks were carried out: Review of literature, fieldmeasurements in Egypt, development of an inventory of small isolated systems, overview of end...... for Isolated Systems with Wind Power, applicable for international organisations such as donoragencies and development banks....

Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites

Energy Technology Data Exchange (ETDEWEB)

Maheras, Steven J.; Best, Ralph E.; Ross, Steven B.; Buxton, Kenneth A.; England, Jeffery L.; McConnell, Paul E.

2013-09-30

This report fulfills the M2 milestone M2FT-13PN0912022, “Stranded Sites De-Inventorying Report.” In January 2013, the U.S. Department of Energy (DOE) issued the Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste (DOE 2013). Among the elements contained in this strategy is an initial focus on accepting used nuclear fuel from shutdown reactor sites. This focus is consistent with the recommendations of the Blue Ribbon Commission on America’s Nuclear Future, which identified removal of stranded used nuclear fuel at shutdown sites as a priority so that these sites may be completely decommissioned and put to other beneficial uses (BRC 2012). Shutdown sites are defined as those commercial nuclear power reactor sites where the nuclear power reactors have been shut down and the site has been decommissioned or is undergoing decommissioning. In this report, a preliminary evaluation of removing used nuclear fuel from 12 shutdown sites was conducted. The shutdown sites were Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, Zion, Crystal River, Kewaunee, and San Onofre. These sites have no other operating nuclear power reactors at their sites and have also notified the U.S. Nuclear Regulatory Commission that their reactors have permanently ceased power operations and that nuclear fuel has been permanently removed from their reactor vessels. Shutdown reactors at sites having other operating reactors are not included in this evaluation.

DESIGN OF EXPERIMENTS IN TRUCK COMPANY

Directory of Open Access Journals (Sweden)

Bibiana Kaselyova

2015-07-01

Full Text Available Purpose: Design of experiment (DOE represent very powerful tool for process improvement vastly supported by six sigma methodology. This approach is mostly used by large and manufacturing orientated companies. Presented research is focused on use of DOE in truck company, which is medium size and service orientated. Such study has several purposes. Firstly, detailed description of improvement effort based on DOE can be used as a methodological framework for companies similar to researched one. Secondly, it provides example of successfully implemented low cost design of experiment practise. Moreover, performed experiment identifies key factors, which influence the lifetime of truck tyres.Design/methodology: The research in this paper is based on experiment conducted in Slovakian Truck Company. It provides detailed case study of whole improvement effort, together with problem formulation, design creation and analysis, as well as the results interpretation. The company wants to improve lifetime of the truck tyres. Next to fuel consumption, consumption of tyres and their replacement represent according to them, one of most costly processes in company. Improvement effort was made through the use of PDCA cycle. It start with analysis of current state of tyres consumption. The variability of tyres consumption based on years and types was investigated. Then the causes of tyres replacement were identified and screening DOE was conducted. After a screening design, the full factorial design of experiment was used to identify main drivers of tyres deterioration and breakdowns. Based on result of DOE, the corrective action were propose and implement.Findings: Based on performed experiment our research describes process of tyres use and replacement. It defines main reasons for tyre breakdown and identify main drivers which influence truck tyres lifetime. Moreover it formulates corrective action to prolong tyres lifetime.Originality: The study represents full

The development of multimedia communication system for electric power company

Energy Technology Data Exchange (ETDEWEB)

Woo, Hee Gon; Kim, Seong Bok [Korea Electric Power Corp. (KEPCO), Taejon (Korea, Republic of). Research Center

1995-12-31

It is a final report of the research project that is a development of PC-LAN based multimedia desktop conference system, which is research on the essential technologies and application and development of multimedia communication services for electric power company. This report is consisted of -Survey and study of the multimedia related technologies, -Multimedia communication protocols and network configurations, and -Design, developments of pilot model, evaluation, and applications of multimedia conference system. (author). 112 refs., 250 figs.

The development of multimedia communication system for electric power company

Energy Technology Data Exchange (ETDEWEB)

Woo, Hee Gon; Kim, Seong Bok [Korea Electric Power Corp. (KEPCO), Taejon (Korea, Republic of). Research Center

1996-12-31

It is a final report of the research project that is a development of PC-LAN based multimedia desktop conference system, which is research on the essential technologies and application and development of multimedia communication services for electric power company. This report is consisted of -Survey and study of the multimedia related technologies, -Multimedia communication protocols and network configurations, and -Design, developments of pilot model, evaluation, and applications of multimedia conference system. (author). 112 refs., 250 figs.

Taiwan Power Company's power distribution analysis and fuel thermal margin verification methods for pressurized water reactors

International Nuclear Information System (INIS)

Huang, P.H.

1995-01-01

Taiwan Power Company's (TPC's) power distribution analysis and fuel thermal margin verification methods for pressurized water reactors (PWRs) are examined. The TPC and the Institute of Nuclear Energy Research started a joint 5-yr project in 1989 to establish independent capabilities to perform reload design and transient analysis utilizing state-of-the-art computer programs. As part of the effort, these methods were developed to allow TPC to independently perform verifications of the local power density and departure from nucleate boiling design bases, which are required by the reload safety evaluation for the Maanshan PWR plant. The computer codes utilized were extensively validated for the intended applications. Sample calculations were performed for up to six reload cycles of the Maanshan plant, and the results were found to be quite consistent with the vendor's calculational results

The nuclear power generation

International Nuclear Information System (INIS)

Serres, R.

1999-01-01

The French nuclear generating industry is highly competitive. The installations have an average age of fifteen years and are half way through their expected life. Nuclear power accounts for 70% of the profits of the French generating company, EDF. Nuclear generation has a minimal effect on the atmosphere and France has a level of CO 2 emissions, thought to be the main cause of the greenhouse effect, half that of Europe as a whole. The air in France is purer than in neighbouring countries, mainly because 75% of all electrical power is generated in nuclear plants and 15% in hydroelectric stations. The operations and maintenance of French nuclear power plants in the service and distribution companies out of a total of 100 000 employees in all, 90 % of whom are based in mainland France. (authors)

76 FR 77022 - In the Matter of Carolina Power & Light Company, H.B. Robinson Steam Electric Plant, Unit No. 2...

Science.gov (United States)

2011-12-09

... and 72-3] In the Matter of Carolina Power & Light Company, H.B. Robinson Steam Electric Plant, Unit No. 2, H. B. Robinson Steam Electric Plant, Unit 2, Independent Spent Fuel Storage Installation; Order Approving Indirect Transfer of Control of Licenses I. Carolina Power & Light Company (CP&L, the licensee) is...

Table of written agreements on securing safety of nuclear power plants (Saga, Shimane, Fukushima, Ehime, Miyagi, Ibaraki, Fukui and Shizuoka prefectures)

International Nuclear Information System (INIS)

1981-01-01

A table collecting the written agreements concluded between local city, town and village offices, prefectural governments and the local nuclear enterprises on securing nuclear power safety is given, which was prepared by the study committee on local development and finance problems in Japan Atomic Industrial Forum, Inc. The prefectures, with each of which the agreement was concluded are Saga, Shimane, Fukushima, Ehime, Miyagi, Ibaraki, Fukui and Shizuoka. The local nuclear enterprises are Kyushu, Chugoku, Tokyo, Shikoku, Tohoku, Chubu and Kansai Electric Power Companies, Japan Atomic Power Company, Japan Atomic Energy Research Institute, Power Reactor and Nuclear Fuel Development Corporation, etc. The contents of the agreements are as follows: radioactive waste and material control, understanding in advance of plans, environmental radioactivity measurement, presentation of measured results, hazard countermeasures, communication in normal plant operation and others, on the spot inspection, damage compensation, etc. (J.P.N.)

Environmental studies and clearance compliance of Kudankulam Atomic Power Project

International Nuclear Information System (INIS)

Agarwal, S.K.; Singh, Jitendra

2002-01-01

Full text: Nuclear industry has played a leading role in evolving proper and effective environmental management impact from development practices right form inception thus minimizing the environmental impact from developmental activities of man. In the engineering design of nuclear power plant, safety is further enhanced considerably by providing double back-upped engineered safety systems. Besides the engineered safety, the other factors considered for ensuring environmental impact minimization are siting criteria, conservative rad-waste management, effluent treatment, application of stringent environmental protection standards for limiting waste discharges, an elaborate environmental surveillance program and an on site and off site emergency preparedness plan. Recently, nuclear power industry has taken a drive to develop and implement Environmental Management System (EMS) to all its operating stations in line with ISO-14001 standards. For Kudankulam atomic power project, a number of studies specifically for environmental protection are carried out to meet the requirements of Russian Federation, new guidelines of Ministry of environment and Forests (MOEF) and Atomic Energy Regulatory Board (AERB). In the present paper an attempt has been made to present the environmental management plan and clearance compliance status of the project

Results of the radiological survey at the Napp Chemical Company, 199 Main Street, Lodi, New Jersey (LJ076)

International Nuclear Information System (INIS)

Foley, R.D.; Floyd, L.M.; Carrier, R.F.

1989-11-01

Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally 232 Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, the Napp Chemical Company, 199 Main Street, Lodi, New Jersey (LJ076), was conducted during 1987. Results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions were not significantly different from normal background levels in the northern New Jersey area. 4 refs., 8 figs., 3 tabs

Transforming Ontario's Power Generation Company

International Nuclear Information System (INIS)

Manley, J.; Epp, J.; Godsoe, P.C.

2004-01-01

The OPG Review Committee was formed by the Ontario Ministry of Energy to provide recommendations and advice on the future role of Ontario Power Generation Inc. (OPG) in the electricity sector. This report describes the future structure of OPG with reference to the appropriate corporate governance and senior management structure. It also discusses the potential refurbishing of the Pickering A nuclear generating Units 1, 2 and 3. The electricity system in Ontario is becoming increasingly fragile. The province relies heavily on electricity imports and the transmission system is being pushed to near capacity. Three nuclear generating units are out of service. The problems can be attributed to the fact that the electricity sector has been subjected to unpredictable policy changes for more than a decade, and that the largest electricity generator (OPG) has not been well governed. OPG has had frequent senior management change, accountability has been weak, and cost overruns have delayed the return to service of the Pickering nuclear power Unit 4. It was noted that the generating assets owned and operated by OPG are capable of providing more than 70 per cent of Ontario's electricity supply. Decisive action is needed now to avoid a potential supply shortage of about 5,000 to 7,000 megawatts by 2007. In its current state, OPG risks becoming a burden on ratepayers. Forty recommendations were presented, some of which suggest that OPG should become a rate-regulated commercial utility focused on running and maintaining its core generating assets. This would require that the government act as a shareholder, and the company operate like a commercial business. It was also emphasized that the market must be allowed to bring in new players. refs., tabs., figs

Inevitability of atomic energy in India's power programme

International Nuclear Information System (INIS)

Ramanna, R.

1977-01-01

The case for atomic energy as the inevitable answer to the energy problem of India has been emphatically put up and supported with data. Hydroelectric power is costly to develop and moreover its potential is not enough to meet India's growing energy requirements. On the grounds of economics and safety, nuclear power has been shown to be superior to power from coal-based power plants. India's proved reserves of coal are 21 billion tonnes out of which 80% has ash content more than 20% and in order to reach only half of the present per capita energy consumption in Europe, the present output of 90 million tonnes/year of coal will have to be increased by a factor of 10, which in addition raises the problem of its transportation to the plant sites. Secondly, total energy from the available coal is estimated at 160 x 10 12 kwh, while that from known reserves of 52,000 tonnes of uranium is 7.2 x 10 12 kwh if used in thermal reactors and 208 x 10 12 kwh if used in fast reactors. Thorium with its known reserves of 320,000 tonnes would give another 1280 x 10 12 kwh. As for safety and ecology, it has been pointed out that : (1) in U.S., the number of coal miners dying of black cancer is 1000 per 10 12 kwh of electricity generated, whereas the fatality rate of uranium miners due to lung cancer is 20 per 10 12 kwh of electricity generated and (2) safety has been the primary concern in all aspects of nuclear technology - mining, fuel production, reactor operation and radioactive waste processing. It has also been explained how the fear of any terrorist getting possession of plutonium for spreading it into atmosphere or making a nuclear bomb is highly improbable, because at any point throughout the fuel cycle plutonium is under strict security surveillance and it is impossible to make a nuclear device without the back-up of powerful laboratory facilities. Finally, India's three stage atomic power programme is described in brief. (M.G.B.)

Future challenges for the management of power supply companies; Zukuenftige Herausforderungen fuer das Management von EVU

Energy Technology Data Exchange (ETDEWEB)

Bausch, A. [Jena Univ. (Germany). Professur fuer Allgemeine Betriebswirtschaftslehre/Internationales Management; Jacobs Univ., Bremen (Germany). Professur fuer Strategisches Management und Controlling; Werthschulte, S.; Schumacher, T. [Accenture GmbH (Germany); Holst, A. [Jena Univ. (Germany). Professur fuer Allgemeine Betriebswirtschaftslehre/Internationales Management; Fritz, T. [Jacobs Univ., Bremen (Germany). Professur fuer Strategisches Management und Controlling

2007-06-15

Among the challenges on power supply companies seeking profitable growth are strategic corporate development in terms of product and process innovation and the management's and employees' capacity for change. This was the outcome of a survey conducted as part of the ''Value Creator III'' study performed among 130 executives of German, Austrian and Swiss companies operating in the energy sector. Based on a review of companies' past successes and expectations for the future the study presents business models for tomorrow's energy market and classifies companies within a past-and-future portfolio according to their market prospects.

Application of diagnostic system for diesel engines in nuclear power plant

International Nuclear Information System (INIS)

Yoshinaga, Takeshi

2004-01-01

The diagnostic system for diesel engines makes a diagnosis of secular change and abnormal indications of diesel engines (DG) by combination of characteristic analysis of engine, lubricating oil, fuel oil, and cooling water. The principles of diagnostic system for DG, results of confirmation of the efficiency and the maintenance plan for DG in the Japan Atomic Power Company are described. DG in the company is classified to a safety device in order to supply the power source to the Emergency Core Cooling System etc., when the power source in the plant is lost, for example, at lightning struck. Characteristics of DG, outline of the diagnostic system for DG, diagnostic technologies such as engine signature analysis, chemical analysis of samples, temperature measurement, degradation mode of DG, and training in the company are stated. (S.Y.)

The social and economic impact of nuclear power in the year 2000 and beyond

International Nuclear Information System (INIS)

Kritsky, W.G.; Loiselle, V.

1998-01-01

Worldwide, there are 437 nuclear plants in operation throughout 31 nations based upon data provided by the IAEA Power Reactor Information System. These plants represent 17% of world electrical production and 2300 Billion kwhrs. In the United States, production exceeded 600 billion kwhrs and 22% of total electrical production in 1995. Between 1996 and 1997, seven new plants were brought on-line, of which only one was located in the US. Therefore, the United States has definitely established a gradual decline of nuclear electric production with decisions to shut down Big Rock Point and Maine Yankee and more recently, the Zion Nuclear Station. This brings to 13 the total number of power plans within the pipeline for decommissioning, or more than 10% of the commissioned installations. With no plans for new plant construction in the offing, nuclear power's share of electrical production will shrink. This decline is expected to make a significant impact upon the social and economic structure before new needs or a new equilibrium is achieved. Specifically, the authors present their view of what the decline will do to these areas of social and commercial concern to the year 2000 and beyond

A short history of the CANDU nuclear power system

Energy Technology Data Exchange (ETDEWEB)

Brooks, G L

1993-04-01

This paper provides a short historical summary of the evolution of the CANDU nuclear power system with emphasis on the roles played by Ontario Hydro and private sector companies in Ontario in collaboration with Atomic Energy of Canada Limited (AECL). (author). 1 fig., 61 refs.

A short history of the CANDU nuclear power system

International Nuclear Information System (INIS)

Brooks, G.L.

1993-04-01

This paper provides a short historical summary of the evolution of the CANDU nuclear power system with emphasis on the roles played by Ontario Hydro and private sector companies in Ontario in collaboration with Atomic Energy of Canada Limited (AECL). (author). 1 fig., 61 refs

Examining the cost efficiency of Chinese hydroelectric companies using a finite mixture model

International Nuclear Information System (INIS)

Barros, Carlos Pestana; Chen, Zhongfei; Managi, Shunsuke; Antunes, Olinda Sequeira

2013-01-01

This paper evaluates the operational activities of Chinese hydroelectric power companies over the period 2000–2010 using a finite mixture model that controls for unobserved heterogeneity. In so doing, a stochastic frontier latent class model, which allows for the existence of different technologies, is adopted to estimate cost frontiers. This procedure not only enables us to identify different groups among the hydro-power companies analysed, but also permits the analysis of their cost efficiency. The main result is that three groups are identified in the sample, each equipped with different technologies, suggesting that distinct business strategies need to be adapted to the characteristics of China's hydro-power companies. Some managerial implications are developed. - Highlights: ► This paper evaluates the operational activities of Chinese electricity hydric companies. ► This study uses data from 2000 to 2010 using a finite mixture model. ► The model procedure identifies different groups of Chinese hydric companies analysed. ► Three groups are identified in the sample, each equipped with completely different “technologies”. ► This suggests that distinct business strategies need to be adapted to the characteristics of the hydric companies

Exchange of current BPA surplus power for future power from certain companies' share of WNP-3 to settle a dispute over construction delay. Record of decision. Volume II. Exhibits

International Nuclear Information System (INIS)

1985-01-01

This exchange is between BPA and Portland General Electric Company, Puget Sound Power and Light Company, and the Washington Water Power Company. Pacific Power and Light Company (Pacific) is not initially a party to the exchange. Pacific may at any time prior to January 1, 1994 elect on at least 12 months notice to enter the exchange provided that if BPA determines to resume full plant construction Pacific must elect or forego the option within 6 months after construction is resumed. If the plant is terminated at a time when the option has not been exercised, the option may not thereafter be exercised. If Pacific elects to make the exchange effective and the plant is later terminated prior to the effective data of the exchange, the exchange will become effective on the specified data, unless, prior to such data. Pacific notifies BPA that is rescinds such prior election

Poison pills: A defensive measure against a hostile takeover or a demonstration of power of the target company

Directory of Open Access Journals (Sweden)

Jovanović-Zattila Milena

2014-01-01

Full Text Available The balance of power is particularly at stake in hostile takeovers, which makes the issue of establishing the balance of power one of the most controversial issues in the contemporary company law. In the circumstances of direct market competition and the need to have a dominant market position, companies are necessarily forced to constantly upgrade and advance their offensive and defensive methods, techniques and strategies. In order to prevent a hostile takeover, the target company may resort to an array of defence mechanisms, the most prominent of which are 'poison pills'. In spite of being perceived as the most powerful tool for obstructing hostile takeovers (and commonly designated as the 'Holy Grail' among the defensive mechanisms, there are many pros and cons underlying their application. One of the positive effects of using the poison pills is that the fear of takeovers makes the target company management more disciplined and efficient in business operations. The negative consequences are reflected in the relationship between the company board of directors and the shareholders. The target company management makes a unilateral decision on using a poison pill and this decision does not have to be approved by the shareholders in the General Meeting; however, this is highly inconsistent with the basic principles of corporate governance. The asymmetry of information, where the management (an agent has disproportionately more relevant information at its disposal than the shareholders (principals, generates a conflict between the management and the shareholders. In company law, this agency problem is generally known as the principal-agent problem, which is most prominent in a takeover. Poison pills are often associated with the discrimination of the target company shareholders, but not necessarily. The controversial nature of this defensive measure which can be applied by the target company has given rise to numerous debates on the need to

Measuring efficiency and productivity change in power electric generation management companies by using data envelopment analysis: A case study

International Nuclear Information System (INIS)

Fallahi, Alireza; Ebrahimi, Reza; Ghaderi, S.F.

2011-01-01

This paper provides an empirical analysis of the determinants of energy efficiency in 32 power electric generation management companies over the period 2005–2009. The study uses non-parametric Data Envelopment Analysis (DEA) to estimate the relative technical efficiency and productivity change of these companies. In order to verify the stability of our DEA model and the importance of each input variable, a stability test is also conducted. The results of the study indicate that average technical efficiency of companies decreased during the study period. Nearly half of the companies (14) are below this average level of 88.7% for five years. Moreover, it is shown that the low increase of productivity changes is more related to low efficiency rather than technology changes. -- Highlights: ► DEA was applied on the 32 power electric generation management companies. ► A stability test is applied to verify the stability of DEA model. ► Average technical efficiency of companies decreased during the study period. ► The low increase of productivity changes is more related to low efficiency changes.

Interaction of antiprotons with Rb atoms and a comparison of antiproton stopping powers of the atoms H, Li, Na, K, and Rb

DEFF Research Database (Denmark)

Lühr, Armin Christian; Fischer, Nicolas; Saenz, Alejandro

2009-01-01

Ionization and excitation cross sections as well as electron-energy spectra and stopping powers of the alkali metal atoms Li, Na, K, and Rb colliding with antiprotons were calculated using a time-dependent channel-coupling approach. An impact-energy range from 0.25 to 4000 keV was considered....... The target atoms are treated as effective one-electron systems using a model potential. The results are compared with calculated cross sections for antiproton-hydrogen atom collisions....

The effect of electric transmission constraints on how power generation companies bid in the Colombian electrical power market

Directory of Open Access Journals (Sweden)

Luis Eduardo Gallego Vega

2010-05-01

Full Text Available This paper presents the results of research about the effect of transmission constraints on both expected electrical energy to be dispatched and power generation companies’ bidding strategies in the Colombian electrical power market. The proposed model simulates the national transmission grid and economic dispatch by means of optimal power flows. The proposed methodology allows structural problems in the power market to be analyzed due to the exclusive effect of trans- mission constraints and the mixed effect of bidding strategies and transmission networks. A new set of variables is proposed for quantifying the impact of each generation company on system operating costs and the change in expected dispatched energy. A correlation analysis of these new variables is presented, revealing some interesting linearities in some generation companies’ bidding patterns.

The Northern States Power Company welding manual advisor

International Nuclear Information System (INIS)

Lu, Yi; Wood, R.M.

1993-01-01

The Welding Manual Advisor (WMA) is an object oriented expert system designed to assist Northern States Power (NSP) personnel in implementing the company's Welding Manual. The expert system captures the knowledge of welding experts, addresses important issues in welding activities and automates the use of the Welding Manual. It is estimated that use of the WMA will save $81,000 over the next six years at NSP, because of the reduction of labor and errors in the use of the Welding Manual, and facilitation of training of NSP personnel. The important features of the WMA include the accuracy and consistency in determining welding procedure and requirements, update capability, user friendly interface, on-line help function, back-up capability, and well-documented manuals

Application study of the project management on the nuclear power projects in China Institute of Atomic Energy

International Nuclear Information System (INIS)

Ji Cunxing

2012-01-01

The article introduced the actions of foreign and domestic nuclear power technical services in China Institute of Atomic Energy, the project management theory is applied to the organization, implementation and control of the nuclear power projects. It is analyzed the quality, schedule , investment etc of nuclear power projects, the improving measures and suggestions are bring forward on the project management organization, quality assurance, reduce cost etc. It will raise its nuclear power project management level in China Institute of Atomic Energy. (author)

Atoms in Slovakia

International Nuclear Information System (INIS)

Danis, D.; Feik, K.; Florek, M.; Kmosena, J.; Chrapan, J.; Morovic, M.; Slugen, V.; Seliga, M.; Valovic, J.

2006-01-01

In this book the history of development of using of nuclear energy in the Slovak Republic as well as in the Czechoslovakia (before 1993 year) is presented. The aim of the book is to preserve the memory of the period when the creation and development of nuclear physics, technology, nuclear medicine, radioecology and energetics in Slovakia occurred - as witnessed by people who experienced this period and to adapt it to future generations. The Editorial board of the SNUS collected the views of 60 contributors and distinguished workers - Slovakian experts in nuclear science, education and technology. Calling upon a wide spectrum of experts ensured an objective historical description of the period. A huge amount of subjective views on recent decades were collected and supported by a wealth of photographic documentation. This created a synthesised reflection on the history of the 'atoms' in Slovakia. The book contains 15 tables, 192 black and white and 119 colour pictures from around the world and from places involved in the compilation of the study and with the study of atomic science in Slovakia. The main chapters are as follows: Atoms in the world, Atoms in Slovakia, Atoms in the educational system, Atoms in health services (Radiology, Nuclear medicine, Radiation protection, the Cyclotron centre of the Slovak Republic), Radioecology, Other applications of irradiation, Nuclear energetics (Electric energy in the second half of the 20 th century, NPP Bohunice, NPP Mochovce, the back-end of Nuclear energetics, Big names in Nuclear energetics in Slovakia), Chronology and an Appendix entitled 'Slovak companies in nuclear energetics'

Situation of nuclear power generation in Europe

International Nuclear Information System (INIS)

Toukai, Kunihiro

2003-01-01

Nuclear power plants began to be built in Europe in the latter half of 1960. 146 plants are operating and generating about 33% of total power in 2002. France is top of Europe and operating 59 plants, which generate about 75% of power generation in the country. Germany is second and 30%. England is third and 30%. However, Germany decided not to build new atomic power plant in 2000. Movement of non-nuclear power generation is decreasing in Belgium and Switzerland. The liberalization of power generation decreased the wholesale price and BE Company in England was financial difficulties. New nuclear power generation is planning in Finland and France. (S.Y.)

77 FR 42715 - Lockhart Power Company, Inc.; Notice of Application Ready for Environmental Analysis and...

Science.gov (United States)

2012-07-20

...(r). h. Applicant Contact: Bryan D. Stone, Chief Operating Officer, Lockhart Power Company, Inc., 420... paper-filed. To paper-file, mail an original and seven copies to: Kimberly D. Bose, Secretary, Federal...

A research company in transition

International Nuclear Information System (INIS)

Hatcher, S.R.

1989-01-01

The role of Atomic Energy of Canada Ltd's Research Company is to perform the research, development, demonstration and marketing needed to apply nuclear sciences and their associated technologies for the maximum benefit of Canada. This article by its president, Dr S R Hatcher, describes the Research Company as it attempts to fulfil its mission in very altered circumstances. (Author)

Internal structure of reactor building for Madras Atomic Power Project

International Nuclear Information System (INIS)

Pandit, D.P.

1975-01-01

The structural configuration and analysis of structural elements of the internal structure of reactor building for the Madras Atomic Power Project has been presented. Two methods of analysis of the internal structure, viz. Equivalent Plane Frame and Finite Element Method, are explained and compared with the use of bending moments obtained. (author)

The recent activities of nuclear power globalization. Our provision against global warming by global deployment of our own technologies as integrated nuclear power plant supply company'

International Nuclear Information System (INIS)

Yamauchi, Kiyoshi; Suzuki, Shigemitsu

2008-01-01

Mitsubishi Heavy Industries, Ltd. (MHI) is striving to expand and spread nuclear power plants as an 'Integrated Nuclear Power Plant Supply Company' based on its engineering, manufacturing, and technological support capabilities. The company also has ample experience in the export of major components. MHI is accelerating its global deployment through the market introduction of large-sized strategic reactor US-APWR, the joint development of a mid-sized strategic reactor ATMEA1 with AREVA, and a small strategic reactor PBMR. The company also plans to internationally deploy technologies for the nuclear fuel cycle. We present here the leading-edge trends in the global deployment of these nuclear businesses, all of which help to solve the energy and environmental issues in the world. (author)

The main players; Les acteurs d'influence

Energy Technology Data Exchange (ETDEWEB)

Delbecq, D.

2012-02-15

About 30 French main players in the field of energy (political parties, administrations, companies, non-governmental organizations and think-tanks) have been reported and dispatched on a chart according to their opinions following 2 axis: pro- versus anti-nuclear energy and pro- versus anti-wind power. The energy sector in France is dominated by 4 companies: EDF, GDF-Suez, Areva and Total, all are strongly pro-nuclear. All the political parties except EELV (Europe-Ecology-Les-Verts) are favourable to nuclear energy. Most non-governmental organizations are favourable to renewable energies, but the FED (Federation Environnement Durable) gathers local associations fighting the installations of wind turbines. (A.C)

Comparative Analysis of the Main Business Intelligence Solutions

OpenAIRE

Alexandra RUSANEANU

2013-01-01

Nowadays, Business Intelligence solutions are the main tools for analyzing and monitoring the company’s performance at any organizational level. This paper presents a comparative analysis of the most powerful Business Intelligence solutions using a set of technical features such as infrastructure of the platform, development facilities, complex analysis tools, interactive dashboards and scorecards, mobile integration and complex implementation of performance management methodologies.

Two Approaches to Reactor Decommissioning: 10 CFR Part 50 License Termination and License Amendment, Lessons Learned from the Regulatory Perspective

International Nuclear Information System (INIS)

Watson, B.A.; Buckley, J.T.; Craig, C.M.

2006-01-01

Trojan Nuclear Plant (Trojan) and Maine Yankee Nuclear Plant (Maine Yankee) were the first two power reactors to complete decommissioning under the U. S. Nuclear Regulatory Commission's (NRC's) License Termination Rule (LTR), 10 CFR Part 20, Subpart E. The respective owners' decisions to decommission the sites resulted in different approaches to both the physical aspects of the decommissioning, and the approach for obtaining approval for completing the decommissioning in accordance with regulations. Being in different States, the two single-unit pressurized water reactor sites had different State requirements and levels of public interest that impacted the decommissioning approaches. This resulted in significant differences in decommissioning planning, conduct of decommissioning operations, volumes of low- level radioactive waste disposed, and the final status survey (FSS) program. While both licensees have Independent Spent Fuel Storage Installations (ISFSIs), Trojan obtained a separate license for the ISFSI in accordance with the requirements of 10 CFR Part 72 and terminated their 10 CFR Part 50 license. Maine Yankee elected to obtain a general license under 10 CFR Part 50 for the ISFSI and reduce the physical site footprint to the ISFSI through a series of license amendments. While the NRC regulations are flexible and allow different approaches to ISFSI licensing there are separate licensing requirements that must be addressed. In 10 CFR 50.82, the NRC mandates public participation in the decommissioning process. For Maine Yankee, public input resulted in the licensee entering into an agreement with a concerned citizen group and resulted in State legislation that significantly lowered the dose limit below the NRC radiological criteria of 25 mrem (0.25 mSv) per year (yr) in 10 CFR 20.1402 for unrestricted use. The lowering of the radiological criteria resulted in a significant dose modeling effort using site-specific Derived Concentrations Guideline Levels (DCGLs

Cost structure analysis of commercial nuclear power plants in Japan based on corporate financial statements of electric utility companies

International Nuclear Information System (INIS)

Kunitake, Norifumi; Nagano, Koji; Suzuki, Tatsujiro

1998-01-01

In this paper, we analyze past and current cost structure of commercial nuclear power plants in Japan based on annual corporate financial statements published by the Japanese electric utility companies, instead of employing the conventional methodology of evaluating the generation cost for a newly constructed model plant. The result of our study on existing commercial nuclear plants reveals the increasing significance of O and M and fuel cycle costs in total generation cost. Thus, it is suggested that electric power companies should take more efforts to reduce these costs in order to maintain the competitiveness of nuclear power in Japan. (author)

Cost efficiency of Japanese steam power generation companies: A Bayesian comparison of random and fixed frontier models

Energy Technology Data Exchange (ETDEWEB)

Assaf, A. George [Isenberg School of Management, University of Massachusetts-Amherst, 90 Campus Center Way, Amherst 01002 (United States); Barros, Carlos Pestana [Instituto Superior de Economia e Gestao, Technical University of Lisbon, Rua Miguel Lupi, 20, 1249-078 Lisbon (Portugal); Managi, Shunsuke [Graduate School of Environmental Studies, Tohoku University, 6-6-20 Aramaki-Aza Aoba, Aoba-Ku, Sendai 980-8579 (Japan)

2011-04-15

This study analyses and compares the cost efficiency of Japanese steam power generation companies using the fixed and random Bayesian frontier models. We show that it is essential to account for heterogeneity in modelling the performance of energy companies. Results from the model estimation also indicate that restricting CO{sub 2} emissions can lead to a decrease in total cost. The study finally discusses the efficiency variations between the energy companies under analysis, and elaborates on the managerial and policy implications of the results. (author)

Present status and perspective of Japanese atomic energy industry

International Nuclear Information System (INIS)

Miura, Kenzo

1990-01-01

Already 35 years are going to elapse since atomic energy industry was founded in Japan, and the positive development has been carried out in the nuclear power generation mainly with light water reactors as the base energy, as the result, now both the result of electric power generation and the technology have reached the highest level in the world. These are due to the accumulation of efforts, the preponderant assignment of able men and the positive investment for the research and development of the atomic energy industry. However, since 1985, the slowdown of power reactor development, the practical use of new type power reactors such as fast breeder reactors and the establishment of nuclear fuel cycle such as uranium enrichment and fuel reprocessing have been the new situation to be dealt with. In order to properly and flexibly cope with such change of situation, the healthy development of the atomic energy industry so as to secure the market on a certain scale and develop the business with responsibility is indispensable. The outlay of electric power industry related to atomic energy, the development of atomic energy market and the sales of mining and manufacturing industries, the trend of research and development and personnel, and the perspective and subjects of hereafter are reported. (K.I.)

Investigation Study on Gamma Ray Imaging Technology for Nuclear Power Plant Decommissioning

Energy Technology Data Exchange (ETDEWEB)

Lee, Sang Guk; Jeong, Woo Tae [Machinery and Materials Laboratory, Korea Hydro and Nuclear Power Co., Daejeon (Korea, Republic of)

2014-10-15

The gamma ray imaging system provides an estimated dose-rate of the source at 30 cm above. The gamma detector is a terbium activated glass scintillator. The system is capable of producing a color two dimensional image of a radiation field superimposed on a black and white visual image. The system used in US power plants consists of a portable sensor head that contains both gamma ray and visual imaging systems and a portable control computer. The gamma ray imaging system has been successfully used as an ALARA tool for identifying source terms and determining the adequacy of existing shielding. Because the control system can be positioned away from the camera, the radiation exposure to personnel can be reduced without extensive shielding requirements. The gamma ray imaging system has been used to date in the decommissioning of Maine Yankee, Big Rock point,Trojan, San Onofre1, and Millstone 1. The equipment has also been used at normal refueling outages at a number of commercial nuclear power plants and at several Department of Energy Decommissioning sites. This paper is intended to review the applicability of gamma ray imaging system as decommissioning tool. In order to review the actual applicability, we are going to introduce applications for US power plants.

Department of Energy interest and involvement in nuclear plant license renewal activities

International Nuclear Information System (INIS)

Bustard, L.D.; Harrison, D.L.

1991-01-01

Recognizing the importance of nuclear license renewal to the nation's energy strategy, the Department of Energy (DOE) initiated a plant lifetime improvement program during 1985 to determine the feasibility of the license renewal option for US nuclear plants. Initial activities of the DOE program focused on determining whether there were technical and economic obstacles that might preclude or limit the successful implementation of the license renewal option. To make this determination, DOE cosponsored with the Electric Power Research Institute (EPRI) pilot-plant efforts by Virginia Electric Power and Northern States Power. Both pilot-plant efforts concluded that life extension is technically and economically feasible. In parallel with the pilot-plant activities, DOE performed national economic studies that demonstrated the economic desirability of life extension. Having demonstrated the feasibility of life extension, DOE, in conjunction with EPRI, selected two lead plants to demonstrate the license renewal process. These lead plants are Yankee Atomic's Yankee Rowe facility and Northern States Power's Monticello facility. DOE also initiated activities to develop the technical and regulatory bases to support the license renewal process in the United States. DOE has recently identified nuclear plant license renewal to be an important element of its National Energy Strategy. This paper summarizes the significant results, conclusions, and ongoing activities of the DOE effort. 18 refs

20 kHz main inverter unit. [for space station power supplies

Science.gov (United States)

Hussey, S.

1989-01-01

A proof-of-concept main inverter unit has demonstrated the operation of a pulse-width-modulated parallel resonant power stage topology as a 20-kHz ac power source driver, showing simple output regulation, parallel operation, power sharing and short-circuit operation. The use of a two-stage dc input filter controls the electromagnetic compatibility (EMC) characteristics of the dc power bus, and the use of an ac harmonic trap controls the EMC characteristics of the 20-kHz ac power bus.

77 FR 38796 - Georgia Power Company; Bartletts Ferry Hydroelectric Project; Notice of Revised Restricted...

Science.gov (United States)

2012-06-29

... Alabama] Georgia Power Company; Bartletts Ferry Hydroelectric Project; Notice of Revised Restricted... by issuance of a new license for the Bartletts Ferry Hydroelectric Project No. 485. The programmatic... Hydroelectric Project. On June 14, 2012, the Kialegee Tribal Town requested a revision to the restricted service...

Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites

Energy Technology Data Exchange (ETDEWEB)

Maheras, Steven J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Best, Ralph E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Ross, Steven B. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Buxton, Kenneth A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); England, Jeffery L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McConnell, Paul E. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Massaro, Lawrence M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Jensen, Philip J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2015-09-30

A preliminary evaluation of removing spent nuclear fuel (SNF) from 13 shutdown nuclear power reactor sites was conducted. At these shutdown sites the nuclear power reactors have been permanently shut down and the sites have been decommissioned or are undergoing decommissioning. The shutdown sites were Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, Zion, Crystal River, Kewaunee, San Onofre, and Vermont Yankee. The evaluation was divided into four components: (1) characterization of the SNF and greater-than-Class C low-level radioactive waste (GTCC waste) inventory, (2) a description of the on-site infrastructure and conditions relevant to transportation of SNF and GTCC waste, (3) an evaluation of the near-site transportation infrastructure and experience relevant to shipping transportation casks containing SNF and GTCC waste, including identification of gaps in information, and (4) an evaluation of the actions necessary to prepare for and remove SNF and GTCC waste. Every site was found to have at least one off-site transportation mode option for removing its SNF and GTCC waste; some have multiple options. Experience removing large components during reactor decommissioning provided an important source of information used to identify the transportation mode options for the sites. Especially important in conducting the evaluation were site visits, through which information was obtained that would not have been available otherwise. Extensive photographs taken during the site visits proved to be particularly useful in documenting the current conditions at or near the sites. It is expected that additional site visits will be conducted to add to the information presented in the evaluation.

Monitoring method of an atomic power plant

International Nuclear Information System (INIS)

Koba, Akitoshi; Goto, Seiichiro; Ohashi, Hideaki.

1975-01-01

Object: To make a monitoring vehicle, which is loaded with various detecting elements, go round along the monorail disposed so as to surround various devices to thereby early discover various abnormal conditions. Structure: The monitoring vehicle is travelled on the monorail disposed so as to surround the periphery of various devices in an atomic power plant so that detection signals from an ITV camera, temperature and radioactive rays and sound detecting elements, and the like are received through a slide contact between the wheel and transmitting and receiving line disposed in the wheel groove to transmit the signals to a central control panel. (Yoshihara, H.)

The problem of ensuring the seismic stability of atomic electric power plant equipment and ways of solving it

International Nuclear Information System (INIS)

Kaznovskii; Filippov, G.A.

1983-01-01

By seismic stability the authors mean the ability of the equipment and buildings to retain certain properties when subjected to seismic loads: leakproofness, strength, the absence of any residual changes of shape, which interfere with normal operation, ability to be repaired, nuclear and radiation safety. The latter requirement is the main thing which differentiates atomic electric power plants from other constructions, including other power-generation plants. Whereas, for example, an accident in the event of an earthquake in a thermal electric power plant can be regarded as a local accident, and the measures to ensure seismic stability are determined by economic factors and safety requirements for the operating staff, to ensure the seismic stability of an AES it is essential to take account in the first instance of the possibility of dangerous radiation effects both in the AES and in the vast area around it

Orcas Power and Light Company [fourth quarterly] technical progress report, July--September 1992

Energy Technology Data Exchange (ETDEWEB)

1992-12-31

After a year of operating the G-Van, OPALCO concluded that the company transportation needs were not being met by the G-Van. The previous quarterly report mentioned battery problems with the Solectria (No. 51). This problem is one of reduced range and power and has been determined to be caused by one or more individual monoblock failures. The local Solectria representative and Solectria headquarters personnel have been aware of this unsatisfactory condition and are continuing their attempt to solve it. The Solectria and G-Van continue to be used intermittently by company personnel for errands and engineering trips. Generally, the smaller, compact size of the Solectria make it the most preferred by company drivers. Clearly the G-Van is not selected for use because of its size and weight. It is important to note that the driver dissatisfaction is not related to the fact that it is an electric van, but more its lack of maneuverability.

Orcas Power and Light Company [fourth quarterly] technical progress report, July--September 1992

Energy Technology Data Exchange (ETDEWEB)

1992-01-01

After a year of operating the G-Van, OPALCO concluded that the company transportation needs were not being met by the G-Van. The previous quarterly report mentioned battery problems with the Solectria (No. 51). This problem is one of reduced range and power and has been determined to be caused by one or more individual monoblock failures. The local Solectria representative and Solectria headquarters personnel have been aware of this unsatisfactory condition and are continuing their attempt to solve it. The Solectria and G-Van continue to be used intermittently by company personnel for errands and engineering trips. Generally, the smaller, compact size of the Solectria make it the most preferred by company drivers. Clearly the G-Van is not selected for use because of its size and weight. It is important to note that the driver dissatisfaction is not related to the fact that it is an electric van, but more its lack of maneuverability.

77 FR 38796 - Alabama Power Company; Holt Hydroelectric Project; Notice of Revised Restricted Service List for...

Science.gov (United States)

2012-06-29

... Power Company; Holt Hydroelectric Project; Notice of Revised Restricted Service List for a Programmatic... Hydroelectric Project No. 2203. The programmatic agreement, when executed by the Commission, the Alabama SHPO...

Centralized vs. decentralized thermal IR inspection policy: experience from a major Brazilian electric power company

Science.gov (United States)

dos Santos, Laerte; da Costa Bortoni, Edson; Barbosa, Luiz C.; Araujo, Reyler A.

2005-03-01

Furnas Centrais Elétricas S.A is one of the greatest companies of the Brazilian electric power sector and a pioneer in using infrared thermography. In the early 70s, the maintenance policy used was a centralized approach, with only one inspection team to cover all the company"s facilities. In the early 90s, FURNAS decided to decentralize the thermography inspections creating several inspection teams. This new maintenance policy presented several advantages when compared to the previous one. However the credibility of the results obtained with the thermal inspection was frequently being questioned, in part due to the lack of a detailed planning to carry out the transition from the centralized inspection to the decentralized one. In some areas of the company it was suggested the inactivation of the thermography. This paper presents the experience of FURNAS with these different maintenance policies and details the procedures which have been taken that nowadays the infrared thermal inspection has become one of the most important techniques of predictive maintenance in the company.

75 FR 82414 - Carolina Power & Light Company; H. B. Robinson Steam Electric Plant, Unit No. 2; Exemption

Science.gov (United States)

2010-12-30

... NUCLEAR REGULATORY COMMISSION [Docket No. 50-261; NRC-2010-0062] Carolina Power & Light Company; H. B. Robinson Steam Electric Plant, Unit No. 2; Exemption 1.0 Background Carolina Power & Light... authorizes operation of the H.B. Robinson Steam Electric Plant, Unit 2 (HBRSEP). The license provides, among...

75 FR 11579 - Carolina Power & Light Company H. B. Robinson Steam Electric Plant, Unit No. 2; Exemption

Science.gov (United States)

2010-03-11

... NUCLEAR REGULATORY COMMISSION [Docket No. 50-261; NRC-2010-0062] Carolina Power & Light Company H. B. Robinson Steam Electric Plant, Unit No. 2; Exemption 1.0 Background Carolina Power & Light... of the H. B. Robinson Steam Electric Plant, Unit 2 (HBRSEP). The license provides, among other things...

Biofouling in the condenser cooling conduits of Madras Atomic Power Station

International Nuclear Information System (INIS)

Thiyagarajan, V.; Subramoniam, T.; Venugopalan, V.P.; Nair, K.V.K.

1995-01-01

The present paper deals with various aspects fouling organisms collected from the condenser cooling water circuit of Madras Atomic Power Station (MAPS II) their biomass, thickness, composition and length frequency distribution of one of the major species namely, B. reticulatus. (author). 8 refs., 1 tab., 2 figs

76 FR 28024 - Swan Falls Hydroelectric Project, Idaho Power Company; Notice of Teleconference

Science.gov (United States)

2011-05-13

... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 503-048-ID] Swan Falls Hydroelectric Project, Idaho Power Company; Notice of Teleconference a. Date and Time of Meeting: Tuesday, May 24, 2011 at 10 a.m. (Mountain Time). b. Place: By copy of this notice we are inviting all interested parties to attend a teleconference from...

Atomic energy indemnification system in Japan

International Nuclear Information System (INIS)

Hoshino, Eiichi

1980-01-01

The Japanese legislation on the indemnification by atomic energy enterprisers for atomic energy damages, published in 1961 and enforced in 1962, includes the law concerning indemnification for atomic energy damages and the law concerning atomic energy damage indemnification contracts (hereafter referred to as ''the law concerning indemnification contracts''). While the Japanese laws are same as the foreign legislation in the provisions of the responsibility of atomic energy damages without the error of atomic energy enterprisers, exemption reasons are more important in this respect. When damages are due to exceptionally grave natural disasters or social disturbances, atomic energy enterprisers are exempted from the responsibility. Indemnification amounts are determined, but the Japanese laws do not limit then, different from the foreign regulations. The periods for demanding indemnification are not defined particularly in the law concerning indemnification contracts, and the general basic rules of the civil law are applied. As a result, the demand right terminates in 3 years after the injured persons find damage and offenders, and in 20 years since the unlawful act (Article 724, Civil law). The indemnification liability for atomic energy damages is focused on atomic energy enterprisers concerned in the same way as the foreign laws. The measures for assuring the execution of indemnification responsibility consist in principle of the firm conbination of the liability insurance contracts with private insurance companies and the indemnification contracts for atomic energy damages with the state. The damages of employes suffered in works are excluded from indemnification, which has been the main issue of discussion since the enactment of atomic energy laws. (Okada, K.)

Metal cluster compounds - chemistry and importance; clusters containing isolated main group element atoms, large metal cluster compounds, cluster fluxionality

International Nuclear Information System (INIS)

Walther, B.

1988-01-01

This part of the review on metal cluster compounds deals with clusters containing isolated main group element atoms, with high nuclearity clusters and metal cluster fluxionality. It will be obvious that main group element atoms strongly influence the geometry, stability and reactivity of the clusters. High nuclearity clusters are of interest in there own due to the diversity of the structures adopted, but their intermediate position between molecules and the metallic state makes them a fascinating research object too. These both sites of the metal cluster chemistry as well as the frequently observed ligand and core fluxionality are related to the cluster metal and surface analogy. (author)

Modification of reactor installation in the Genkai nuclear power plant No. 1 of Kyushu Electric Power Company, Inc

International Nuclear Information System (INIS)

1979-01-01

The Nuclear Safety Commission recognized the adequacy concerning the inquiry which was offered from the Minister of International Trade and Industry on July 25, 1979, following the safety evaluation in the Ministry of International Trade and Industry, and decided to submit a report to the Minister of International Trade and Industry on July 26, 1979, about the modification of reactor installation in the Genkai nuclear power plant No. 1 of the Kyushu Electric Power Company, Inc. This is concerned to the application which was made from the president of the Kyushu Electric Power Company, Inc., to the Minister of International Trade and Industry on July 24, 1979. The content of the modification is to add a control circuit which is actuated by the signal of abnormal low pressure in a reactor to the circuit of actuating the emergency core cooling system of the plant. The influences on the safety protection system by the addition of the circuit transmitting safety injection signal and by the additions of an interlock circuit preventing the misoperation of pressurizer spray and of a block circuit of safety injection signal in case of the abnormal low pressure in a reactor were evaluated. The effects on the function and characteristics of the emergency core cooling system due to the addition of the control circuit were investigated, and it was recognized by the analysis that there is no effect in the pipe ruptures of both small and large scales. (Nakai, Y.)

Atomic power plant and its operation method

International Nuclear Information System (INIS)

Yamamoto, Fumiaki; Higashio, Satoru.

1986-01-01

Purpose: To improve operation performance by partially restraining local over power in the axial power distribution of the reactor core by properly controlling the reactor pressure and furthermore by smoothly and properly performing reactor start-up operation in a short time while maintaining fuel integrity. Method: With the reactor pressure input to the pressure controller from the pressure detector, the valve opening of the main steam adjusting valve is adjusted so that the pressure will decrease when the reactor is started up. Also the adjusting valve is controlled so that the pressure will be lower than the set value of rated pressure, thus changing the axial distribution of void. In the meantime, with the stored state of xenon stored along with the increase of reactor power taken into consideration, the reactor pressure is increased as high as the rated value until the reactor power reaches to the rated power, thereby alleviating the local increase of reactor power without changing the whole reactor power and also enabling substantial reduction of reactor start-up time while maintaining reactor integrity. (Horiuchi, T.)

Measuring sustainability by Energy Efficiency Analysis for Korean Power Companies: A Sequential Slacks-Based Efficiency Measure

Directory of Open Access Journals (Sweden)

Ning Zhang

2014-03-01

Full Text Available Improving energy efficiency has been widely regarded as one of the most cost-effective ways to improve sustainability and mitigate climate change. This paper presents a sequential slack-based efficiency measure (SSBM application to model total-factor energy efficiency with undesirable outputs. This approach simultaneously takes into account the sequential environmental technology, total input slacks, and undesirable outputs for energy efficiency analysis. We conduct an empirical analysis of energy efficiency incorporating greenhouse gas emissions of Korean power companies during 2007–2011. The results indicate that most of the power companies are not performing at high energy efficiency. Sequential technology has a significant effect on the energy efficiency measurements. Some policy suggestions based on the empirical results are also presented.

Main building of the Paks nuclear power plant, Hungary

International Nuclear Information System (INIS)

Fejes, A.

1983-01-01

The general layout of the main service building of the power plant, the applied building materials as well as the prefabricated structures are described. The conditions of planning and construction are discussed. Novel construction methods under the given conditions were utilized. (author)

Section 1: Company directory

International Nuclear Information System (INIS)

Anon.

1991-01-01

This is a 1992 directory of those companies doing business in all areas of the independent power producers industry. The listing includes the company name, address, telephone and FAX numbers, and the name of a company contact. The listing is international in scope

Photoionization of atoms encapsulated by cages using the power-exponential potential

International Nuclear Information System (INIS)

Lin, C Y; Ho, Y K

2012-01-01

The systems of confined atoms in cages have received considerable attention for decades due to interesting phenomena arising from the effect of cage environment on the atom. For early theoretical work based on empirical model potentials, the Dirac δ-potential, i.e. the so-called bubble potential, and the attractive short-range spherical shell potential are conventionally used for the description of interaction between the valence electron of confined atom and the cage. In this work, the power-exponential potential with a flexible confining shape is proposed to model the cages. The methods of complex scaling in the finite-element discrete variable representation are implemented to investigate the hydrogen, hydrogen-like ions and alkali metals encapsulated by the cages. The energy spectrum varying with the confining well depth exhibits avoided crossings. The influence of cage on atomic photoionization leading to the oscillation behaviour or the so-called confinement resonances in cross sections is demonstrated in a variety of confined atomic systems. In comparisons with existing predictions using the Dirac δ-potential and the attractive short-range spherical shell potentials, our results show the significant influence of cage thickness and smooth shell boundary on the photoionization. The drastic changes of cross sections due to the character of cage are presented and discussed for the encaged lithium and sodium atoms. The present model is useful for clarifying the boundary effect of confining shell on the endohedral atoms. (paper)

Owners of nuclear power plants: Percentage ownership of commercial nuclear power plants by utility companies

International Nuclear Information System (INIS)

Wood, R.S.

1987-08-01

The following list indicates percentage ownership of commercial nuclear power plants by utility companies as of June 1, 1987. The list includes all plants licensed to operate, under construction, docked for NRC safety and environmental reviews, or under NRC antitrust review. It does not include those plants announced but not yet under review or those plants formally canceled. In many cases, ownership may be in the process of changing as a result of altered financial conditions, changed power needs, and other reasons. However, this list reflects only those ownership percentages of which the NRC has been formally notified. Part I lists plants alphabetically with their associated applicants/licensees and percentage ownership. Part II lists applicants/licensees alphabetically with their associated plants and percentage ownership. Part I also indicates which plants have received operating licenses (OL's). Footnotes for both parts appear at the end of this document

Service hall in Number 1 Fukushima Nuclear Power Station, Tokyo Electric Power Company, Inc

International Nuclear Information System (INIS)

Tawara, Shigesuke

1979-01-01

There are six BWR type nuclear power plants in the Number 1 Fukushima Nuclear Power Station, Tokyo Electric Power Company, Inc. The service hall of the station is located near the entrance of the station. In the center of this service hall, there is the model of a nuclear reactor of full scale. This mock-up shows the core region in the reactor pressure vessel for the number one plant. The diameter and the thickness of the pressure vessel are about 5 m and 16 cm, respectively. The fuel assemblies and control rods are set just like the actual reactor, and the start-up operation of the reactor is shown colorfully and dynamically by pushing a button. When the control rods are pulled out, the boiling of water is demonstrated. The 1/50 scale model of the sixth plant with the power generating capacity of 1100 MWe is set, and this model is linked to the mock-up of reactor written above. The operations of a recirculating loop, a turbine and a condenser are shown by switching on and off lamps. The other exhibitions are shielding concrete wall, ECCS model, and many kinds of panels and models. This service hall is incorporated in the course of study and observation of civics. The good environmental effects to fishes and shells are explained in this service hall. Official buildings and schools are built near the service hall utilizing the tax and grant concerning power generation. This service hall contributes to give much freedom from anxiety to the public by the tour. (Nakai, Y.)

Shippingport Atomic Power Station decommissioning program and applied technology

Energy Technology Data Exchange (ETDEWEB)

Crimi, F P; Skavdahl, R E

1985-01-01

The Shippingport Station decommissioning project is the first decommissioning of a large scale nuclear power plant, and also the first nuclear power plant to be decommissioned which has continued the power operation as long as 25 years. The nuclear facilities which have been decommissioned so far have operated for shorter period and were small as compared with commercial power reactors, but the experience gained by those decommissionings as well as that gained by nuclear plant maintenance and modification has helped to establish the technology and cost basis for Shippingport and future decommissioning projects. In this paper, the current status of the preparation being made by the General Electric Co., its subcontractor and the US Department of Energy for starting the decommissioning phase of the Shippingport Atomic Power Station is described. Also remote metal cutting, decontamination, concrete removal, the volume reduction of liquids and solids and robotics which will be applied to the project are discussed. The Shippingport Station is a 72 MWe PWR plant having started operation in 1957, and permanently shut down in 1982, after having generated over 7.4 billion kWh of electricity.

Report from investigation committee on the accident at the Fukushima Nuclear Power Stations of Tokyo Electric Power Company

International Nuclear Information System (INIS)

Koshizuka, Seiichi

2012-01-01

Government's Investigation Committee on the Accident at Fukushima Nuclear Power Stations of Tokyo Electric Power Company published its final report on July 23, 2012. Results of investigation combined final report and interim report published on December 26, 2011. The author was head of accident accuse investigation team mostly in charge of site response, prior measure and plant behavior. This article reported author related technical investigation results focusing on site response and prior measures against tsunamis of units 1-3 of Fukushima Nuclear Power Stations. Misunderstanding of working state of isolation condenser of unit 1, unsuitability of alternative water injection at manual stop of high-pressure coolant injection (HPCI) system of unit 3 and improper prior measure against tsunami and severe accident were pointed out in interim report. Improper monitoring of suppression chamber of unit 2 and again unsuitable work for HPCI system of unit 3 were reported in final report. Thorough technical investigation was more encouraged to update safety measures of nuclear power stations. (T. Tanaka)

Radioactive waste management at Narora atomic power station in India

International Nuclear Information System (INIS)

Prasad, P.N.; Gupta, J.P.; Mittal, S.

2001-01-01

Modern society creates waste material, which have to be disposed of in nature without disturbing the ecological equilibrium. Hence effective waste management in all industries is a major concern today. Narora Atomic Power Station (NAPS) generates low and intermediate level liquid, solid and gaseous wastes during its operation and maintenance. The generation of wastes is controlled at the source itself. The wastes are managed by adequate and appropriate treatment before being released into the environment. Different types of liquid wastes are treated by chemical co-precipitation, ion exchange, evaporation, filtration, and dilution techniques. For handling and conditioning of solid wastes, volume reduction techniques such as incineration and baling are employed. The treated wastes are immobilised by incorporation into cement and polymer matrices. Gaseous waste is cleaned by passing through pre-filters and high efficiency particulate (HEPA) filters and diluted with inactive air prior to release to the atmosphere through a 145 m high stack to get further atmospheric dilution. Regular monitoring up to 30 km radius is carried out by fully equipped Environmental Survey and Micrometeorological Laboratory which functions independently under the Directorate of Health and Safety, Bhabha Atomic Research Centre (BARC), Mumbai. So far, the annual maximum dose to the public around NAPS is reported to be 0.2 to 0.3% of limit of 1 mSv/year recommended by the International Commission on Radiological Protection (ICRP). A decade of experience has proved that present practices of nuclear waste management at Narora Atomic Power Station are quite safe and effective with respect to ecological equilibrium. (author)

77 FR 14516 - Alabama Power Company, Martin Dam Hydroelectric Project; Notice of Proposed Revised Restricted...

Science.gov (United States)

2012-03-12

... Power Company, Martin Dam Hydroelectric Project; Notice of Proposed Revised Restricted Service List for... for inclusion in, the National Register of Historic Places at the Martin Dam Hydroelectric Project...)). The Commission's responsibilities pursuant to section 106 for the Martin Dam Hydroelectric Project...

78 FR 49305 - Luminant Generation Company LLC, Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2...

Science.gov (United States)

2013-08-13

... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-445 and 50-446; NRC-2013-0182] Luminant Generation Company LLC, Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2; Application for Amendment to Facility... Operating License Nos. NPF-87 and NPF-89 for the Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2...

Discussion of manage mode for nuclear power construcation in China

International Nuclear Information System (INIS)

Gao Mingshi; Chen Hua

2007-01-01

This paper analyzed the development status of management mode for NPP construction and nuclear power engineering companies. Considering the national development plan of nuclear power, and making reference of the experiences of the successful construction of NPPs, the management mode for NPP construction in which the nuclear engineering companies are the main factors have been discussed. This paper proposed that EPC/TurnKey as the management mode for the nuclear power construction, led by the owner, and constructed by engineering companies according to the contracts, so as to establish a construction group with expertise knowledge. (authors)

Vermont Yankee Nuclear Power Station. Annual operating report: January--December 1976

International Nuclear Information System (INIS)

1977-01-01

Net electrical energy generated was 3,260,016 MWH with the facility on line for 6,776 hrs. Information is presented concerning operation, procedure changes, tests, experiments, plant changes, corrective maintenance, license event reports, forced power reductions, shutdowns, personnel radiation exposures, use of chemicals, plant discharges, cooling tower blowdown, traveling screens, fish impingement, reactor start-up, scram reports, and primary coolant chemistry

German atomic low meeting 2004

International Nuclear Information System (INIS)

Ossenbuehl, F.

2005-01-01

The conference report on the German atomic law meeting 2004 contains 14 contributions on the German atomic legislation within four parts: Damage precaution in the operational phase; Legal general requirements for the final disposal - considerations ''de lege lata'' and ''de lege ferenda''. Financing of the site searching by a statutory company (''Verbandsmodell''). Atomic supervision authority - federal executive administration or federal self administration?

Analysis of main dynamic parameters of split power transmission

Directory of Open Access Journals (Sweden)

A. Janulevičius

2008-06-01

Full Text Available The review carried out had shown one basic approach of split power transmission to the organization of drive which is applied to stepless transmissions of tractors and parallel hybrid cars. In the split power transmission the power split device uses a planetary gear. Tractor engine power in the split power transmission is transmitted to the drive shaft via a mechanical and hydraulic path. The theoretical analysis of main parameters of the split power transmission of the tractor is presented. The angular velocity of sun and coronary gears of the differential set is estimated by solution of the system of equations in which one equation is made for planetary differential gear, and another – for hydrostatic drive. The analysis of the transmission gear-ratio dependencies on the ratio of hydraulic machines capacities is carried out. Dependence of the variation of angular velocity of the coronary and the sun gears on the ground speed of the tractor is presented. Dependence of sum shaft torque and its constituents, carried by mechanical and hydraulic lines, on sum shaft angular velocity and ground speed of tractor and engine speed is also presented.

Scenarios for the popular initiatives 'Strom ohne Atom' (Electricity without nuclear power) and 'Moratorium Plus'

International Nuclear Information System (INIS)

Eckerle, K.; Haker, K.; Hofer, P.

2001-01-01

This report for the Swiss Federal Office of Energy (SFOE) presents the results of a study made on the possible effects of two Swiss Popular Initiatives which called for the shutdown of nuclear power stations in Switzerland ('Strom ohne Atom'), the restriction of their operating life and the abstention from building new atomic power stations ('Moratorium Plus'). The report examines the energetic and financial consequences of the initiatives. The approaches used for the analysis are described and the energy policy actions required to avoid gaps in the supply of power after the possible closure of the power stations are discussed. Apart from a reference scenario (long-term utilisation of nuclear energy), scenarios for power generation using co-generation are presented. The problems posed by the resulting CO 2 and NO x emissions are discussed. Further scenarios review the contribution to be made by renewable sources of energy and increasing energy-conservation efforts. The costs of the shutdown of nuclear power stations are discussed and the results of a sensitivity analysis are presented

Way to save nuclear power

International Nuclear Information System (INIS)

Brightsen, R.A.

1979-01-01

In the opinion of many citizens, including the majority of those who oppose it, nuclear power will never recover from the 1979 accident at Three Mile Island. But some of nuclear power's supporters hope that the accident will shatter past smugness and spur constructive self-criticism on the part of the companies that build reactors, the utilities that buy them, and the Federal regulators who oversee their operation--and that it will usher in an era of truly safe atomic electricity. The article reviews deficiencies of the existing nuclear regulation - industry framework, and what must be done

Motor-Generator powering the PS (Proton Synchrotron) main magnets

CERN Multimedia

1983-01-01

This motor-generator,30 MW peak, 1500 r.p.m.,pulsed power supply for the PS main magnet replaced in 1968 the initial 3000 r.p.m. motor-generator-flywheel set which had served from the PS start-up in 1959 until end 1967. See also photo 8302337 and its abstract.

Innovations in techniques of electric power in 2008

International Nuclear Information System (INIS)

Ohfusa, Takahiro; Endo, Yukio; Ino, Hiroyuki

2009-01-01

Tokyo Electric Power Company (TEPCO), Kansai Electric Power Co., Inc., Tohoku Electric Power and other nine companies reported the results of innovations in techniques of electric power in 2008, Japan. J-Power started construction of the Ohma Nuclear Power Plant (power generating capacity: 1,383 MW, ABWR) in Ohma Town, Aomori prefecture, Japan, in May 2008. TEPCO developed the low vibration control valve and carried out the model experiments using air as fluid and the simulation by computational fluid dynamics. Mach number distribution (ε L =0.068) at the valve showed change of the supersonic jet flow as time advanced and a periodic pressure change on the valve and valve seat. Japan Atomic Power Company reported development of techniques for the established nuclear power station such as control of pipe thinning of the secondary system of PWR by insertion of oxygen at Tsuruga Power Station Unit 2, risk evaluation, the effects of increase of generating power on aging deterioration, and development of heat protective clothing. Researched are a power generation plant of small-and-medium-size reactors which took in reforming technology using the location to a narrow site, funds by stakeholders and the idea of future 'fast breeder reactor system', sodium-cooled loop type reactor, which uses TRU as fuel. The accumulator tank of new type safety system for Tsuruga Power Station Unit 3 and 4 is designed and tested. Decommissioning process of Tokai Power Plant and recycling of shielding materials, blocks and concrete powder are stated. (S.Y.)

Spatio-temporal distribution of 3H in air moisture around Kakrapar Atomic Power Station

International Nuclear Information System (INIS)

Joshi, C.P.; Patra, A.K.; Jain, A.K.; Ravi, P.M.; Sarkar, P.K.; Gadhia, M.

2012-01-01

Tritium ( 3 H) is the only radioactive isotope of hydrogen. It decays to helium by emission of beta particle with a maximum energy of 18.6 keV. 3 H is most environmentally mobile radionuclide. To accomplish the task of estimating human exposure to tritium, it is necessary to know the tritium concentration in the atmosphere. Environmental Survey Laboratory (ESL) of Health Physics Division (HPD) of Bhabha Atomic Power Station (BARC) located at Kakrapar Atomic Power Station (KAPS) site is regularly monitoring the activity of tritium in the environment to ensure the safety of the public. This paper presents the result of analysis of tritium in atmospheric environment covering an area up to 30 km radius around KAPS site

Incentive mechanisms to promote energy efficiency programs in power distribution companies

International Nuclear Information System (INIS)

Osorio, Karim; Sauma, Enzo

2015-01-01

Power distribution companies (DISCOs) play an important role in promoting energy efficiency (hereafter EE), mainly due to the fact that they have detailed information regarding their clients' consumption patterns. However, under the traditional regulatory framework, DISCOs have disincentives to promote EE, due to the fact that a reduction in sales also means a reduction in their revenues and profits. Most regulatory policies encouraging EE have some embedded payment schemes that allow financing EE programs. In this paper, we focus on these EE-programs' payment schemes that are embedded into the regulatory policies. Specifically, this paper studies two models of the Principal–Agent bi-level type in order to analyze the economic effects of implementing different payment schemes to foster EE in DISCOs. The main difference between each model is that uncertainty in energy savings is considered by the electricity regulatory institution in only one of the models. In terms of the results, it is observed that, in general terms, it is more convenient for the regulator to adopt a performance-based incentive mechanism than a payment scheme financing only the fixed costs of implementing EE programs. However, if the electricity regulatory institution seeks a higher level of minimum expected utility, it is optimal to adopt a mixed system of compensation, which takes into account the fixed cost compensation and performance-based incentive payments. - Highlights: • We studied different payment schemes to promote energy efficiency in DISCOs. • We propose two bi-level models based on the Principal–Agent theory. • Uncertainty associated with energy savings is incorporated in one of the models. • A performance-based payment scheme is generally more convenient for the regulator. • A mixed payment scheme is optimal when a lower level of uncertainty is tolerated

A three-stage short-term electric power planning procedure for a generation company in a liberalized market

International Nuclear Information System (INIS)

Nabona, Narcis; Pages, Adela

2007-01-01

In liberalized electricity markets, generation companies bid their hourly generation in order to maximize their profit. The optimization of the generation bids over a short-term weekly period must take into account the action of the competing generation companies and the market-price formation rules and must be coordinated with long-term planning results. This paper presents a three stage optimization process with a data analysis and parameter calculation, a linearized unit commitment, and a nonlinear generation scheduling refinement. Although the procedure has been developed from the experience with the Spanish power market, with minor adaptations it is also applicable to any generation company participating in a competitive market system. (author)

Quality control of three main materials for civil construction of nuclear power plant

International Nuclear Information System (INIS)

Wang Feng

2011-01-01

The construction and operation of nuclear power plant is a systematic engineering. To ensure quality and safety of nuclear power plants, each work from design to operation can have certain impact on the quality and safety of the project. The quality of each related work shall be controlled. Starting from the quality control over raw materials for the civil construction of nuclear power plant, this article mainly analyzes how to control the quality and manage the three main materials of steel, concrete and modular parts in the civil construction. (author)

Tampa Electric Company Polk Power Station IGCC project: Project status

Energy Technology Data Exchange (ETDEWEB)

McDaniel, J.E.; Carlson, M.R.; Hurd, R.; Pless, D.E.; Grant, M.D. [Tampa Electric Co., FL (United States)

1997-12-31

The Tampa Electric Company Polk Power Station is a nominal 250 MW (net) Integrated Gasification Combined Cycle (IGCC) power plant located to the southeast of Tampa, Florida in Polk County, Florida. This project is being partially funded under the Department of Energy`s Clean Coal Technology Program pursuant to a Round II award. The Polk Power Station uses oxygen-blown, entrained-flow IGCC technology licensed from Texaco Development Corporation to demonstrate significant reductions of SO{sub 2} and NO{sub x} emissions when compared to existing and future conventional coal-fired power plants. In addition, this project demonstrates the technical feasibility of commercial scale IGCC and Hot Gas Clean Up (HGCU) technology. The Polk Power Station achieved ``first fire`` of the gasification system on schedule in mid-July, 1996. Since that time, significant advances have occurred in the operation of the entire IGCC train. This paper addresses the operating experiences which occurred in the start-up and shakedown phase of the plant. Also, with the plant being declared in commercial operation as of September 30, 1996, the paper discusses the challenges encountered in the early phases of commercial operation. Finally, the future plans for improving the reliability and efficiency of the Unit in the first quarter of 1997 and beyond, as well as plans for future alternate fuel test burns, are detailed. The presentation features an up-to-the-minute update on actual performance parameters achieved by the Polk Power Station. These parameters include overall Unit capacity, heat rate, and availability. In addition, the current status of the start-up activities for the HGCU portion of the plant is discussed.

Rotary-atomizer electric power generator

NARCIS (Netherlands)

Nguyen, Trieu; Tran, Tuan; de Boer, Hans L.; van den Berg, Albert; Eijkel, Jan C.T.

2015-01-01

We report experimental and theoretical results on a ballistic energy-conversion method based on a rotary atomizer working with a droplet acceleration-deceleration cycle. In a rotary atomizer, liquid is fed onto the center of a rotating flat surface, where it spreads out under the action of the

Physical reason for quantum behaviour of the electron and stability of the main state of the hydrogen atom

International Nuclear Information System (INIS)

Rangelov, J.M.

1986-01-01

An electron model is proposed explaining the physical reasons for its nonrelativistic quantum-mechanical behaviour, the origin of its own mechanical and magnetic momentum and field energy. As an example the main electron state in hydrogen atom is obtained

Performance of the Electric power companies of Burkina Faso, the Ivory Coast, Mali and Senegal, and their organizational models

International Nuclear Information System (INIS)

Girod, J.

1993-01-01

The history of the technical, economic, and financial performances of these four countries' power companies over the past two decades is recounted, and then interpreted as the result of the existing organizational models. The changes that have occurred can be understood in long-term perspective by comparing the performance of these companies to the characteristics, rules, and objectives used to define the models, which also helps explain the history of performance indicator variations. Two models are defined: one for the physical plant and one for the management. These correspond to two successive phases in the organization and operation of the electrical sector. Rural electrification and regional interconnection will be important factors in any new model or models developed for the future, because the forms they take is likely to modify the characteristics of these national power companies. 26 refs., 1 fig., 3 tabs

Design of calandria-end shield support diaphragm of Narora Atomic Power Project

Energy Technology Data Exchange (ETDEWEB)

Srivastava, S K; Nanda Kumar, S; Kakodkar, A

1975-01-01

The calandria-end shield diaphragm is one of the important components in Narora Atomic Power Plant. The support diaphragm is designed against elastic and plastic instability failures. Method of analysis for elastic and plastic instability is discussed for normal loading, pipe rupture loading, and earthquake loading.

Design of calandria-end shield support diaphragm of Narora Atomic Power Project

International Nuclear Information System (INIS)

Srivastava, S.K.; Nanda Kumar, S.; Kakodkar, A.

1975-01-01

The calandria-end shield diaphragm is one of the important components in Narora Atomic Power Plant. The support diaphragm is designed against elastic and plastic instability failures. Method of analysis for elastic and plastic instability is discussed for normal loading, pipe rupture loading and earthquake loading. (author)

76 FR 25330 - Georgia Power Company; Project No. 485-063-Georgia and Alabama, Bartletts Ferry Hydroelectric...

Science.gov (United States)

2011-05-04

... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission Georgia Power Company; Project No. 485-063--Georgia and Alabama, Bartletts Ferry Hydroelectric Project; Notice of Proposed Restricted Service... Ferry Hydroelectric Project. The Programmatic Agreement, when executed by the Commission, the Georgia...

Health physics practices and experience at Duke Power Company

International Nuclear Information System (INIS)

Lewis, L.

1986-01-01

The history and development of the health physics and as-low-as-reasonably-achievable (ALARA) program at Duke Power Company's Oconee Nuclear Station is described as are the fundamental elements of the program and how the program works. The benefits of this health physics/ALARA program have been determined to be (a) improved quality of manpower planning and scheduling, (b) increased efficiency of shutdown activities, (c) reduced cost of shutdown, (d) immediate awareness of adverse job exposure trends, (e) better management information on exposure-related problems, (f) improved accuracy of personnel and job dose records, and (g) in general, improved outage performance and subsequent plant operation. Experience with the health physics/ALARA program is discussed in terms of (a) savings of critical path time, (b) maintaining ALARA personnel doses, and (c) record capacity factors

(Shippingport Atomic Power Station). Quarterly operating report, fourth quarter 1980

Energy Technology Data Exchange (ETDEWEB)

1980-01-01

At the beginning of the fourth quarter of 1980, the Shippingport Atomic Power Station remained shutdown for the normally planned semiannual maintenance and testing program, initiated September 12, 1980. Operational testing began on November 7. Maximum power was achieved November 28 and was maintained throughout the remainder of the quarter except as noted. The LWBR Core has generated 19,046.07 EFPH from start-up through the end of the quarter. During this quarter, approximately 0.000025 curies of Xe 133 activity were released from the station. During the fourth quarter of 1980, 1081 cubic feet of radioactive solid waste was shipped out of state for burial. These shipments contained 0.037 curies of radioactivity.

76 FR 71014 - Idaho Power Company, IDACORP Energy, L.P., IDACORP, Inc.; Notice of Petition

Science.gov (United States)

2011-11-16

... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Docket No. IN03-9-000] Idaho Power Company, IDACORP Energy, L.P., IDACORP, Inc.; Notice of Petition Take notice that on September 9, 2011..., 2003,\\1\\ filed a petition to terminate Appendix B, Appendix C, and Appendix E to the Settlement...

Safety evaluation report: related to the operation of Perry Nuclear Power Plant, Units 1 and 2, Docket Nos. 50-440 and 50-441, Cleveland Electric Illuminating Company

International Nuclear Information System (INIS)

1982-08-01

Supplement No. 1 to the Safety Evaluation Report on the application filed by the Cleveland Electric Illuminating Company on behalf of itself and as agent for the Duquesne Light Company, the Ohio Edison Company, the Pennsylvania Power Company, and the Toledo Edison Company (the Central Area Power Coordination Group, CAPCO), as applicants and owners, for a license to operate the Perry Nuclear Power Plant, Units 1 and 2 (Docket Nos. 50-440 and 441). The facility is located near Lake Erie in Lake County, Ohio. This supplement has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission and reports the status of certain items that had not been resolved at the time of publication of the Safety Evaluation Report

Laser-assisted atom-atom collisions

International Nuclear Information System (INIS)

Roussel, F.

1984-01-01

The basic layer-assisted atom-atom collision processes are reviewed in order to get a simpler picture of the main physical facts. The processes can be separated into two groups: optical collisions where only one atom is changing state during the collision, the other acting as a spectator atom, and radiative collisions where the states of the two atoms are changing during the collision. All the processes can be interpreted in terms of photoexcitation of the quasimolecule formed during the collisional process. (author)

Assessment and Improving Methods of Reliability Indices in Bakhtar Regional Electricity Company

Directory of Open Access Journals (Sweden)

Saeed Shahrezaei

2013-04-01

Full Text Available Reliability of a system is the ability of a system to do prospected duties in future and the probability of desirable operation for doing predetermined duties. Power system elements failures data are the main data of reliability assessment in the network. Determining antiseptic parameters is the goal of reliability assessment by using system history data. These parameters help to recognize week points of the system. In other words, the goal of reliability assessment is operation improving and decreasing of the failures and power outages. This paper is developed to assess reliability indices of Bakhtar Regional Electricity Company up to 1393 and the improving methods and their effects on the reliability indices in this network. DIgSILENT Power Factory software is employed for simulation. Simulation results show the positive effect of improving methods in reliability indices of Bakhtar Regional Electricity Company.

The computerized radiation control system for the nuclear power plant

International Nuclear Information System (INIS)

Hunamoto, H.; Sato, T.; Taniguchi, K.

1993-01-01

Major works of Radiation control in nuclear power plant consist of occupational exposure control, radiation monitoring of working areas and surveillance of monitoring equipment, environmental monitoring and so on. Since a large amount of data will be generated from these works, therefore use of high performance computers will be indispensable. The systematization is presently being advanced in The Japan Atomic Power Company from this viewpoint and the project is being realized smoothly. The actual state is introduced

The Atoms for Peace USIS Films: Spreading the Gospel of the "Blessing" of Atomic Energy in the Early Cold War Era

Directory of Open Access Journals (Sweden)

Yuka Tsuchiya

2014-08-01

Full Text Available In 1955, the U.S. Information Service (USIS Tokyo produced a thirty-minute documentary film Blessing of Atomic Energy in commemoration of the tenth anniversary of the Atomic bombing of Hiroshima and Nagasaki. The film introduced how the Japanese government, researchers, and companies were using radioisotopes offered by the U.S. Argonne National Laboratory for the “peaceful” purposes in agriculture, medicine, hygiene, industry, and disaster prevention. The film also showed the mechanism of atomic power generation, and explained that it was already put into practice in the U.S. and Europe. The images of Japanese people enjoying the “blessing” of the “peaceful” use of atomic energy, ten years after the traumatic experience of A-bombs, were not only shown all over Japan, but also translated into different languages and shown in many countries, including the UK, Finland, Indonesia, Sudan, and Venezuela. The film was part of some fifty educational and documentary films produced for President Eisenhower’s “Atoms for Peace” campaign – a global information dissemination programs on the U.S. leadership in the civilian use of nuclear energy. This paper will explore the roles USIS films played in disseminating information on the “peaceful” use of nuclear energy in the early Cold War era.

Uncertainties in criticality analysis which affect the storage and transportation of LWR fuel

International Nuclear Information System (INIS)

Napolitani, D.G.

1989-01-01

Satisfying the design criteria for subcriticality with uncertainties affects: the capacity of LWR storage arrays, maximum allowable enrichment, minimum allowable burnup and economics of various storage options. There are uncertainties due to: calculational method, data libraries, geometric limitations, modelling bias, the number and quality of benchmarks performed and mechanical uncertainties in the array. Yankee Atomic Electric Co. (YAEC) has developed and benchmarked methods to handle: high density storage rack designs, pin consolidation, low density moderation and burnup credit. The uncertainties associated with such criticality analysis are quantified on the basis of clean criticals, power reactor criticals and intercomparison of independent analysis methods

Booster main magnet power supply, present operation and potential future upgrades

Energy Technology Data Exchange (ETDEWEB)

Bajon, E.; Bannon, M.; Marneris, I.; Danowski, G.; Sandberg, J.; Savatteri, S.

2011-03-28

The Brookhaven Booster Main Magnet Power Supply (MMPS) is a 24 pulse thyristor control supply, rated at 5500 Amps, +/-2000 Volts, or 3000 Amps, +/-6000 Volts. The power supply is fed directly from the power utility and the peak magnet power is 18 MWatts. This peak power is seen directly at the incoming ac line. This power supply has been in operation for the last 18 years. This paper will describe the present topology and operation of the power supply, the feedback control system and the different modes of operation of the power supply. Since the power supply has been in operation for the last 18 years, upgrading this power supply is essential. A new power supply topology has been studied where energy is stored in capacitor banks. DC to DC converters are used to convert the dc voltage stored in the capacitor banks to pulsed DC voltage into the magnet load. This enables the average incoming power from the ac line to be constant while the peak magnet power is pulsed to +/- 18 MWatts. Simulations and waveforms of this power supply will be presented.

The independent power production and the reorganization of the electric power sector

International Nuclear Information System (INIS)

1998-12-01

The transformation of the electric power production and distribution sector is in progress thanks to the progressive opening of markets and to the emergence of a new kind of actor: the independent producer. After the USA, the UK, and most of the emerging countries, the continental Europe is actively preparing its mutation. The historical actors try to protect their positions on their own national markets and at the same time to develop their international position. The newcomers (oil companies, independent power producers, collective service companies) have adopted a radically offensive strategy based on an international development and a skimming of the market. This study takes stock of the degree of liberalization of the different markets and analyzes their structuring elements and dynamism. An analytical presentation of the main actors of the electric power market is performed in order to evaluate their forces and feeblenesses in front of this mutation. Finally, it tries to answer the following questions: which are the most promising zones for the newcomers, and which companies will win this new deal? (J.S.)

Stopping powers and ranges for the heaviest atoms

International Nuclear Information System (INIS)

Sagaidak, Roman N.; Utyonkov, Vladimir K.; Dmitriev, Sergey N.

2015-01-01

Slowing down and stopping of the heaviest atoms, products of the fusion–evaporation nuclear reactions, during their passage through the Dubna gas-filled recoil separator has been studied using TRIM simulations. The study is important for experiments on the synthesis of super-heavy elements (SHEs) with atomic numbers around Z_P = 114 produced with accelerated heavy ion (HI) beams and extracted with a separator for their detection. The average Mylar stopping power (SP) values obtained with the simulations for HIs with 82 ⩽ Z_P ⩽ 92 reveal almost the same magnitudes, allowing extrapolation to the region of Z_P > 92. Similar extrapolation of the ranges in an He + Ar gas mixture leads to rather small values for the heaviest atoms (Z_P ⩾ 102) as compared to the range for U. The extrapolated values have large uncertainties and should be verified with different approaches. Available SP data obtained for HIs with 18 ⩽ Z_P ⩽ 92 at energies E < 20 MeV/u have been analysed within various semi-empirical approaches. The analysis has shown that existing parameterizations give Mylar SP values for Z_P ⩾ 82 that are very different from each other at energies of interest (around 0.1 MeV/u). We propose to use a general approach based on the HI effective charge parameterization obtained with available SP data for HIs and the hydrogen SP and effective charge corresponding to the same velocity and stopping medium as those for HIs. In this manner, the SPs of the gases H_2, He, C_4H_1_0, and Ar as well as those of the solids Mylar, C, Al, and Ti have been obtained for any atoms with Z_P ⩾ 18 (including the heaviest ones) at their reduced velocities 0.03 ⩽ V_r_e_d ⩽ 5.0. The SP values derived in such a way seem to be more reliable compared to the existing semi-empirical calculations and can be used in the conditioning of experiments on the synthesis of SHEs.

JAPANESE MONOPOLIST COMPANIES – INSTRUMENTS OF THE 'NATIONAL POLICY'

Directory of Open Access Journals (Sweden)

Mihut Marius Ioan

2012-12-01

Full Text Available As the title suggests, this article discusses the problem of monopolistic Japanese companies, unique features among advanced countries, and perhaps worldwide. The japanese most ardent desire was always to reach and to overcome the Western, and, as a balanced development of all companies would have taken a long time, japanese policy makers decided to support only those with good performances, around them being concentrated all energies in the east Asian archipelago. Following these important efforts (from the State, small and medium companies, people, etc., as it is well known, Japan has succeeded, precisely by those holdings, to become a tough opponent for developed countries and even to overcome them, becoming the second global power behind the United States. The importance of this article derives precisely from the fact that these companies (Zaibatsu and later hondings were the driving force behind Japan's economic development, whether we talk about the period preceding the Second World War or the next one. Even if after the American occupation, it was wanted with at all costs their liquidation, holdings being considered as close to prewar militaristic power, after the American withdrawal from the archipelago, they were rebuilt as a Japanese principle, the foundation of Japanese reconstruction. The paper aims to embody the main dimensions on which these companies have arrived, as well as their structure, the relations between them, their organization. On the topic discussed, the literature contains more general issue of the Japanese economy, without being paid (at least in the contemporary period consideration to these main pillars of Japanese capitalism development. The main work in which they are giving increased attention is written at the end of the Second World War, thus the need for the additions concerning the next period is important. The authors’ contribution lies precisely in the synthesis of information that he provides, from

Evaluation of Risks Related To Russian Power Grid Companies by Foreign Investors

Directory of Open Access Journals (Sweden)

Daria L. Val'kova

2016-01-01

Full Text Available The article focuses on the impact of the current crisis on evaluation of risks related to Russian power grid companies by foreign investors as well as on prospects of raising foreign capital. The current situation resulted in a considerable deterioration of investment climate in Russia as well as in aggravation of industry-specific problems. Inflation growth, devaluation of the national currency, GDP decrease, drop in electricity consumption and the crisis in the banking sector negatively impact the investment profile of the country. This leads to increased risk premium for foreign capital investments in any type of Russian assets. At the same time industry-specific problems augmented as well. Those are primarily lack of transparency in regulation, which is subject to constant changes, growth in overdue receivables, limited access to modern technologies. All of the above had a considerable impact on the perception of Russian risks by international investors. A comprehensive approach is needed to improve the investment climate in the country and this would be largely defined by the general macroeconomic development of the Russian Federation and relations with other states. Consistent strategy and integrated actions of the Government and respective Ministries are of particular importance. As for the industry-specific factors, transparent and well-balanced long-term tariff system is the key condition for sustainable improvement of the situation in the sector, according to the major industry participants and leading experts. Thus, the article highlights changes in investor perception of the Russian power grid sector as well as relative impact on the industry development prospects. This analysis is the basis for further elaboration of recommendations regarding easing off of the crisis impact on the power grid companies as well as for assessment of prospects of meeting strategic industry development objectives.

75 FR 7471 - Chandra Coffee and Rabun Boatworks, Complainants v. Georgia Power Company, Respondent; Notice of...

Science.gov (United States)

2010-02-19

... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 2354-10] Chandra Coffee and Rabun Boatworks, Complainants v. Georgia Power Company, Respondent; Notice of Complaint February 3, 2010. Take notice that on December 14, 2009, as amended on January 8, 2010, Chandra Coffee and Rabun...

75 FR 57746 - Lockhart Power Company; Notice of Application Tendered for Filing With the Commission, Soliciting...

Science.gov (United States)

2010-09-22

.... Applicant Contact: Bryan D. Stone, Chief Operating Officer, Lockhart Power Company, Inc., 420 River Street... Support. Although the Commission strongly encourages electronic filing, documents may also be paper-filed. To paper-file, mail an original and seven copies to: Kimberly D. Bose, Secretary, Federal Energy...

Considerations for surviving the loss of a main feedwater pump at full power

International Nuclear Information System (INIS)

Gaydos, K.A.; Calvo, R.; Conroy, P.W.; Klein, C.M.; Mellers, J.E.

1990-01-01

Today's economics dictate that nuclear power operational costs be contained by addressing frequently-occurring trips that might be minimized or avoided via specific upgrades. Much recent attention has focused on the significant percentage of plant trips related to feedwater flow regulation; however, another frequent feedwater-related trip stems from the loss of a single main feedwater pump while operating at high power levels, causing a plant trip on low steam generator water-level. This paper summarizes the results of several plant-specific studies that evaluate a unit's capabilities to consistently survive the loss of a main feedwater pump from full power, and outlines a methodology for analyzing this capability

Probabilistic safety assessment support for the maintenance rule at Duke Power Company

International Nuclear Information System (INIS)

Brewer, H. Duncan; Canady, Ken S.

1999-01-01

The Nuclear Regulatory Commission (NRC) published the Maintenance Rule on July 10, 1991 with an implementation date of July 10, 1996 . Maintenance rule implementation at the Duke Power Company has used probabilistic safety assessment (PSA) insights to help focus the monitoring of structures, systems and components (SSC) performance and to ensure that maintenance is effectively performed. This paper describes how the probabilistic risk assessment (PRA) group at the Duke Power Company provides support for the maintenance rule by performing the following tasks: (1) providing a member of the expert panel; (2) determining the risk-significant SSCs; (3) establishing SSC performance criteria for availability and reliability; (4) evaluating past performance and its impact on core damage risk as part of the periodic assessment; (5) providing input to the PRA matrix; (6) providing risk analyses of combinations of SSCs out of service; (7) providing support for the SENTINEL program; and (8) providing support for PSA training. These tasks are not simply tied to the initial implementation of the rule. The maintenance rule must be kept consistent with the current design and operation of the plant. This will require that the PRA models and the many PSA calculations performed to support the maintenance rule are kept up-to-date. Therefore, support of the maintenance rule will be one of the primary roles of the PSA group for the remainder of the life of the plant

Modern technical diagnostic system for the main components of powerful turbine generator

International Nuclear Information System (INIS)

Ezovit, G.P.; Uglyarenko, V.P.; Burlaka, S.I.; Goroz, N.I.; Orinin, S.E.; Komaritsa, V.N.; Zav'yalov, D.N.; Mazurenko, O.A.

2011-01-01

The modern diagnostic system to monitor the technical state of a powerful turbine generator is considered. This system permits the detection of defects in its main components and cooling system at the early stage of their development, prevention of damage and, as a consequence, emergency shutdown of nuclear power units

Relativistic many-body theory of atomic structures

International Nuclear Information System (INIS)

Cheng, K.T.

1983-01-01

The main objective of this program is to improve our understanding of the effect of relativity and electron correlations on atomic processes. Current efforts include hyperfine structure (hfs) studies using the multiconfiguration Dirac-Fock (MCDF) technique. Atomic hfs are known to be sensitive to relativity and electron correlations, and provide important tests of relativistic atomic many-body theories. Preliminary results on the hfs of the 4f 12 3 H ground state of 68 Er 167 are shown and are in good agreement with experiment. This shows that the MCDF technique can be an efficient and powerful method for atomic hfs studies. Further tests of this method are in progress. We are also studying the absorption spectra for Xe-like ions in the region of 4d → nf, epsilonf transitions

The Atomic energy basic law

International Nuclear Information System (INIS)

1979-01-01

The law aims to secure future energy resources, push forward progress of science and advancement of industry for welfare of the mankind and higher standard of national life by helping research, development and utilization of atomic power. Research, development and utilization of atomic power shall be limited to the peaceful purpose with emphasis laid on safety and carried on independently under democratic administration. Basic concepts and terms are defined, such as: atomic power; nuclear fuel material; nuclear raw material; reactor and radiation. The Atomic Energy Commission and the Atomic Energy Safety Commission shall be set up at the Prime Minister's Office deliberately to realize national policy of research, development and utilization of atomic power and manage democratic administration for atomic energy. The Atomic Energy Commission shall plan, consider and decide matters concerning research, development and utilization of atomic energy. The Atomic Energy Safety Commission shall plan, consider and decide issues particularly concerning safety securing among such matters. The Atomic Energy Research Institute shall be founded under the governmental supervision to perform research, experiment and other necessary affairs for development of atomic energy. The Power Reactor and Nuclear Fuel Development Corporation shall be established likewise to develop fast breeding reactor, advanced thermal reactor and nuclear fuel materials. Development of radioactive minerals, control of nuclear fuel materials and reactors and measures for patent and invention concerning atomic energy, etc. are stipulated respectively. (Okada, K.)

76 FR 7840 - American Hydro Power Company; Notice of Termination of Exemption by Implied Surrender and...

Science.gov (United States)

2011-02-11

... Power Company; Notice of Termination of Exemption by Implied Surrender and Soliciting Comments, Protests... the Commission: a. Type of Proceeding: Termination of exemption by implied surrender. b. Project No... if any term or condition of the exemption is violated. The project has not operated since 2004, and...

Method of accounting for code safety valve setpoint drift in safety analyses

International Nuclear Information System (INIS)

Rousseau, K.R.; Bergeron, P.A.

1989-01-01

In performing the safety analyses for transients that result in a challenge to the reactor coolant system (RCS) pressure boundary, the general acceptance criterion is that the peak RCS pressure not exceed the American Society of Mechanical Engineers limit of 110% of the design pressure. Without crediting non-safety-grade pressure mitigating systems, protection from this limit is mainly provided by the primary and secondary code safety valves. In theory, the combination of relief capacity and setpoints for these valves is designed to provide this protection. Generally, banks of valves are set at varying setpoints staggered by 15- to 20-psid increments to minimize the number of valves that would open by an overpressure challenge. In practice, however, when these valves are removed and tested (typically during a refueling outage), setpoints are sometimes found to have drifted by >50 psid. This drift should be accounted for during the performance of the safety analysis. This paper describes analyses performed by Yankee Atomic Electric Company (YAEC) to account for setpoint drift in safety valves from testing. The results of these analyses are used to define safety valve operability or acceptance criteria

Methods of selection and training of personnel for the Rajasthan atomic power station

International Nuclear Information System (INIS)

Sarma, M.S.R.; Wagadarikar, V.K.

1975-01-01

Personnel selected to work in a nuclear electric generating station rarely have the necessary knowledge and experience in all the related fields. A station can be operated and maintained and at the same time radiation doses absorbed by station personnel can be kept to a minimum only if the operating personnel are familiar with, and can be used for, all phases of station operation and the maintainers have more than one skill or trade. More technical knowledge and more diversified skills, in addition to those required in other industries, are needed because of the nature of the nuclear reactor and the associated radiation environment and high automation. A training programme has been developed at the Nuclear Training Centre (NTC) near the Rajasthan Atomic Power Station (RAPS), Kota, India, to cater to the needs of the operation and maintenance personnel for nuclear power stations including the Madras Atomic Power Station. This programme has been in operation for the last five years. The paper describes the method of recruitment/selection of various categories of personnel and the method of training them to meet the job requirements. (author)

Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites

Energy Technology Data Exchange (ETDEWEB)

Maheras, Steven J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Best, Ralph E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Ross, Steven B. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Buxton, Kenneth A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); England, Jeffery L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McConnell, Paul E. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Massaro, Lawrence M. [Fermi Research Alliance (FRA), Batavia, IL (United States); Jensen, Philip J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2016-09-30

A preliminary evaluation of removing spent nuclear fuel (SNF) from 13 shutdown nuclear power plant sites was performed. At these shutdown sites the nuclear power reactors have been permanently shut down and the sites have been decommissioned or are undergoing decommissioning. The shutdown sites were Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, Zion, Crystal River, Kewaunee, San Onofre, and Vermont Yankee. The evaluation was divided into four components: Characterization of the SNF and greater-than-Class C low-level radioactive waste (GTCC waste) inventory A description of the on-site infrastructure at the shutdown sites An evaluation of the near-site transportation infrastructure and transportation experience at the shutdown sites An evaluation of the actions necessary to prepare for and remove SNF and GTCC waste. The primary sources for the inventory of SNF and GTCC waste were the U.S. Department of Energy (DOE) spent nuclear fuel inventory database, industry publications such as StoreFUEL, and government sources such as the U.S. Nuclear Regulatory Commission. The primary sources for information on the conditions of on-site infrastructure and near-site transportation infrastructure and experience included information collected during site visits, information provided by managers at the shutdown sites, Facility Interface Data Sheets compiled for DOE in 2005, Services Planning Documents prepared for DOE in 1993 and 1994, industry publications such as Radwaste Solutions, and Google Earth. State staff, State Regional Group representatives, a Tribal representative, and a Federal Railroad Administration representative have participated in nine of the shutdown site visits. Every shutdown site was found to have at least one off-site transportation mode option for removing its SNF and GTCC waste; some have multiple options. Experience removing large components during reactor decommissioning provided an

78 FR 14361 - In the Matter of Luminant Generation Company LLC, Comanche Peak Nuclear Power Plant, Units 1 and...

Science.gov (United States)

2013-03-05

... NUCLEAR REGULATORY COMMISSION [NRC-2012-0310; Docket Nos. 50-445 and 50-446; License Nos. NPF-87 and NPF-89] In the Matter of Luminant Generation Company LLC, Comanche Peak Nuclear Power Plant, Units... Nuclear Power Plant, Units 1 and 2 (CPNPP), and its Independent Spent Fuel Storage Installation Facility...

Electric utility companies and geothermal power

Science.gov (United States)

Pivirotto, D. S.

1976-01-01

The requirements of the electric utility industry as the primary potential market for geothermal energy are analyzed, based on a series of structured interviews with utility companies and financial institution executives. The interviews were designed to determine what information and technologies would be required before utilities would make investment decisions in favor of geothermal energy, the time frame in which the information and technologies would have to be available, and the influence of the governmental politics. The paper describes the geothermal resources, electric utility industry, its structure, the forces influencing utility companies, and their relationship to geothermal energy. A strategy for federal stimulation of utility investment in geothermal energy is suggested. Possibilities are discussed for stimulating utility investment through financial incentives, amelioration of institutional barriers, and technological improvements.

To question of NPP power reactor choice for Kazakhstan

International Nuclear Information System (INIS)

Batyrbekov, G.A.; Makhanov, Y.M.; Reznikova, R.A.; Sidorenco, A.V.

2004-01-01

in the regions of Republic of Kazakhstan occurs. Southern and western regions import electric power and capacity because of undeveloped circuit of networks. Moreover, power intensity of an industrial-agrarian complex of the country is limited transmission capacity of lines is insufficient; plenty of small consumers are removed from power supply lines. Thus, nuclear stations of medium and low power are the most acceptable for construction in Kazakhstan. Recommendations for the choice of maximum safe, reliable and economically competitive reactors for Kazakhstan have been made in result of the carried out projects' comparison of the power reactors according to 15 criteria of safety and economic competitiveness, with respect to condition and perspectives of Kazakhstan power complex development: Recommended power reactors of medium capacity: - P-600 - passive PWR, developed of the Westinghouse company, USA; - CANDU-6, developed by Atomic Energy of Canada, Limited (AECL), Canada. - MS-600 - Mitsubishi Company, Japan. Recommended reactors of low power: - IRIS - reactor of IV generation developed by the international corporation of 13 organizations from 7 countries; - NPP 'UNITERM' - development NIKIET, Moscow, Russia; - MRX - the Project of sea reactor MRX for civil applications, is developed by the Japanese Research Institute of Atomic Energy (JAERI). The most important advantages of recommended medium and low power reactors are given

To question of NPP power reactor choice for Kazakhstan

International Nuclear Information System (INIS)

Batyrbekov, G.A.; Makhanov, Y.M.; Reznikova, R.A.; Sidorenco, A.V.

2004-01-01

regions of Republic of Kazakhstan occurs. Southern and western regions import electric power and capacity because of undeveloped circuit of networks. Moreover, power intensity of an industrial-agrarian complex of the country is limited transmission capacity of lines is insufficient; plenty of small consumers are removed from power supply lines. Thus, nuclear stations of medium and low power are the most acceptable for construction in Kazakhstan. Recommendations for the choice of maximum safe, reliable and economically competitive reactors for Kazakhstan have been made in result of the carried out projects' comparison of the power reactors according to 15 criteria of safety and economic competitiveness, with respect to condition and perspectives of Kazakhstan power complex development: Recommended power reactors of medium capacity: - P-600 - passive PWR, developed of the Westinghouse company, USA; - CANDU-6, developed by Atomic Energy of Canada, Limited (AECL), Canada. - MS-600 - Mitsubishi Company, Japan. Recommended reactors of low power: - IRIS - reactor of IV generation developed by the international corporation of 13 organizations from 7 countries; - NPP 'UNITERM' - development NIKIET, Moscow, Russia; - MRX - the Project of sea reactor MRX for civil applications, is developed by the Japanese Research Institute of Atomic Energy (JAERI). The most important advantages of recommended medium and low power reactors are given

Report on the atom what you should know about atomic energy

CERN Document Server

Dean, Gordon

1954-01-01

The American approach to the atom ; Uranium is where you find it ; the production line: ore to bombs ; the expanding programme ; the headaches ; the pay-off: weapons ; the military and the atoms ; power: the peaceful goals, first phase ; power: the peaceful goals, second goals ; radioisotopes: servants of man ; the quest for knowledge ; secrecy, security and spies ; the international atom ; behind the Iron Curtain ; the way ahead.

75 FR 62531 - Alabama Power Company; Project No. 349-150-Alabama Martin Dam Hydroelectric Project; Notice of...

Science.gov (United States)

2010-10-12

... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission Alabama Power Company; Project No. 349-150--Alabama Martin Dam Hydroelectric Project; Notice of Proposed Restricted Service List for a... the Martin Dam Hydroelectric Project. The Programmatic Agreement, when executed by the Commission, the...

Progress of innovation of electrical power technology in 2013

International Nuclear Information System (INIS)

Nakaiwa, Masaru; Inumaru, Jun; Hamada, Takashi

2014-01-01

The following is the description of technical innovations at five companies including Central Research Institute of Electric Power Industry, Japan Atomic Energy Agency, and Japan Nuclear Fuel Ltd. Central Research Institute of Electric Power Industry presented their efforts in (1) advancement of the safety of light water reactors (2) clarification of radiological risks and improvement of radiation protection matters (3) support of backend projects and (4) countermeasures against natural disasters for electric power distribution facilities aiming at the establishment of the optimum risk management. Japan Atomic Energy Agency presented the research and development related to (1) measures taken for the Fukushima Daiichi nuclear power plant accident (2) practical use of FBR cycle (3) disposal technology of high-level radioactive wastes (4) technical system to extract fusion energy (5) particle beam technology (6) research based on the formation of the foundation and social needs of atomic study (7) nuclear hydrogen/heat application (8) atomic safety (9) backend measures; and (10) nuclear proliferation. Japan Nuclear Fuel Ltd. presented the record of 5 and half years from the start to the completion of vitrification test. In the course of the development, the active test started from March 2003 was suspended due to the Great East Japan Earthquake on March 11th, 2011 but resumed thereafter and completed. (S.Y.)

Examination of stainless steel-clad Connecticut Yankee fuel assembly S004 after storage in borated water

International Nuclear Information System (INIS)

Langstaff, D.C.; Bailey, W.J.; Johnson, A.B. Jr.; Landow, M.P.; Pasupathi, V.; Klingensmith, R.W.

1982-09-01

A Connecticut Yankee fuel assembly (S004) was tested nondestructively and destructively. It was concluded that no obvious degradation of the 304L stainless steel-clad spent fuel from assembly S004 occurred during 5 y of storage in borated water. Furthermore, no obvious degradation due to the pool environment occurred on 304 stainless steel-clad rods in assemblies H07 and G11, which were stored for shorter periods but contained operationally induced cladding defects. The seam welds in the cladding on fuel rods from assembly S004, H07, and G11 were similar in that they showed a wrought microstructure with grains noticeably smaller than those in the cladding base metal. The end cap welds showed a dendritically cored structure, typical of rapidly quenched austenitic weld metal. Some intergranular melting may have occurred in the heat-affected zone (HAZ) in the cladding adjacent to the end cap welds in rods from assemblies S004 and H07. However, the weld areas did not show evidence of corrosion-induced degradation

The main pump motor remote visual check in the application of the domestic nuclear power plants