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

Preliminary irradiation test results from the Yankee Atomic Electric Company reactor vessel test irradiation program

International Nuclear Information System (INIS)

Biemiller, E.C.; Fyfitch, Stephen; Campbell, C.A.

1994-01-01

The Yankee Atomic Electric Company test irradiation program was implemented to characterize the irradiation response of representative Yankee Rowe reactor vessel beltline plate materials and to remove uncertainties in the analysis of existing irradiation data on the Yankee Rowe reactor vessel steel. Plate materials each containing 0.24 w/o copper, but different nickel contents at 0.63 w/o and 0.19 w/o, were heat treated to simulate the Yankee vessel heat treatment (austenitized at 982 o C (1800 o F)) and to simulate Regulatory Guide 1.99 database materials (austenitized at 871 o C (1600 o F)). These heat treatments produced different microstructures so the effect of microstructure on irradiation damage sensitivity could be tested. Because the nickel content of the test plates varied and the copper level was constant, the effect of nickel on irradiation embrittlement was also tested. Correlation monitor material, HSST-02, was included in the program to benchmark the Ford Nuclear Reactor (University of Michigan Test Reactor) which had never been used before for this type of irradiation program. Materials taken from plate surface locations (versus 1/4 T) were included to test whether or not the improved toughness properties of the plate surface layer, resulting from the rapid quench, are maintained after irradiation. If the improved properties are maintained, pressurized thermal shock calculations could utilize this margin. Finally, for one experiment, irradiations were conducted at two irradiation temperatures (260 o C and 288 o C) to determine the effect of irradiation temperature on embrittlement. (Author)

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

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

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

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

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...

Stakeholder involvement in the decommissioning of Trojan and Maine Yankee nuclear power plants

International Nuclear Information System (INIS)

Watson, Bruce A.; Orlando, Dominick A.

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 the decommissioning planning, the conduct of decommissioning operations, the volume of low-level radioactive waste, 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 its 10 CFR Part 50 license. Maine Yankee elected to reduce the 10 CFR Part 50 license to only the requirements for the ISFSI. 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, stakeholder and public input resulted in the licensee entering into an agreement with a citizen group and resulted in State legislation that lowered the dose limit below the NRC radiological criteria of 0.25 milli-Sievert/year (mSv/yr) (25 mrem/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) that were well below the NRC DCGL screening values. This contributed to

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

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

78 FR 26401 - Connecticut Yankee Atomic Power Company, Haddam Neck Plant, Environmental Assessment and Finding...

Science.gov (United States)

2013-05-06

... Atomic Power Company, Haddam Neck Plant, Environmental Assessment and Finding of No Significant Impact... Neck Plant (HNP) Independent Spent Fuel Storage Installation (ISFSI). CYAPCO stated that the exemption...-rm/adams.html . From this site, you can access the NRC's ADAMS, which provides text and image files...

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

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

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

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 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

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

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

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...

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.)

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)

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

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

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.

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...

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

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)

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

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.

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

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)

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

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.

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

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.)

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.)

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...

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)

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.)

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.)

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)

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

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...

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.)

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

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

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.

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.

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)

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 ...

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.

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.

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.

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.

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

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

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.)

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)

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

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

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.

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

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

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)

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

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)

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)

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

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

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.

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

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

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)

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

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.

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

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.)

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

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.)

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.

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

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...

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

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.)

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

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.)

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

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....

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...

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)

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)

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

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.)

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.

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

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)

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.

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.)

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)

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

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

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)

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

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

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)

(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.

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

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...

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...

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.

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.)

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.)

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)

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

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.

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

Regulation for delivery of subsidies for urgent safety measures for atomic power generating facilities

International Nuclear Information System (INIS)

1981-01-01

This rule is established under the provisions of the law for the proper enforcement of subsidy budgets and the ordinance for the execution of this law and to practice these provisions. It is applied to the delivery of subsidies for the expenses of the measures taken beforehand for the security of inhabitants in the surrounding areas of atomic power generating facilities in the emergency time of hazard or the danger of the occurrence of hazard by such facilities. Basic terms are defined, such as atomic power generating facilities and others, prefecture concerned, cities, towns and villages concerned, emergency communication network arrangement business, emergency medical facility arrangement business, business of holding hazard prevention course and expected date of beginning operation. Directors of ministries and agencies concerned deliver, if necessary, to prefectures concerned subsidies for all or a part of the expenses needed for the businesses of emergency communication network arrangement, emergency medical facility arrangement and holding hazard prevention course. The terms of delivery and the amounts of subsidies vary according to the kinds of businesses. Prefectures which intend to apply for the delivery of subsidies shall file to the director of the ministry or agency concerned the specified application attaching the operation plans of businesses and the general explanation of atomic power generating facilities, etc. The decision and conditions of delivery, reports on the situations and results of businesses and other related matters are defined, respectively. (Okada, K.)

Radiological mapping of emergency planning zone of Narora Atomic Power Station

International Nuclear Information System (INIS)

Pujari, R.N.; Saindane, Shashank; Narsaiah, M.V.R.; Solase, S.S.; Chaudbury, Probal; Kumar, Deepak; Gautam, Y.P.; Sharma, A.K.; Kumar, Avinash

2016-01-01

As a part of emergency preparedness programme, environmental radiation monitoring of Emergency Planning Zone (EPZ) (16 km radius) of Nuclear Power Plants (NPPs) is being carried out periodically. An environmental radiation monitoring of EPZ of Narora Atomic Power Station (NAPS) was carried out by installing various state-of-the-art mobile radiation monitoring systems in a vehicle and soil samples were collected from 40 locations. Around 200 important villages within EPZ were monitored and the radiological mapping of the monitored area is shown. The average dose rate recorded was 125 ± 28.8 nGy h -1 . Analysis of the collected dose rate data and the soil samples indicate normal background radiation level in the area

Partial thorium loading in the initial core of Kakrapar atomic power reactor

International Nuclear Information System (INIS)

Balakrishnan, M.R.

1993-01-01

The first unit of Kakrapar nuclear power station has gone critical with some thorium oxide fuel bundles loaded in its core. The thorium helps to flatten the power by reducing neutron flux in the centre of the reactor. However, the placing of the thorium had to be planned with care, because if the neutron flux at a point where a safety rod is located is depressed, the reactivity worth of the safety rod gets reduced. Using a dynamic programing approach, the Reactor Engineering Division of Bhabha Atomic Research Centre worked out a satisfactory configuration for loading the thorium bundles

Experimental study of stopping powers for ions of intermediate atomic numbers

International Nuclear Information System (INIS)

Bucher, R.G.

1975-01-01

A technique has been developed to measure the energy loss as a function of ion atomic number for the fragments emitted by the spontaneous fission of 252 Cf; the atomic numbers of the fragments were directly measured by the detection of a characteristic K x-ray. The measured energy losses were compared with the theories of Lindhard and of Firsov, with the tabulation of Northcliffe and Schilling, and with the semiempirical formula of Moak and Brown. For the light fragments the measured values are in good agreement with the predictions of Moak--Brown and Northcliffe--Schilling; for the heavy fragments the measured values are approximately midway between the prediction of Moak--Brown and Northcliffe--Schilling and those of Lindhard for xi/sub epsilon/ = 2. The difference in the stopping powers for adjacent ion atomic numbers Z 1 was concluded to be (1.8 +- 0.2) percent for 40 less than or equal to Z 1 less than or equal to 45 at a velocity of 1.36 cm/ns and (2.0 +- 0.1) percent for 53 less than or equal to Z 1 less than or equal to 58 at a velocity of 1.04 cm/ns

Thoughts on Documentation of Atomic Power Technology

International Nuclear Information System (INIS)

Oh, Jeong Hoon; Lee, Hee Won; Song, Ki Chan

2012-01-01

Korean Atomic Energy Research Institute (KAERI) has accumulated a number of technology development and research outcomes, including its representative achievements such as atomic energy technology independence and the first export of atomic energy system, since it was established in 1959. With its long history of over 50 years, KAERI has produced a large amount of information and explicit knowledge such as experiment data, database, design data, report, instructions, and operation data at each stage of its research and development process as it has performed various researches since its establishment. Also, a lot of tacit knowledge has been produced both knowingly and not unknowingly based on the experience of researchers who have participated in many projects. However, in the research environment in Korea where they focus overly on the output, tacit knowledge has not been managed properly compared to explicit knowledge. This tacit knowledge is as an important asset as explicit knowledge for an effective research and development. Moreover, as the first generation of atomic energy independence and research manpower retire, their accumulated experience and knowledge are in danger of disappearing. Therefore, in this study, we sought how to take a whole view and to document atomic energy technology researched and developed by KAERI, from the background to achievement of each field of the technology. Comprehensive and systematic documentation of atomic energy technology will establish a comprehensive management system of national atomic energy technology record to make a foundation of technical advancement and development of atomic energy technology. Also, it is expected to be used as an important knowledge and information resource of atomic energy knowledge management system

Trends of personal dosimetry at atomic power plants

International Nuclear Information System (INIS)

Yamamura, Seini

1998-01-01

The individual dosimetry at the atomic power station is sorted for monthly dosimetry, daily dosimetry and special job dosimetry in high dose circumstance. Film badge (passive dosimeter) can measure gamma dose, beta dose and neutron dose respectively lower than about 0.1 mSv. While workers are in the radiation controlled area, they have to wear the dosimeters and the individual dose is accumulated for every one month. Recently the Silicon semiconductors detecting beta ray and neutron have been developed. With microcircuit technology and these new sensors, new multiple function dosimeter of the card size had been put to practical use. The result of dose measurement obtained by the electronic dosimeter is consistent well with the measurement of usual film badge and new dosimeter can determine the dose as low as 0.01 mSv. The result is stored in the non-volatile memory in the electronic personal dosimeter and held for more than one year without the power supply. The function to read data directly from the memory improves the reliability of the data protection. The realization of the unified radiation control system that uses the electronic personal dosimeter for monthly dosimetry is expected. (J.P.N.)

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

Water electrolysis plants for hydrogen and oxygen production. Shipped to Tsuruga Power Station Unit No.1, and Tokai No.2 power station, the Japan Atomic Power Co

International Nuclear Information System (INIS)

Ueno, Syuichi; Sato, Takao; Ishikawa, Nobuhide

1997-01-01

Ebara's water electrolysis plants have been shipped to Tsuruga Power Station Unit No.1, (H 2 generation rate: 11 Nm 3 /h), and Tokai No.2 Power Station (H 2 generation rate: 36 Nm 3 /h), Japan Atomic Power Co. An outcome of a business agreement between Nissho Iwai Corporation and Norsk Hydro Electrolysers (Norway), this was the first time that such water electrolysis plants were equipped in Japanese boiling water reactor power stations. Each plant included an electrolyser (for generating hydrogen and oxygen), an electric power supply, a gas compression system, a dehumidifier system, an instrumentation and control system, and an auxiliary system. The plant has been operating almost continuously, with excellent feedback, since March 1997. (author)

Atomic Fisher information versus atomic number

International Nuclear Information System (INIS)

Nagy, A.; Sen, K.D.

2006-01-01

It is shown that the Thomas-Fermi Fisher information is negative. A slightly more sophisticated model proposed by Gaspar provides a qualitatively correct expression for the Fisher information: Gaspar's Fisher information is proportional to the two-third power of the atomic number. Accurate numerical calculations show an almost linear dependence on the atomic number

Atom for peace, code for war. The technology policy of the atomic power solution in Finland between 1955-1970; Rauhan atomi, sodan koodi. Suomalaisen atomivoimaratkaisun teknopolitiikka 1955-1970

Energy Technology Data Exchange (ETDEWEB)

Sarkikoski, T.

2011-07-01

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

Metal powder production by gas atomization

Science.gov (United States)

Ting, E. Y.; Grant, N. J.

1986-01-01

The confined liquid, gas-atomization process was investigated. Results from a two-dimensional water model showed the importance of atomization pressure, as well as delivery tube and atomizer design. The atomization process at the tip of the delivery tube was photographed. Results from the atomization of a modified 7075 aluminum alloy yielded up to 60 wt pct. powders that were finer than 45 microns in diameter. Two different atomizer designs were evaluated. The amount of fine powders produced was correlated to a calculated gas-power term. An optimal gas-power value existed for maximized fine powder production. Atomization at gas-power greater than or less than this optimal value produced coarser powders.

Intertidal ecology of the sea shore near Tarapur Atomic Power Station

International Nuclear Information System (INIS)

Balani, M.C.

1975-01-01

Surveys were carried out between March 1969 and August 1970 to study the fauna and flora in the littoral zone of the sea shore near the Tarapur Atomic Power Station. The beach adjacent to the Station is rocky with a number of tidal pools inhabited by a variety of organisms whereas the beach to the south is mostly sandy and barren except for a small rocky stretch. The tidal range is 6 m and over a mile of beach is exposed during low tide. The near shore currents are very strong and have a clear northsouth oscillation with the changing tides. Less Atherina sp. fry were available near the Power Station in March 1970 than during the previous year. Possible reasons for these differences are discussed, including the effect of heated discharges on biota. The need is also emphasized to monitor the biota (Plankton, Nekton and Benthos) systematically for content of fission products released by the Power Station. (auth.)

Decommissioning of the Shippingport Atomic Power Station. Draft environmental impact statement

International Nuclear Information System (INIS)

1981-10-01

The US DOE proposes to decommission the Shippingport Atomic Power Station. This environmental impact statement analyzes possible decommissioning alternatives, evaluates potential environmental impacts associated with each alternative, and presents cost estimates for each alternative. The Department's preferred decommissioning alternative is immediate dismantlement. Other alternatives include no action, safe storage followed by deferred dismantlement, and entombment. The environmental impacts that are evaluated include those associated with occupational radiation dose, public radiation dose, handling and transporting of radioactive wastes, resource commitments, and socio-economic effects

The future of nuclear power: An IAEA perspective. Address at the German atomic forum, Berlin, 27 January 2000

International Nuclear Information System (INIS)

ElBaradei, M.

2000-01-01

In his address at the German Atomic Forum (Berlin, 27 January 2000), the Director General of the IAEA presented a survey of the prospects for nuclear power as seen from the perspective of the IAEA. The speech focussed on the following aspects: nuclear power and world energy requirements, nuclear and radiation safety, competitiveness of nuclear power, and public support

Assessment of tritium dose around Rajasthan Atomic Power Station (1989-1997)

International Nuclear Information System (INIS)

Verma, P.C.; Vijaykumar, B.; George, Thomas; Sankhla, Rajesh; Roy, Alpana; Vyas, P.V.; Gurg, R.P.

1999-01-01

Tritium monitoring in the atmospheric and aquatic environment forms an integral part of the environmental radiological measurements conducted around PHWR type Nuclear Power Plant sites as tritium is one of the predominantly produced radionuclides in such systems. This paper presents the tritium concentration levels in the atmospheric and aquatic environs of Rajasthan Atomic Power Station (RAPS) during 1989-1997. The committed effective doses due to tritium are computed on annual basis for different radial zones around RAPS. It is observed that the maximum dose due to tritium at 1.6 km post fence has been less than 1% of the dose limit (1 mSv) set by regulatory body for the members of the public and beyond 5 km distance it is only 0.4% of the limit. (author)

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...

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...

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

Nuclear power. Nuclear fuel cycle and waste management. 1990-2002. International Atomic Energy Agency publications

International Nuclear Information System (INIS)

2002-02-01

This document lists all sales publications of the International Atomic Energy Agency dealing with Nuclear Power, Nuclear Fuel Cycle and Waste Management, issued during the period 1990-2002. It gives a short abstract of these publications along with contents and their costs

Review of modifications performed to core monitoring systems related to core reloading

International Nuclear Information System (INIS)

Carew, J.F.; Diamond, D.J.

1978-09-01

The recent increase in the number of licensees selecting new fuel suppliers for reload cycles has resulted in a trend toward Core Monitoring Systems (CMS) for which the cycle dependent data and the CMS software are supplied by different vendors. At the request of and under the direction of the Division of Operating Reactors, USNRC, a review of the qualification and documentation for these CMS has been made. Several potential problem areas in the determination of CMS cycle dependent input involving empirical normalizations and relatively complex neutronic analysis were identified. As representative of present qualification and documentation practices, Yankee Atomic Electric Co., Virginia Electric Power Co., Nuclear Associations International, Exxon Nuclear Co., Northeast Utilities Service Co. and Jersey Central Power and Light were selected and reviewed in detail

Ubiquitous atom

International Nuclear Information System (INIS)

Spruch, G.M.; Spruch, L.

1974-01-01

The fundamentals of modern physics, including the basic physics and chemistry of the atom, elementary particles, cosmology, periodicity, and recent advances, are surveyed. The biology and chemistry of the life process is discussed to provide a background for considering the effects of atomic particles on living things. The uses of atomic power in space travel, merchant shipping, food preservation, desalination, and nuclear clocks are explored. (Pollut. Abstr.)

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

Tape transfer atomization patterning of liquid alloys for microfluidic stretchable wireless power transfer.

Science.gov (United States)

Jeong, Seung Hee; Hjort, Klas; Wu, Zhigang

2015-02-12

Stretchable electronics offers unsurpassed mechanical compliance on complex or soft surfaces like the human skin and organs. To fully exploit this great advantage, an autonomous system with a self-powered energy source has been sought for. Here, we present a new technology to pattern liquid alloys on soft substrates, targeting at fabrication of a hybrid-integrated power source in microfluidic stretchable electronics. By atomized spraying of a liquid alloy onto a soft surface with a tape transferred adhesive mask, a universal fabrication process is provided for high quality patterns of liquid conductors in a meter scale. With the developed multilayer fabrication technique, a microfluidic stretchable wireless power transfer device with an integrated LED was demonstrated, which could survive cycling between 0% and 25% strain over 1,000 times.

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

Evaluation of the integrity of reactor vessels designed to ASME Code, Sections I and/or VIII

International Nuclear Information System (INIS)

Hoge, K.G.

1976-01-01

A documented review of nuclear reactor pressure vessels designed to ASME Code, Sections I and/or VIII is made. The review is primarily concerned with the design specifications and quality assurance programs utilized for the reactor vessel construction and the status of power plant material surveillance programs, pressure-temperature operating limits, and inservice inspection programs. The following ten reactor vessels for light-water power reactors are covered in the report: Indian Point Unit No. 1, Dresden Unit No. 1, Yankee Rowe, Humboldt Bay Unit No. 3, Big Rock Point, San Onofre Unit No. 1, Connecticut Yankee, Oyster Creek, Nine Mile Point Unit No. 1, and La Crosse

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.)

Recommendations regarding problems of research policy relating to the establishment and operation of atomic power stations in Denmark

Energy Technology Data Exchange (ETDEWEB)

1976-01-01

This report, which was submitted by the Danish Planning Council for Research to the Parliamentary Committee on Scientific Research, is based on reports from the DANISH Atomic Energy Commission. and on a sub-committee appointed by the Planning Council, as well as on the comments of the Danish Research Council on these reports. The Planning Council submit that: (1) the question of the introduction and scope of Danish utilization of atomic energy should be considered as a link in setting up a total plan for energy policy elucidating the possibilities in the energy field from both aspects of supply and demand, (2) that there is a continuous interaction between energy policy and research policy in the subject field, (3) that the total resources for energy research and development should be considerably increased, (4) that investigations into the economy of atomic power should be intensified, and (5) that investigations of possibilities for long-term storage of radioactive waste in Denmark should be speeded up. Further, the Planning Council points out the need for research in areas such as (a) wind and solar energy, (b) the environmental impact of utilizing atomic power in relation to that of utilizing other forms of power, (c) economic and social effects of different forms of energy supply, as well as the problems of siting, decision taking and public information and participation and finally, (d) the utilization of the energy raw materials found in Greenland.

Recommendations regarding problems of research policy relating to the establishment and operation of atomic power stations in Denmark

International Nuclear Information System (INIS)

1976-01-01

This report, which was submitted by the Danish Planning Council for Research to the Parliamentary Committee on Scientific Research, is based on reports from the DANISH Atomic Energy Commission. and on a sub-committee appointed by the Planning Council, as well as on the comments of the Danish Research Council on these reports. The Planning Council submit that: 1) the question of the introduction and scope of Danish utilization of atomic energy should be considered as a link in setting up a total plan for energy policy elucidating the possibilities in the energy field from both aspects of supply and demand, 2) that there is a continuous interaction between energy policy and research policy in the subject field 3) that the total resources for energy research and development should be considerably increased, 4) that investigations into the economy of atomic power should be intensified, and 5) that investigations of possibilities for long-term storage of radioactive waste in Denmark should be speeded up. Further, the Planning Council points out the need for research in areas such as a) wind and solar energy, b) the environmental impact of utilizing atomic power in relation to that of utilizing other forms of power, c) economic and social effects of different forms of energy supply, as well as the problems of siting, decision taking and public information and participation and finally, d) the utilization of the energy raw materials found in Greenland. (B.P.)

Atoms: for war or peace

Energy Technology Data Exchange (ETDEWEB)

Subrahmanyam, K V

1981-08-01

History of nuclear power generation starting from the experimental split of uranium atom in 1938 to the establishment of the International Atomic Energy Agency is traced. In India, the Atomic Energy Commission was established with the major objective of developing nuclear power to make up India's deficiencies in energy sources. It is noted that from the very beginning the commission's activities were covered under a blanket of secrecy. According to the author, India's atomic energy programme stagnated after Dr. Bhabha's death. The Department of Atomic Energy diverted its attention to the nuclear explosion which was carried out in 1974. This event caused a great setback to the collaboration with Canada and USA in the nuclear power programme. The resulting problems are still not fully solved. The author maintains that the Department of Atomic Energy should have confined its efforts to the reactor development with special reference to the fast breeder reactor so that thorium can be utilised to the maximum advantage.

Isotopic validation for PWR actinide-only burnup credit using Yankee Rowe data

International Nuclear Information System (INIS)

1997-11-01

Safety analyses of criticality control systems for transportation packages include an assumption that the spent nuclear fuel (SNF) loaded into the package is fresh or unirradiated. In other words, the spent fuel is assumed to have its original, as-manufactured U-235 isotopic content. The ''fresh fuel'' assumption is very conservative since the potential reactivity of the nuclear fuel is substantially reduced after being irradiated in the reactor core. The concept of taking credit for this reduction in nuclear fuel reactivity due to burnup of the fuel, instead of using the fresh fuel assumption in the criticality safety analysis, is referred to as ''Burnup Credit.'' Burnup credit uses the actual physical composition of the fuel and accounts for the net reduction of fissile material and the buildup of neutron absorbers in the fuel as it is irradiated. Neutron absorbers include actinides and other isotopes generated as a result of the fission process. Using only the change in actinide isotopes in the burnup credit criticality analysis is referred to as ''Actinide-Only Burnup Credit.'' The use of burnup credit in the design of criticality control systems enables more spent fuel to be placed in a package. Increased package capacity results in a reduced number of storage, shipping and disposal containers for a given number of SNF assemblies. Fewer shipments result in a lower risk of accidents associated with the handling and transportation of spent fuel, thus reducing both radiological and nonradiological risk to the public. This paper describes the modeling and the results of comparison between measured and calculated isotopic inventories for a selected number of samples taken from a Yankee Rowe spent fuel assembly

Atomic Energy Act 1946

International Nuclear Information System (INIS)

1946-01-01

This Act provides for the development of atomic energy in the United Kingdom and for its control. It details the duties and powers of the competent Minister, in particular his powers to obtain information on and to inspect materials, plant and processes, to control production and use of atomic energy and publication of information thereon. Also specified is the power to search for and work minerals and to acquire property. (NEA) [fr

Compton scattering and electron-atom scattering in an elliptically polarized laser field of relativistic radiation power

International Nuclear Information System (INIS)

Panek, P.; Kaminski, J.Z.; Ehlotzky, F.

2003-01-01

Presently available laser sources can yield powers for which the ponderomotive energy of an electron U p can be equal to or even larger than the rest energy mc 2 of an electron. Therefore it has become of interest to consider fundamental radiation-induced or assisted processes in such powerful laser fields. In the present work we consider laser-induced Compton scattering and laser-assisted electron atom scattering in such fields, assuming that the laser beam has arbitrary elliptic polarization. We investigate in detail the angular and polarisation dependence of the differential cross-sections of the two laser-induced or laser-assisted nonlinear processes as a function of the order N of absorbed or emitted laser photons ω. The present work is a generalization of our previous analysis of Compton scattering and electron-atom scattering in a linearly polarized laser field. (authors)

Prospects and constraints in biofouling control at Madras Atomic Power Plant: a historical perspective

International Nuclear Information System (INIS)

Azariah, Jayapaul; Nair, K.V.K.

1995-01-01

The paper describes the various aspects of Madras Atomic Power Station -its prospects and constraints in biofouling control. It reviews the achievements in biofouling control. It also includes current studies on barnacles and mussels, suspended particulate matter as an antifoulant, flow conditions and larval settlement and biofilm and larval adhesion along with recommendations. (V.R.). 21 refs

Operating experience and performance at Narora Atomic Power Station

International Nuclear Information System (INIS)

Mittal, Subhash; Gupta, J.P.

1998-01-01

Narora Atomic Power Station consists of two units of 220 MWe capacity each. These are Pressurized Heavy Water Reactors, fuelled by natural uranium, moderated and cooled by heavy water. The Station is owned by Nuclear Power Corporation of India Ltd., which is responsible for design, construction, commissioning, and operation of all nuclear power stations in the country. NAPS was the first opportunity to apply operating experiences in design, keeping in view the evolving safety and seismicity requirements, ease of maintenance, inservice inspection needs, improved construction ability and standardization. Both the units of NAPS are having improved safety standards of current international levels. All the equipment are indigenous with improved quality and reliability. The first unit of the station went critical in March 1989 and synchronized to the grid in July 1989. The second units followed with its criticality in October 1991 and synchronization in January 1992. Considering the initial stabilizing period, the performance of both units of NAPS has progressively improved over the years. The annual capacity factor for NAPS - 1 was 90.01% and for NAPS - 2 was 89.01% for the financial year 1997-1998. This paper presents an analysis of the performance during the last three years and measures taken to improve it. The stated enhanced performance could be achieved by improvement in human performance by training/re-training, scrupulous monitoring and review of equipment/systems, institution of adequate procedure and ensuring their adherence. (authors)

Salient design features of secondary containment structure of Narora Atomic Power Project

International Nuclear Information System (INIS)

Rahalkar, B.D.

1975-01-01

Design of the secondary containment structure for Narora Atomic Power Project is an improvement over the two earlier structures at of Rajasthan and Kalpakkam wherein Candu-type of reactors are involved. The major improvements envisaged are : to limit the leakage through the double containment envelope to 0.1% of volume of the building per day as against 0.1% per hour achieved for earlier stations; to separate heavy water atmosphere from that of light water for effective heavy water recovery; and better man-rem budgetting by limiting inner containment structure upto boiler room floor level and making boiler room area accessible during normal operation for servicing of light water system equipment. Narora Atomic Power Station is located in the Indo-Gangetic alluvial plains in seismically active zone IV. Comprehensive soil investigation, including dynamic properties of soil is required to be undertaken as the foundation level of the containment structure is 17 M below the ground level. The salient results of this investigation relevant to the foundations as well as type of foundation proposed are presented in brief. Double containment concept similar to that adopted for Kalpakkam station is provided for this station also. However, necessary changes in design to withstand large earthquake forces are required to be made. These design problems are discussed in brief. (author)

Recurrent mass mortalities of the blueback herring, Alosa aestivalis, in the lower Connecticut River

International Nuclear Information System (INIS)

Moss, S.A.; Leggett, W.C.; Boyd, W.A.

1976-01-01

The authors studied 5 mass mortalities of blueback herring, Alosa aestivalis between 1965 and 1971. The reach of the Connecticut River in which the mortalities were observed includes the region thermally influenced by cooling water effluents from the Connecticut Yankee Atomic Power Plant. This warm water effluent has not been related to catastrophic blueback herring mortalities to the present time. The mortalities observed in 1965, 1966, and 1967 occurred before the plant became operational. The years of no abnormal mortalities, 1968, 1969, and 1970 coincided with periods of near-maximum generating output by this power plant. Only in June, 1971, did power plant operation coincide with a mass mortality of herring. Nevertheless, the occurrence of herring mortalities in four years out of seven observed suggests that further deterioration of water quality in the Connecticut River may threaten the continued spawning success of this fish. 9 references, 4 figures, 4 tables

Internal exposure profile of occupational workers of a BWR type atomic power station

International Nuclear Information System (INIS)

Hegde, A.G.; Bhat, I.S.

1979-01-01

The internal exposure profile of major radionuclides, for Tarapur Atomic Power Station (India) occupational staff for the last 9 years (1970-1978) of station operation, is presented. This power station has two boiling water reactor units. The occupational staff were monitored for internal exposure with the whole body counter. It has been observed that 60 Co, 134 Cs and 137 Cs are major contaminants. The highest yearly average of internal exposure was less than 1% of maximum permissible body burden recommended by ICRP. Depending on the nature of exposures the power station employees were classified under four different groups, (i) maintenance, (ii) operations, (iii) techanical and (iv) non-technical. This study revealed that maintenance group had highest incidence of internal exposure among these. It is also observed that contribution of 60 Co is maximum in the exposure of this group. (B.G.W.)

Nuclear power plant waste heat utilization

Energy Technology Data Exchange (ETDEWEB)

Ryther, J.H.; Huke, R.E.; Archer, J.C.; Price, D.R.; Jewell, W.J.; Hayes, T.D.; Witherby, H.R.

1977-09-01

The possibility of using Vermont Yankee condenser effluent for commercial food growth enhancement was examined. It was concluded that for the Vermont Yankee Nuclear Station, commercial success, both for horticulture and aquaculture endeavors, could not be assured without additional research in both areas. This is due primarily to two problems. First, the particularly low heat quality of our condenser discharge, being nominally 72 +- 2/sup 0/F; and second, to the capital intensive support systems. The capital needed for the support systems include costs of pumps, piping and controls to move the heated water to growing facilities and the costs of large, efficient heat exchangers that may be necessary to avoid regulatory difficulties due to the 1958 Delaney Amendment to the U.S. Food, Drug and Cosmetics Act. Recommendations for further work include construction of a permanent aquaculture research laboratory and a test greenhouse complex based on a greenhouse wherein a variety of heating configurations would be installed and tested. One greenhouse would be heated with biogas from an adjacent anaerobic digester thermally boosted during winter months by Vermont Yankee condenser effluent. The aquaculture laboratory would initially be dedicated to the Atlantic salmon restoration program. It appears possible to raise fingerling salmon to smolt size within 7 months using water warmed to about 60/sup 0/F. The growth rate by this technique is increased by a factor of 2 to 3. A system concept has been developed which includes an aqua-laboratory, producing 25,000 salmon smolt annually, a 4-unit greenhouse test horticulture complex and an 18,000 square foot commercial fish-rearing facility producing 100,000 pounds of wet fish (brook trout) per year. The aqualab and horticulture test complex would form the initial phase of construction. The trout-rearing facility would be delayed pending results of laboratory studies confirming its commercial viability.

Nuclear power plant waste heat utilization

International Nuclear Information System (INIS)

Ryther, J.H.; Huke, R.E.; Archer, J.C.; Price, D.R.; Jewell, W.J.; Hayes, T.D.; Witherby, H.R.

1977-09-01

The possibility of using Vermont Yankee condenser effluent for commercial food growth enhancement was examined. It was concluded that for the Vermont Yankee Nuclear Station, commercial success, both for horticulture and aquaculture endeavors, could not be assured without additional research in both areas. This is due primarily to two problems. First, the particularly low heat quality of our condenser discharge, being nominally 72 +- 2 0 F; and second, to the capital intensive support systems. The capital needed for the support systems include costs of pumps, piping and controls to move the heated water to growing facilities and the costs of large, efficient heat exchangers that may be necessary to avoid regulatory difficulties due to the 1958 Delaney Amendment to the U.S. Food, Drug and Cosmetics Act. Recommendations for further work include construction of a permanent aquaculture research laboratory and a test greenhouse complex based on a greenhouse wherein a variety of heating configurations would be installed and tested. One greenhouse would be heated with biogas from an adjacent anaerobic digester thermally boosted during winter months by Vermont Yankee condenser effluent. The aquaculture laboratory would initially be dedicated to the Atlantic salmon restoration program. It appears possible to raise fingerling salmon to smolt size within 7 months using water warmed to about 60 0 F. The growth rate by this technique is increased by a factor of 2 to 3. A system concept has been developed which includes an aqua-laboratory, producing 25,000 salmon smolt annually, a 4-unit greenhouse test horticulture complex and an 18,000 square foot commercial fish-rearing facility producing 100,000 pounds of wet fish (brook trout) per year. The aqualab and horticulture test complex would form the initial phase of construction. The trout-rearing facility would be delayed pending results of laboratory studies confirming its commercial viability

Atomic-powered democracy: Policy against politics in the quest for American nuclear energy

International Nuclear Information System (INIS)

Williams, R.W.

1993-01-01

This dissertation focuses on the relationship of American nuclear energy to democracy. It examines whether the nuclear policy processes have furthered the legitimacy-government accountability and citizen participation-which the democratic institutes are based. Nuclear policy and its institutions have placed severe limitations on democratic practices. Contravened democracy is seen most clearly in the decoupling of policy from politics. Decoupling refers to the weakening of institutional linkages between citizens and government, and to the erosion of the norms that ground liberal democracy. Decoupling is manifested in policy centralization, procedural biases, technical rationality, and the spatial displacement of conflict. Decoupling has normative implications: While federal accountability was limited and citizen participation was shackled, other major groups enjoyed privileged access to policy making. The decoupling of nuclear policy from politics arose within the context of US liberal-democratic capitalism. The federal government pursued its own goals of defense and world leadership. Yet, it was not structurally autonomous from the hegemony of the political-economic context. Economically, the Atomic Energy Act did not permit federal agencies to directly invest in power plant construction, and did not authorize them to commercially generate electricity. Private industry was structurally placed to domesticate the atom. Politically, the liberal-democratic system hampered an unquestioning pursuit of atomic energy. Federal institutions have been forced to heed some of the anti-nuclear concerns. The pervasive influence of the US political economy on nuclear policy has come to transgress democracy. Nuclear power's growth faltered during the 1970s. The political and economic constraints on federal actions have limited the means available to revive a becalmed nuclear industry; this has exerted strong pressure on federal institutions to decouple policy from participation

Review of the general atomic experimental fusion power reactor initial conceptual design

International Nuclear Information System (INIS)

Baker, C.C.; Sager, P.H. Jr.; Harder, C.R.

1976-01-01

The primary objective of the Experimental Power Reactor (EPR) is to provide the necessary interface between physics experiments and the first demonstration power plants. Since economically viable tokamak-type reactors may well have to be very high Q devices (ratio of fusion power out to power into the plasma), it will be essential for a tokamak demonstration reactor to operate at or near ignition conditions. Thus, it is believed that one of the primary objectives of the EPR must be to fully model the behavior of a D-T burning plasma required in the reactor of a demonstration plant. Therefore, a major objective of the EPR should be to achieve ignition conditions. In addition to demonstrating the ability to ignite and control a D-T plasma, it is also desirable that the EPR should produce, or at least demonstrate the ability to produce, a small amount of net electrical power. These objectives should be accomplished at a reasonable cost; this implies achieving a sufficiently high β (ratio of plasma pressure to magnetic field pressure). It is believed that noncircular cross section tokamaks offer the best chance of realizing these objectives. Consequently, noncircular cross sections are a major design feature of the General Atomic EPR

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)

Seismic re-evaluation of the Tarapur atomic power plants 1 and 2

International Nuclear Information System (INIS)

Ingole, S.M.; Kumar, B.S.; Gupta, S.; Singh, U.P.; Giridhar, K.; Bhawsar, S.D.; Samota, A.; Chhatre, A.G.; Dixit, K.B.; Bhardwaj, S.A.

2004-01-01

Two Boiling Water Reactors (BWR) of 210 MWe each at Tarapur Atomic Power Station, Units-1 and 2 (TAPS-1-2) were commissioned in the year 1969. The safety related civil structures at TAPS had been designed for a seismic coefficient of 0.2 g and other structures for 0.1 g. The work of seismic re-evaluation of the TAPS-1-2 has been taken up in the year 2002. As two new Pressurized Heavy Water Reactor (PHWR) plants of 540 MWe each, Tarapur Atomic Power Project Units-3 and 4 (TAPP-3-4), are coming up in the vicinity of TAPS-1-2, detailed geological and seismological studies of the area around TAPS-1-2 are available. The same free-field ground motion as generated for TAPP-3-4 has been used for TAPS-1-2. The seismic re-evaluation of the plant has been performed as per the procedure given in IAEA, Safety Reports Series entitled 'Seismic Evaluation of Existing Nuclear Power Plants', and meeting the various codes and standards, viz., ASME, ASCE, IEEE standards etc. The Safety Systems (SS) and Safety Support Systems (SSS) are qualified by adopting detailed analysis and testing methods. The equipment in the SS and SSS have been qualified by conducting a walk-down as per the procedure given in Generic Implementation Procedure, Dept. of Energy (GIP--DOE), USA. The safety systems include the systems required for safe shutdown of the plant, one chain of decay heat removal and containment of activity. The safety support systems viz., Electrical, Instrumentation and Control and systems other than SS and SSS have been qualified by limited analysis, testing and mostly by following the procedure of walk-down. The paper brings out the details of the work accomplished during seismic re-evaluation of the two units of BWR at Tarapur. (authors)

The contract of design of an atomic reactor system in Yonggwang - 5, 6 nuclear power plant

International Nuclear Information System (INIS)

1995-05-01

This is a contract of design of an atomic reactor system in Yonggwang 5, 6 nuclear power plant. It has the general contract condition. In the appendix, it indicates the detail regulations between two parties which are the coverage of division on the responsibility, schedule of the delivery, standard of the technology, guarantee, drawing and paper support of the Korea Electric Power Corporation, support of technology drill, test, regulations of code and standard and list of items and prices.

Prospects of nuclear power in Finland. A joint study by the IAEA and the Finnish Atomic Energy Commission

Energy Technology Data Exchange (ETDEWEB)

NONE

1960-12-01

Nuclear power is one of the most important practical applications of atomic energy and a major function of the Agency is to further its development. It became apparent in the Agency's early studies in this field that too often the economics of nuclear power were discussed in general terms and without reference to the multitude of conditions governing each specific power situation, which vary widely from country to country and even within a given country. It was also found that the few specific studies which existed had been carried out in countries where it had already been decided to establish a nuclear power station or even to embark on a full-scale nuclear power program. It was therefore considered that the prospects of nuclear power throughout the world could be realistically assessed only on the basis of a series of studies of as wide a range of different actual situations as possible. At its fourth regular session, the General Conference of the Agency adopted a resolution calling for the continuation of nuclear power surveys in Member States at their request. The Government of Finland invited the Agency to participate in a study of the prospects of nuclear power in Finland during the next decade. The desire of the Government of Finland was, on the one hand, to benefit from the specialized experience of the Agency, and on the other, to make a contribution to the Agency's program of furthering the development of nuclear power. We fully appreciate the value of this contribution and consider it very important for the Agency's program that this first nuclear power study has been undertaken together with a Member State which has long experience in conventional power planning and has consistently looked at nuclear power within the general context of the problem of meeting her growing power needs. The Board of Governors of the International Atomic Energy Agency approved the Agency's participation in the study and work began in March 1960. A joint study group was set

Prospects of nuclear power in Finland. A joint study by the IAEA and the Finnish Atomic Energy Commission

International Nuclear Information System (INIS)

1960-01-01

Nuclear power is one of the most important practical applications of atomic energy and a major function of the Agency is to further its development. It became apparent in the Agency's early studies in this field that too often the economics of nuclear power were discussed in general terms and without reference to the multitude of conditions governing each specific power situation, which vary widely from country to country and even within a given country. It was also found that the few specific studies which existed had been carried out in countries where it had already been decided to establish a nuclear power station or even to embark on a full-scale nuclear power program. It was therefore considered that the prospects of nuclear power throughout the world could be realistically assessed only on the basis of a series of studies of as wide a range of different actual situations as possible. At its fourth regular session, the General Conference of the Agency adopted a resolution calling for the continuation of nuclear power surveys in Member States at their request. The Government of Finland invited the Agency to participate in a study of the prospects of nuclear power in Finland during the next decade. The desire of the Government of Finland was, on the one hand, to benefit from the specialized experience of the Agency, and on the other, to make a contribution to the Agency's program of furthering the development of nuclear power. We fully appreciate the value of this contribution and consider it very important for the Agency's program that this first nuclear power study has been undertaken together with a Member State which has long experience in conventional power planning and has consistently looked at nuclear power within the general context of the problem of meeting her growing power needs. The Board of Governors of the International Atomic Energy Agency approved the Agency's participation in the study and work began in March 1960. A joint study group was set

Resonant charging and stopping power of slow channelling atoms in a crystalline metal

International Nuclear Information System (INIS)

Mason, D R; Race, C P; Foo, M H F; Horsfield, A P; Foulkes, W M C; Sutton, A P

2012-01-01

Fast moving ions travel great distances along channels between low-index crystallographic planes, slowing through collisions with electrons, until finally they hit a host atom initiating a cascade of atomic displacements. Statistical penetration ranges of incident particles are reliably used in ion-implantation technologies, but a full, necessarily quantum-mechanical, description of the stopping of slow, heavy ions is challenging and the results of experimental investigations are not fully understood. Using a self-consistent model of the electronic structure of a metal, and explicit treatment of atomic structure, we find by direct simulation a resonant accumulation of charge on a channelling ion analogous to the Okorokov effect but originating in electronic excitation between delocalized and localized valence states on the channelling ion and its transient host neighbours, stimulated by the time-periodic potential experienced by the channelling ion. The charge resonance reduces the electronic stopping power on the channelling ion. These are surprising and interesting new chemical aspects of channelling, which cannot be predicted within the standard framework of ions travelling through homogeneous electron gases or by considering either ion or target in isolation. (paper)

Allowable Residual Contamination Levels in soil for decommissioning the Shippingport Atomic Power Station site

International Nuclear Information System (INIS)

Kennedy, W.E. Jr.; Napier, B.A.; Soldat, J.K.

1983-09-01

As part of decommissioning the Shippingport Atomic Power Station, a fundamental concern is the determination of Allowable Residual Contamination Levels (ARCL) for radionuclides in the soil at the site. The ARCL method described in this report is based on a scenario/exposure-pathway analysis and compliance with an annual dose limit for unrestricted use of the land after decommissioning. In addition to naturally occurring radionuclides and fallout from weapons testing, soil contamination could potentially come from five other sources. These include operation of the Shippingport Station as a pressurized water reactor, operations of the Shippingport Station as a light-water breeder, operation of the nearby Beaver Valley reactors, releases during decommissioning, and operation of other nearby industries, including the Bruce-Mansfield coal-fired power plants. ARCL values are presented for 29 individual radionculides and a worksheet is provided so that ARCL values can be determined for any mixture of the individual radionuclides for any annual dose limit selected. In addition, a worksheet is provided for calculating present time soil concentration value that will decay to the ARCL values after any selected period of time, such as would occur during a period of restricted access. The ARCL results are presented for both unconfined (surface) and confined (subsurface) soil contamination. The ARCL method and results described in this report provide a flexible means of determining unrestricted-use site release conditions after decommissioning the Shippingport Atomic Power Station

The nuclear power safety programme of the International Atomic Energy Agency

International Nuclear Information System (INIS)

Rosen, M.

1981-01-01

The role of the International Atomic Energy Agency in the field of nuclear power safety is growing. In the period since the Three Mile Island accident, a significant expansion in its nuclear safety programme has taken place. To assure an acceptable safety level world-wide, new emphasis is being placed on the major effort to establish and foster the use of a comprehensive set of internationally agreed safety standards for nuclear power plants. New initiatives are in progress to intensify international co-operative safety efforts through the exchange of information on safety-related operating occurrences, and through a more open sharing of safety research results. Emergency accident assistance lends itself to international co-operation and steps are being taken to establish an emergency assistance programme so the Agency can aid in co-ordinating a timely response to provide, at short notice, help and advice in case of a nuclear power accident. There has been some strengthening of those advisory services which involve missions of international experts primarily to countries with less developed nuclear power programmes, and in conjunction with the Technical Assistance Programme there is a co-ordinated programme for developing countries, involving safety training courses and assistance aimed at promoting an effective national regulatory programme in all countries using nuclear power. This paper discusses the major features of the IAEA activities in nuclear power plant safety. An understanding of the programme and its limitations is essential to its more effective use. Additional initiatives may still be proposed, but the possibilities for international and regional co-operation to assure an adequate level of safety world-wide already exist. (author)

IAEA Leads Operational Safety Mission to Rajasthan Atomic Power Station 3 and 4

International Nuclear Information System (INIS)

2012-01-01

Full text: An international team of nuclear safety experts led by the International Atomic Energy Agency (IAEA) today completed a review of safety practices at Units 3 and 4 of the Rajasthan Atomic Power Station in Rawatbhata. The team noted a series of good practices and made recommendations and suggestions to reinforce safety practices. The IAEA assembled the Operational Safety Review Team (OSART) at the request of the Government of India. Led by the IAEA's Division of Nuclear Installation Safety, the team performed an in-depth operational safety review from 29 October to 14 November 2012. The team was comprised of experts from Canada, Belgium, Finland, Germany, Romania, Slovakia, Slovenia, Sweden and the IAEA. The team conducted an in-depth review of the aspects essential to the safe operation of the Power Plant. The conclusions of the review are based on the IAEA's Safety Standards and good international practices. The review covered the areas of Management, Organization and Administration; Training; Operations; Maintenance; Technical Support; Operating Experience; Radiation Protection; Chemistry; Emergency Planning and Preparedness; and Severe Accident Management. The OSART team identified a number of good practices of the plant. These will be shared in due course by the IAEA with the global nuclear industry for consideration. Examples include the following: - The Power Plant's safety culture cultivates a constructive work environment and a sense of accountability among the Power Plant personnel, and gives its staff the opportunity to expand skills and training; - The Power Plant's Public Awareness Programme provides educational opportunities to the local community about nuclear and radiation safety; - The Power Plant has a Management of Training and Authorization system for effective management of training activities; and - The Power Plant uses testing facilities and mockups to improve the quality of maintenance work and to reduce radiation doses. The OSART

The 2002 amendment to the German atomic energy act concerning the phase-out of nuclear power

International Nuclear Information System (INIS)

Vorwerk, A.

2002-01-01

The phase-out of the use of nuclear power for electricity production has now been legally regulated by the 2002 Atomic Energy Act, based on the Agreement between the German Government and the energy utilities. The provisions of this Act comply with constitutional and European law, and take account of Germany's international commitments. The new 2002 Atomic Energy Act is supplemented by additional steps towards the phase-out, in particular in the area of nuclear disposal. These steps are being taken primarily within the framework of a planned national disposal plan and a procedure to be enveloped for the selection of a location for a final disposal site for radioactive wastes. The key task for the Laender authorities and the Federal Ministry for the Environment, Nature Conservation and Nuclear Safety continues to be to ensure that operators of nuclear power plants comply with a high standard of safety during the residual operating periods of their plants. (author)

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.)

Atom dynamics in laser fields

International Nuclear Information System (INIS)

Jang, Su; Mi, No Gin

2004-12-01

This book introduces coherent dynamics of internal state, spread of atoms wave speed, semiclassical atoms density matrix such as dynamics equation in both still and moving atoms, excitation of atoms in movement by light, dipole radiating power, quantum statistical mechanics by atoms in movement, semiclassical atoms in movement, atoms in movement in the uniform magnetic field including effects of uniform magnetic field, atom cooling using laser such as Doppler cooling, atom traps using laser and mirrors, radiant heat which particles receive, and near field interactions among atoms in laser light.

Knolls Atomic Power Laboratory annual environmental monitoring report, calendar year 1997

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-12-31

The results of the effluent and environmental monitoring programs at the three Knolls Atomic Power Laboratory (KAPL) sites are summarized and assessed in this report. The effluent and environmental monitoring programs conducted by KAPL are designed to determine the effectiveness of treatment and control methods, to provide measurement of the concentrations in effluents for comparison with applicable standards, and to assess resultant concentrations in the environment. The monitoring programs include analyses of samples of liquid and gaseous effluents for chemical constituents and radioactivity as well as monitoring of environmental air, water, sediment, and fish. Radiation measurements are also made around the perimeter of each site and at off-site background locations.

Knolls Atomic Power Laboratory annual environmental monitoring report, calendar year 1997

International Nuclear Information System (INIS)

1997-01-01

The results of the effluent and environmental monitoring programs at the three Knolls Atomic Power Laboratory (KAPL) sites are summarized and assessed in this report. The effluent and environmental monitoring programs conducted by KAPL are designed to determine the effectiveness of treatment and control methods, to provide measurement of the concentrations in effluents for comparison with applicable standards, and to assess resultant concentrations in the environment. The monitoring programs include analyses of samples of liquid and gaseous effluents for chemical constituents and radioactivity as well as monitoring of environmental air, water, sediment, and fish. Radiation measurements are also made around the perimeter of each site and at off-site background locations

Refurbishment and replacement efforts to mitigate ageing at Tarapur Atomic Power Station - an overview

International Nuclear Information System (INIS)

Katiyar, S.C.; Thattey, V.; Das, P.K.

2006-01-01

Tarapur Atomic Power Station (TAPS) - a twin Boiling Water Reactor unit and India's first Atomic Power Station was commissioned in April 1969, and was declared commercial in November 1969. Since then the light water moderated, low enriched uranium BWR with its demonstrated reliability and favourable economics is playing a vital role as a reliable source of power for the states of Maharashtra and Gujarat. The Power Station played a key role as a technology demonstrator validating the nuclear energy as safe and environmentally benign and economically viable alternate source of power generation in India. Built in the late sixties with state-of-the-art safety features prevailing then, TAPS has further evolved to be a safe plant with renovation and refurbishment efforts. Ageing Management Programme is in place at TAPS. Identification of systems, structures and components (SSCs) important to safety and availability, assessment of ageing degradation of these SSCs and mitigation through repair, replacement and refurbishment based on the investigations have enhanced the plant safety and reliability. The station's operating experience and feedback from BWRs operating abroad have also given inputs to Ageing Management Programme. A good number of major equipment have been replaced to mitigate ageing. Primary system piping, process heat exchangers, feed water heaters, turbine extraction system piping, turbine blades, emergency condenser tube bundles, various pumps, station batteries, electrical cables, circuit breakers etc. are some of them. Obsolescence is another aspect of ageing of a plant. Replacement of obsolete equipment and components particularly in C and I is another area where much headway has been made. Replacement and refurbishment of equipment have been done after detailed study and analysis so that current standards are met. Retrofitting the indigenously developed and fabricated equipment in a compact plant like TAPS was a difficult task and required lot of

Genetic effects of prolonged combined irradiation of laboratory animals in Chernobyl Atomic Power Plant alienation zone

International Nuclear Information System (INIS)

Savtsova, Z.D.; Vojejkova, Yi.M.; Dzhaman, N.Yi.; Yudyina, O.Yu.; Yindik, V.M.; Kovbasyuk, S.A.

2000-01-01

Prolonged combined (external and internal) irradiation of mice in the r zone of the Chernobyl Atomic Power Plant caused hereditary disturbances physiological defects in the posterity irrespective of the fact if one or both parents were irradiated. The most favourable indices were observed in F2 posterity of the both exposed parents

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.)

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

International Nuclear Information System (INIS)

Bustard, Larry D.; Harrison, Dennis 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 co-sponsored 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 Yankees 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. These include (1) development of a methodology for identifying systems, structures, and components important to license renewal, (2) development of industry reports that describe industry-accepted approaches for license renewal of ten important classes of equipment, (3) development of technical basis to support license renewal, and (4) interaction/negotiation with the NRC through the Nuclear Management Resources Council (NUMARC) regarding appropriate regulatory requirements for license renewal. 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

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)

The future of nuclear power: Looking ahead. Address at the Japan Atomic Industrial Forum, Sendai, 12 April 1999

International Nuclear Information System (INIS)

ElBaradei, M.

1999-01-01

In his address at the Japan Atomic Industrial Forum (Sendai, 12 April 1999), the Director General of the IAEA described the role of the IAEA for nuclear power development, emphasizing the following aspects: nuclear power and the global energy mix, nuclear safety and the importance of public confidence, economic competitiveness and the role of research and development, and the importance of nuclear verification and prevention of illicit trafficking

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.)

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.

Atomic Information Technology Safety and Economy of Nuclear Power Plants

CERN Document Server

Woo, Taeho

2012-01-01

Atomic Information Technology revaluates current conceptions of the information technology aspects of the nuclear industry. Economic and safety research in the nuclear energy sector are explored, considering statistical methods which incorporate Monte-Carlo simulations for practical applications. Divided into three sections, Atomic Information Technology covers: • Atomic economics and management, • Atomic safety and reliability, and • Atomic safeguarding and security. Either as a standalone volume or as a companion to conventional nuclear safety and reliability books, Atomic Information Technology acts as a concise and thorough reference on statistical assessment technology in the nuclear industry. Students and industry professionals alike will find this a key tool in expanding and updating their understanding of this industry and the applications of information technology within it.

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

Atomic Energy Commission Act, 1963

International Nuclear Information System (INIS)

1963-01-01

Promulgated in 1963, the Atomic Energy Commission Act (204) established and vested in the Ghana Atomic Energy Commission the sole responsibility for all matters relating to the peaceful uses of atomic energy in the country. Embodied in the Act are provisions relating to the powers, duties, rights and liabilities of the Commission. (EAA)

Evolution of on-power refuelling system for 500 MWe PHWR based on experience from Rajasthan, Madras and Narora Atomic Power Stations

International Nuclear Information System (INIS)

Warrier, S.R.; Inder Jit; Sanatkumar, A.

1991-01-01

The on-power fuel handling system design at Rajasthan and Madras Atomic Power Stations (RAPS and MAPS) is essentially based on the design of the fuel handling system at Douglas Point Station (CANADA) Although, a number of improvements have been carried out in the fuel handling system of RAPS and MAPS at the component and sub-assembly level, some problems of repetitive nature like frequent deterioration in the performance of B-ram ball screw, leak detector solenoid valves etc., still exist. Further, there are certain limitations and drawbacks in the fuelling systems of these stations. For example, FM carriage design would not meet current seismic qualification standards. Also there are chances of fuel transfer room getting contaminated during movement of a failed fuel bundle. In order to obviate these deficiencies, a new concept has been worked out for the fuel handling system of Narora Atomic Power Station (NAPS) and accordingly, major changes have been made adopting a new layout. For example, FM head supporting arrangement has been changed to 'Suspension' type and a 'Linear-indexed' transfer magazine has been introduced in the fuel transfer system. Based on the experience gained from RAPS, MAPS and NAPS, design concept for 500 MWe fuel handling system has been evolved with further improvements especially in the layout. Also, a Calibration and Maintenance Facility for maintenance, testing calibration of FM head, sub-assemblies and components of fuel handling system has been introduced in the 500 MWe design. This paper discusses some of the experience gained from RAPS, MAPS and NAPS and also highlights the features of 500 MWe fuel handling system. (author)

High power atomic iodine photodissociation lasers

International Nuclear Information System (INIS)

Palmer, R.E.; Padrick, T.D.; Jones, E.D.

1976-01-01

The atomic iodine photodissociation laser has developed into a system capable of producing nanosecond or shorter pulses of near infrared radiation with energies well in excess of a hundred J. Discussed are the operating characteristics, advantages, and potential problem areas associated with this laser

LXII International conference NUCLEUS 2012. Fundamental problems of nuclear physics, atomic power engineering and nuclear technologies (LXII Meeting on nuclear spectroscopy and nuclear structure). Book of abstracts

International Nuclear Information System (INIS)

Vlasnikov, A.K.

2012-01-01

The scientific program of the conference covers almost all problems in nuclear physics and its applications. The recent results of experimental investigations of atomic nuclei properties and nuclear reaction mechanisms are presented. The theoretical problems of atomic nuclei and fundamental interactions as well as nuclear reactions are discussed. The new techniques and methods of nuclear physical experiments are considered. The particular attention is given to fundamental problems of nuclear power and qualitative training of russian and foreign specialist in field of nuclear physics and atomic power engineering [ru

The Future of Atomic Energy

Science.gov (United States)

Fermi, E.

1946-05-27

There is definitely a technical possibility that atomic power may gradually develop into one of the principal sources of useful power. If this expectation will prove correct, great advantages can be expected to come from the fact that the weight of the fuel is almost negligible. This feature may be particularly valuable for making power available to regions of difficult access and far from deposits of coal. It also may prove a great asset in mobile power units for example in a power plant for ship propulsion. On the negative side there are some technical limitations to be applicability of atomic power of which perhaps the most serious is the impossibility of constructing light power units; also there will be some peculiar difficulties in operating atomic plants, as for example the necessity of handling highly radioactive substances which will necessitate, at least for some considerable period, the use of specially skilled personnel for the operation. But the chief obstacle in the way of developing atomic power will be the difficulty of organizing a large scale industrial development in an internationally safe way. This presents actually problems much more difficult to solve than any of the technical developments that are necessary, It will require an unusual amount of statesmanship to balance properly the necessity of allaying the international suspicion that arises from withholding technical secrets against the obvious danger of dumping the details of the procedures for an extremely dangerous new method of warfare on a world that may not yet be prepared to renounce war. Furthermore, the proper balance should be found in the relatively short time that will elapse before the 'secrets' will naturally become open knowledge by rediscovery on part of the scientists and engineers of other countries.

Sandia high-power atomic iodine photodissociation laser

International Nuclear Information System (INIS)

Palmer, R.E.; Padrick, T.D.

1975-01-01

One of the more promising candidates for a laser to demonstrate the feasibility of laser fusion is the 1.315 μ atomic iodine laser. In a relatively short time it has been developed into a viable subnanosecond, high energy laser. Although at present the iodine laser cannot equal the output capabilities of a large Nd:glass laser system, there are no foreseeable obstacles in the construction of a 100 psec, 10 KJ or greater atomic iodine laser system. A 100 joule system being constructed at Sandia to investigate many of the scaling parameters essential to the design of a 10 KJ or greater system is described. (U.S.)

Knolls Atomic Power Laboratory environmental monitoring report, calendar year 1999

Energy Technology Data Exchange (ETDEWEB)

None

2000-12-01

The results of the effluent and environmental monitoring programs at the three Knolls Atomic Power Laboratory (KAPL) Sites are summarized and assessed in this report. Operations at the three KAPL Sites [Knolls Site, Niskayuna, New York; Kesselring Site, West Milton, New York; S1C Site, Windsor, Connecticut] during calendar year 1999 resulted in no significant release of hazardous substances or radioactivity to the environment. The effluent and environmental monitoring programs conducted by KAPL are designed to determine the effectiveness of treatment and control methods, to provide measurement of the concentrations in effluents for comparison with applicable standards, and to assess resultant concentrations in the environment. The monitoring programs include analyses of samples of liquid and gaseous effluents for chemical constituents and radioactivity as well as monitoring of environmental air, water, sediment, and fish. Radiation measurements are also made around the perimeter of each Site and at off-site background locations.

Knolls Atomic Power Laboratory environmental monitoring report, calendar year 1999

International Nuclear Information System (INIS)

2000-01-01

The results of the effluent and environmental monitoring programs at the three Knolls Atomic Power Laboratory (KAPL) Sites are summarized and assessed in this report. Operations at the three KAPL Sites [Knolls Site, Niskayuna, New York; Kesselring Site, West Milton, New York; S1C Site, Windsor, Connecticut] during calendar year 1999 resulted in no significant release of hazardous substances or radioactivity to the environment. The effluent and environmental monitoring programs conducted by KAPL are designed to determine the effectiveness of treatment and control methods, to provide measurement of the concentrations in effluents for comparison with applicable standards, and to assess resultant concentrations in the environment. The monitoring programs include analyses of samples of liquid and gaseous effluents for chemical constituents and radioactivity as well as monitoring of environmental air, water, sediment, and fish. Radiation measurements are also made around the perimeter of each Site and at off-site background locations

Condensing and water supplying systems in an atomic power plant

International Nuclear Information System (INIS)

Shinmura, Akira.

1975-01-01

Object: To reduce heat loss and eliminate accumulation of drain in water supplying and heating units in an atomic power plant by providing a direct contact type drain cooler between a gland-exhauster vapor condenser and a condensing and de-salting means, the drain from each water supplying and heating unit being collected in said cooler for heating the condensed water. Structure: Condensed water from a condenser is fed by a low pressure condensing pump through an air ejector and gland-exhauster vapor condenser to the direct-contact type drain cooler and is condensed in each water supply heater. Next, it is heated by drain fed through a drain level adjuster valve and an orifice and then forced by a medium pressure condenser pump into the condensing and de-salting means. It is then supplied by a high pressure condensing pump into the successive water supply heater. (Kamimura, M.)

Method for controlling a coolant liquid surface of cooling system instruments in an atomic power plant

International Nuclear Information System (INIS)

Monta, Kazuo.

1974-01-01

Object: To prevent coolant inventory within a cooling system loop in an atomic power plant from being varied depending on loads thereby relieving restriction of varied speed of coolant flow rate to lowering of a liquid surface due to short in coolant. Structure: Instruments such as a superheater, an evaporator, and the like, which constitute a cooling system loop in an atomic power plant, have a plurality of free liquid surface of coolant. Portions whose liquid surface is controlled and portions whose liquid surface is varied are adjusted in cross-sectional area so that the sum total of variation in coolant inventory in an instrument such as a superheater provided with an annulus portion in the center thereof and an inner cylindrical portion and a down-comer in the side thereof comes equal to that of variation in coolant inventory in an instrument such as an evaporator similar to the superheater. which is provided with an overflow pipe in its inner cylindrical portion or down-comer, thereby minimizing variation in coolant inventory of the entire coolant due to loads thus minimizing variation in varied speed of the coolant. (Kamimura, M.)

Microfabricated Waveguide Atom Traps.

Energy Technology Data Exchange (ETDEWEB)

Jau, Yuan-Yu [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2017-09-01

A nanoscale , microfabricated waveguide structure can in - principle be used to trap atoms in well - defined locations and enable strong photon-atom interactions . A neutral - atom platform based on this microfabrication technology will be prealigned , which is especially important for quantum - control applications. At present, there is still no reported demonstration of evanescent - field atom trapping using a microfabricated waveguide structure. We described the capabilities established by our team for future development of the waveguide atom - trapping technology at SNL and report our studies to overcome the technical challenges of loading cold atoms into the waveguide atom traps, efficient and broadband optical coupling to a waveguide, and the waveguide material for high - power optical transmission. From the atomic - physics and the waveguide modeling, w e have shown that a square nano-waveguide can be utilized t o achieve better atomic spin squeezing than using a nanofiber for first time.

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

Solar-simulator-pumped atomic iodine laser kinetics

Science.gov (United States)

Wilson, H. W.; Raju, S.; Shiu, Y. J.

1983-01-01

The literature contains broad ranges of disagreement in kinetic data for the atomic iodine laser. A kinetic model of a solar-simulator-pumped iodine laser is used to select those kinetic data consistent with recent laser experiments at the Langley Research Center. Analysis of the solar-simulator-pumped laser experiments resulted in the following estimates of rate coefficients: for alkyl radical (n-C3F7) and atomic iodine (I) recombination, 4.3 x 10 to the 11th power (1.9) + or - cu cm/s; for n-C3F7I stabilized atomic iodine recombination (I + I) 3.7 x 10 to the -32nd power (2.3) + or -1 cm to the 6th power/s; and for molecular iodine (I2) quenching, 3.1 x 10 to the -11th power (1.6) + or - 1 cu cm/s. These rates are consistent with the recent measurements.

Are atomic power plants saver than nuclear power plants

International Nuclear Information System (INIS)

Roeglin, H.C.

1977-01-01

It is rather impossible to establish nuclear power plants against the resistance of the population. To prevail over this resistance, a clarification of the citizens-initiatives motives which led to it will be necessary. This is to say: It is quite impossible for our population to understand what really heappens in nuclear power plants. They cannot identify themselves with nuclear power plants and thus feel very uncomfortable. As the total population feels the same way it is prepared for solidarity with the citizens-initiatives even if they believe in the necessity of nuclear power plants. Only an information-policy making transparent the social-psychological reasons of the population for being against nuclear power plants could be able to prevail over the resistance. More information about the technical procedures is not sufficient at all. (orig.) [de

Advances in atomic spectroscopy

CERN Document Server

Sneddon, J

2000-01-01

This fifth volume of the successful series Advances in Atomic Spectroscopy continues to discuss and investigate the area of atomic spectroscopy.It begins with a description of the use of various atomic spectroscopic methods and applications of speciation studies in atomic spectroscopy. The emphasis is on combining atomic spectroscopy with gas and liquid chromatography. In chapter two the authors describe new developments in tunable lasers and the impact they will have on atomic spectroscopy. The traditional methods of detection, such as photography and the photomultiplier, and how they are being replaced by new detectors is discussed in chapter three. The very active area of glow discharge atomic spectrometry is presented in chapter four where, after a brief introduction and historical review, the use of glow discharge lamps for atomic spectroscopy and mass spectrometry are discussed. Included in this discussion is geometry and radiofrequency power. The future of this source in atomic spectroscopy is also dis...

Long-range interactions among three alkali-metal atoms

International Nuclear Information System (INIS)

Marinescu, M.; Starace, A.F.

1996-01-01

The long-range asymptotic form of the interaction potential surface for three neutral alkali-metal atoms in their ground states may be expressed as an expansion in inverse powers of inter-nuclear distances. The first leading powers are proportional to the dispersion coefficients for pairwise atomic interactions. They are followed by a term responsible for a three body dipole interaction. The authors results consist in evaluation of the three body dipole interaction coefficient between three alkali-metal atoms. The generalization to long-range n atom interaction terms will be discussed qualitatively

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.

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

(Shippingport Atomic Power Station). Quarterly operating report, third quarter 1979

Energy Technology Data Exchange (ETDEWEB)

Jones, T. D.

1979-01-01

At the beginning of the third quarter of 1979, the Shippingport Atomic Power Station remained shutdown to complete repairs of the turbine generator hydrogen circulation fan following discovery of a rubbing noise on May 24, 1979. The Station was in a cooldown condition at approximately 180/sup 0/F and 300 psig with a steam bubble in the pressurizer and the reactor coolant pumps in slow speed. The reactor plant cooldown heat exchanger was in service to maintain coolant temperature. The 1A, 1B, 1C, and 1D reactor coolant loops and the 1AC and 1BD purification loops remained in service. All expended PWR Core 2 fuel elements have previously been shipped off-site. The remaining irradiated PWR Core 2 core barrel and miscellaneous refueling tools were in storage under shielding water in the deep pit of the Fuel Handling Building. The LWBR Core has generated 12,111.00 EFPH from startup through the end of the quarter.

Atomic switch: atom/ion movement controlled devices for beyond von-neumann computers.

Science.gov (United States)

Hasegawa, Tsuyoshi; Terabe, Kazuya; Tsuruoka, Tohru; Aono, Masakazu

2012-01-10

An atomic switch is a nanoionic device that controls the diffusion of metal ions/atoms and their reduction/oxidation processes in the switching operation to form/annihilate a conductive path. Since metal atoms can provide a highly conductive channel even if their cluster size is in the nanometer scale, atomic switches may enable downscaling to smaller than the 11 nm technology node, which is a great challenge for semiconductor devices. Atomic switches also possess novel characteristics, such as high on/off ratios, very low power consumption and non-volatility. The unique operating mechanisms of these devices have enabled the development of various types of atomic switch, such as gap-type and gapless-type two-terminal atomic switches and three-terminal atomic switches. Novel functions, such as selective volatile/nonvolatile, synaptic, memristive, and photo-assisted operations have been demonstrated. Such atomic switch characteristics can not only improve the performance of present-day electronic systems, but also enable development of new types of electronic systems, such as beyond von- Neumann computers. Copyright © 2012 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

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)

Atomic Australia: 1944-1990

International Nuclear Information System (INIS)

Cawte, Alice.

1992-01-01

This book tells how successive Australian governments pursued the elusive uranium dream. With Australian uranium committed to the West's atomic arsenals, Australia seemed set to become a nation powered by the atom. But by the mid-1950 the Australian government learnt that their expectations were premature, if not unrealistic. The background of the creation of the Australian Atomic Energy Commission is also given along with the examination of the uranium controversies of the 1970s and 1980s. 150 refs

The way that Ibaraki Prefecture has tackled atomic energy

International Nuclear Information System (INIS)

Nakata, Hirokatsu; Hirai, Yasuo; Tsuji, Tadashi.

1996-01-01

First, the development of the district centering around Tokai Village is mentioned, where at present Japan Atomic Energy Research Institute, Power Reactor and Nuclear Fuel Development Corporation, Japan Atomic Power Co. and others are located. Ibaraki Prefecture investigated the effects that atomic energy facilities exerted economically and socially to the district. As to the social environment investigation related to atomic energy facilities, its purpose, the objects of investigation, the contents and the method of investigation are reported. As to the progress of the development and utilization of atomic energy in Ibaraki Prefecture, 23 establishments are located in the district. Also there are 16 power reactors and research reactors, one fuel reprocessing plant, 4 nuclear fuel fabrication facilities, 86 nuclear fuel using facilities and 28 radioisotope using facilities. Their situations are reported. As to the atomic energy administration of Ibaraki Prefecture, the safety administration and the countermeasures for surrounding areas are explained. The effects exerted to the society and the economy of the district are reported. The results of the investigation of the conscience concerning atomic energy of residents are shown about energy and atomic energy, atomic energy administration, and the relation of atomic energy facilities with the district. (K.I.)

Long term plan of atomic energy development and utilization

International Nuclear Information System (INIS)

1982-01-01

The atomic energy utilization and development in Japan have progressed remarkably, and already nuclear power generation has borne an important part in electric power supply, while radiation has been utilized in the fields of industry, agriculture, medicine and so on. Now, atomic energy is indispensable for national life and industrial activity. The former long term plan was decided in September, 1978, and the new long term plan should be established since the situation has changed largely. The energy substituting for petroleum has been demanded, and the expectation to nuclear power generation has heightened because it enables stable and economical power supply. The independently developed technology related to atomic energy must be put in practical use. The peaceful utilization of atomic energy must be promoted, while contributing to the nuclear non-proliferation policy. The Atomic Energy Commission of Japan decided the new long term plan to clearly show the outline of the important measures related to atomic energy development and utilization in 10 years hereafter, and the method of its promotion. The basic concept of atomic energy development and utilization, the long term prospect and the concept on the promotion, the method of promoting the development and utilization, and the problems of funds, engineers and location are described. (kako, I.)

Radioactivity of food products in the region of the ''Kozloduj'' atomic power station in the pre-exploitation period

International Nuclear Information System (INIS)

Jotov, M.; Petkov, T.; Zlatanova, R.; Boyadzhiev, A.

1976-01-01

The pre-exploitation status of the region of the ''Kozloduj'' atomic power stationand its torch zone, regarding the concentration of the biologically most dangerous artificial isotopes in the basic food products was determined. The tested foods were milk, meat, wheat, fish and grapes produced at the most important and basic production regions in the controled region. The radioactive isotope concentrations in the analyzed food produxts are reported. They will serve as a basis in assessing any eventual additional contamination of the region as a result of the work of the ''Kozloduj'' electric power station. (author)

Analysis of containment venting for the Peach Bottom Atomic Power Station

International Nuclear Information System (INIS)

Hanson, D.J.; Wright, R.E.; Jenkins, J.P.

1986-01-01

The effectiveness of containment venting as a means of preventing or mitigating the consequences of severe accidents was evaluated for Peach Bottom Atomic Power Station Units 2 and 3 (BWR-4s with Mark I containments). Results from this evaluation indicate that the effectiveness of venting in preventing containment failure is highly dependent on the severe accident sequence. Containment venting can be effective for several classes of sequences, including loss-of-coolant accidents with breaks in the containment and transients with a failure of containment heat removal. However, based on draft procedures and equipment in place at the time of the evaluation, containment venting has limited potential for further reducing the risk associated with several sequences currently identified as significant contributors to risk. Means of improving the potential for risk reduction were identified, but their influence on risk was not analyzed

Nuclear power, nuclear fuel cycle and waste management, 1986-1999. International Atomic Energy Agency publications

International Nuclear Information System (INIS)

2000-04-01

This catalogue lists all sales publications of the International Atomic Energy Agency dealing with nuclear power and nuclear fuel cycle and waste management and issued during the period of 1986-1999. Some earlier titles which form part of an established series or are still considered of importance have been included. Most publications are in English. Proceedings of conferences, symposia and panels of experts may contain papers in languages other than English, but all of these papers have abstracts in English

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

Status of nuclear power in India

International Nuclear Information System (INIS)

Srinivasan, M.R.

1976-01-01

The article traces the history of Indian atomic energy programme and deals with the various nuclear power reactors operating commercially and under construction. Development of atomic energy in India is firmly committed to the installation of PHWR's as the mainstay of the country's immediate nuclear power programme. Indian nuclear power programme upto 1982 and major efforts at indigenisation, as reflected by the diminishing foreign exchange component in capital cost of different projects are discussed. Operational highlights of Tarapur atomic power station and Rajasthan atomic power station are reported. (S.K.K.)

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

The future of atomic energy; TOPICAL

International Nuclear Information System (INIS)

Fermi, E.

1946-01-01

There is definitely a technical possibility that atomic power may gradually develop into one of the principal sources of useful power. If this expectation will prove correct, great advantages can be expected to come from the fact that the weight of the fuel is almost negligible. This feature may be particularly valuable for making power available to regions of difficult access and far from deposits of coal. It also may prove a great asset in mobile power units for example in a power plant for ship propulsion. On the negative side there are some technical limitations to be applicability of atomic power of which perhaps the most serious is the impossibility of constructing light power units; also there will be some peculiar difficulties in operating atomic plants, as for example the necessity of handling highly radioactive substances which will necessitate, at least for some considerable period, the use of specially skilled personnel for the operation. But the chief obstacle in the way of developing atomic power will be the difficulty of organizing a large scale industrial development in an internationally safe way. This presents actually problems much more difficult to solve than any of the technical developments that are necessary, It will require an unusual amount of statesmanship to balance properly the necessity of allaying the international suspicion that arises from withholding technical secrets against the obvious danger of dumping the details of the procedures for an extremely dangerous new method of warfare on a world that may not yet be prepared to renounce war. Furthermore, the proper balance should be found in the relatively short time that will elapse before the 'secrets' will naturally become open knowledge by rediscovery on part of the scientists and engineers of other countries

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

Salmon River Habitat Enhancement, 1989 Annual Report.

Energy Technology Data Exchange (ETDEWEB)

Rowe, Mike

1989-04-01

This project was funded by the Bonneville Power Administration (BPA). The annual report contains three individual subproject papers detailing tribal fisheries work completed during the summer and fall of 1989. Subproject 1 contains summaries of evaluation/monitoring efforts associated with the Bear Valley Creek, Idaho enhancement project. Subproject 2 contains an evaluation of the Yankee Fork of the Salmon River habitat enhancement project. This report has been sub-divided into two parts: Part 1; stream evaluation and Part 2; pond series evaluation. Subproject 3 concerns the East Fork of the Salmon River, Idaho. This report summarizes the evaluation of the project to date including the 1989 pre-construction evaluation conducted within the East Fork drainage. Dredge mining has degraded spawning and rearing habitat for chinook salmon and steelhead trout in the Yankee Fork drainage of the Salmon River and in Bear Valley Creek. Mining, agricultural, and grazing practices degraded habitat in the East Fork of the Salmon River. Biological monitoring of the success of habitat enhancement for Bear Valley Creek and Yankee Fork are presented in this report. Physical and biological inventories prior to habitat enhancement in East Fork were also conducted. Four series of off-channel ponds of the Yankee Fork are shown to provide effective rearing habitat for chinook salmon. 45 refs., 49 figs., 24 tabs.

The exhibition Lumiere d'Atomes (Atoms light)

International Nuclear Information System (INIS)

Foos, Jacques

1995-01-01

Full text: This exhibition has been conceived in order to show for everybody, whatever his scientific level, the peaceful uses of transformations (natural or made by Man) and energetic possibilities of the atomic nucleus. The key-ideas of this exhibition were-: - nuclear applications a world of high technology; - nuclear industry men as the others; - nuclear energy an energetic independence. 6 themes were proposed: 1- Atoms and radioactivity; 2- The nuclear power stations; 3- The nuclear fuel cycle; 4- Surety and environment; 5- The other uses of radioactivity; 6- The French choice: The world nuclear data. This exhibition that comprises information posters, paintings, demonstration models, films and video games, was shown for the first time in Paris in april 1991. From this time, it was shown in many regional cities, with the help of SFEN members. 'Lumiere d'Atomes' received in 1991 the SFEN prize for its information on nuclear energy. (author)

An atomic empire a technical history of the rise and fall of the British atomic energy programme

CERN Document Server

Hill, C N

2013-01-01

Britain was the first country to exploit atomic energy on a large scale, and at its peak in the mid-1960s, it had generated more electricity from nuclear power than the rest of the world combined.The civil atomic energy programme grew out of the military programme which produced plutonium for atomic weapons. In 1956, Calder Hall power station was opened by the Queen. The very next year, one of the early Windscale reactors caught fire and the world's first major nuclear accident occurred.The civil programme ran into further difficulty in the mid-1960s and as a consequence of procrastination in

White paper on atomic energy in 1979

International Nuclear Information System (INIS)

1980-01-01

In Japan, there are currently 21 nuclear power plants in operation with a total capacity of 15,000MW. Under the present situation of the so-called second energy crisis, the role of nuclear power is assuming increasingly more importance. The white paper is presented covering the one year period from October 1978; statistics, however, are for fiscal 1978. Contents are the following: part I general ''world nuclear power situation, advances in nuclear energy, the outlook for 1980s''; part II the status of nuclear power ''nuclear power generation, nuclear power safety, nuclear fuel cycle, international activities, safeguards, development of power reactors, nuclear fusion/nuclear powered ship/high-temperature gas cooled reactor, radiation utilization, basic research, nuclear power industry''; part III references (organization/plans of Atomic Energy Commission etc., atomic energy budgets, nuclear energy statistics, etc.). (J.P.N.)

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

Shippingport Atomic Power Station Operating Experience, Developments and Future Plans

International Nuclear Information System (INIS)

Feinroth, H.; Oldham, G.M.; Stiefel, J.T.

1963-01-01

This paper describes and evaluates five years of operation and test of the Shippingport Atomic Power Station and discusses the current technical developments and future plans of the Shippingport programme. This programme is directed towards development of the basic technology of light-water reactors to provide the basis for potential reduction in the costs of nuclear power. The Shippingport reactor plant has operated for over five years and has been found to integrate readily into a utility system either as a base load or peak load unit. Plant component performance has been reliable. There have been no problems in contamination or waste disposal. Access to primary coolant components for maintenance has been good, demonstrating the integrity of fuel elements. Each of the three refuelling operations performed since start-up of Shippingport has required successively less time to accomplish. Recently, the third seed was refuelled in 32 working days, about one quarter the time required for the first refuelling. The formal requirements of personnel training, written administrative procedures, power plant manuals, etc., which have been a vital factor in the successful implementation of the Shippingport programme, are described. The results obtained from the comprehensive test programme carried out at Shippingport are compared with calculations, and good agreement has been obtained. Reactor core performance, plant stability, and response to load changes, fuel element and control rod performance, long-term effects such as corrosion and radiation level build-up, component performance, etc., are discussed in this paper. The principal objective of the current and future programmes of the Shippingport Project in advancing the basic technology of water-cooled reactors is discussed. This programme includes the continued operation of the Shippingport plant, and the development, design, manufacture and test operation of a long-life, highpower density second core - Core 2. At its

Experience of remote under water handling operations at Tarapur Atomic Power Station

International Nuclear Information System (INIS)

Agarwal, S.K.

1990-01-01

Each Refuelling outage of Tarapur Atomic Power Station Reactors involves a great deal of remote underwater handling operations using special remote handling tools, working deep down in the reactor vessel under about sixty feet of water and in the narrow confines of highly radioactive core. The remote underwater handling operations include incore and out of core sipping operations, fuel reloading or shuffling, uncoupling of control rod drives, replacement and shuffling of control blades, replacement of local power range monitors, spent fuel shipment in casks, retrieval of fallen or displaced fuel top guide spacers, orifices and their installation, underwater CCTV inspection of reactor internals, core verification, channelling and dechannelling of fuel bundles, inspection of fuel bundles and channels, unbolting and removal of old racks, installation of high density racks, removal and reinstallation of fuel support plugs and guide tubes, underwater cutting of irradiated hardware material and their disposal, fuel reconstitution, removal and reinstallation of system dryer separator etc.. The paper describes in brief the salient experience of remote underwater handling operations at TAPS especially the unusual problems faced and solved, by using special tools, employing specific techniques and by repeated efforts, patience, ingenuity and skills. (author). 10 figs

Production and quality control of concrete for the Rajasthan Atomic Power Station - [Part 2

International Nuclear Information System (INIS)

Singh Roy, P.K.; Sukhtankar, K.D.; Prasad, K.

1975-01-01

The following aspects of the production and quality control of concrete and concrete materials used in the construction of twin-reactor Rajasthan Atomic Power Station are discussed : (1) relationship between strength of cubes and cylinders made of concrete used for the prestressed dome (2) temperature control during pouring of concrete (3) thermal conductivity of heavy concrete (4) various types of grouting procedures used for different structures forming part of reactors (5) quality control of normal and heavy concrete and (6) leakage through form ties. Typical concrete mixes used for grouts are also given. (M.G.B.)

Atomic stopping-power problems encountered in measurements of nuclear γ-ray lifetimes by the Doppler-shift-attenuation method

International Nuclear Information System (INIS)

Latta, B.M.; Scanlon, P.J.

1976-01-01

The value of the nuclear lifetime of the 3.34-MeV level in 22 Ne as determined by Broude et al. by the Doppler shift attenuation method exhibits variations depending on the atomic number Z 2 of the slowing down medium. The lifetime has been re-evaluated within the framework of the Lindhard-Winther stopping theory, assuming a simple approximate form for the density of electrons associated with an atom in a solid and an effective point charge for the projectile based on experimental stopping powers. Although there are still variations in the value of the lifetime the variations appear to be systematic through the region of the transition elements. (Auth.)

Optical lattice on an atom chip

DEFF Research Database (Denmark)

Gallego, D.; Hofferberth, S.; Schumm, Thorsten

2009-01-01

Optical dipole traps and atom chips are two very powerful tools for the quantum manipulation of neutral atoms. We demonstrate that both methods can be combined by creating an optical lattice potential on an atom chip. A red-detuned laser beam is retroreflected using the atom chip surface as a high......-quality mirror, generating a vertical array of purely optical oblate traps. We transfer thermal atoms from the chip into the lattice and observe cooling into the two-dimensional regime. Using a chip-generated Bose-Einstein condensate, we demonstrate coherent Bloch oscillations in the lattice....

Analysis of containment venting at the Peach Bottom Atomic Power Station

International Nuclear Information System (INIS)

Hanson, D.J.; Blackman, H.S.; Nelson, W.R.; Wright, R.E.; Leonard, M.T.; DiSalvo, R.

1986-01-01

An analysis of the extent to which containment venting would be effective in preventing or mitigating the consequences of severe accidents has been completed for the Peach Bottom Atomic Power Station, Units 2 and 3 (BWR-4s with Mark I containments). The analysis indicates that the effectiveness of venting in preventing containment overpressurization highly depends on the sequence of the severe accident. Containment venting can be effective for several classes of sequences, including transients with failure of long-term decay heat removal and loss-of-coolant accidents with breaks inside the containment. However, based on draft procedures and equipment in place at the time of the evaluation, containment venting has limited potential for further reducing the risk associated with three severe accident sequences currently identified as important risk contributors at Peach Bottom. Means of improving the potential for risk reduction is identified, but their influence on risk is not analyzed

Installation of the Light-Water Breeder Reactor at the Shippingport Atomic Power Station (LWBR Development Program)

International Nuclear Information System (INIS)

Massimino, R.J.; Williams, D.A.

1983-05-01

This report summarizes the refueling operations performed to install a Light Water Breeder Reactor (LWBR) core into the existing pressurized water reactor vessel at the Shippingport Atomic Power Station. Detailed descriptions of the major installation operations (e.g., primary system preconditioning, fuel installation, pressure boundary seal welding) are included as appendices to this report; these operations are of technical interest to any reactor servicing operation, whether the reactor is a breeder or a conventional light water non-breeder core

Installation of the Light-Water Breeder Reactor at the Shippingport Atomic Power Station (LWBR Development Program)

Energy Technology Data Exchange (ETDEWEB)

Massimino, R.J.; Williams, D.A.

1983-05-01

This report summarizes the refueling operations performed to install a Light Water Breeder Reactor (LWBR) core into the existing pressurized water reactor vessel at the Shippingport Atomic Power Station. Detailed descriptions of the major installation operations (e.g., primary system preconditioning, fuel installation, pressure boundary seal welding) are included as appendices to this report; these operations are of technical interest to any reactor servicing operation, whether the reactor is a breeder or a conventional light water non-breeder core.

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.)

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.

Knolls Atomic Power Laboratory environmental monitoring report, calendar year 2000

International Nuclear Information System (INIS)

2001-01-01

The results of the effluent and environmental monitoring programs at the three Knolls Atomic Power Laboratory (KAPL) Sites are summarized and assessed in this report. Operations at the Knolls Site, Niskayuna, New York and the Kesselring Site, West Milton, New York and site closure activities at the S1C Site, Windsor, Connecticut, continued to have no adverse effect on human health and the quality of the environment during calendar year 2000. The effluent and environmental monitoring programs conducted by KAPL are designed to determine the effectiveness of treatment and control methods, to provide measurement of the concentrations in effluents for comparison with applicable standards, and to assess resultant concentrations in the environment. The monitoring programs include analyses of samples of liquid and gaseous effluents for chemical constituents and radioactivity as well as monitoring of environmental air, water, sediment, and fish. Radiation measurements are also made around the perimeter of each Site and at off-site background locations. Monitoring programs at the S1C Site were reduced in scope during calendar year 2000 due to completion of site dismantlement activities during 1999

Knolls Atomic Power Laboratory environmental monitoring report, calendar year 2000

Energy Technology Data Exchange (ETDEWEB)

None

2001-12-01

The results of the effluent and environmental monitoring programs at the three Knolls Atomic Power Laboratory (KAPL) Sites are summarized and assessed in this report. Operations at the Knolls Site, Niskayuna, New York and the Kesselring Site, West Milton, New York and site closure activities at the S1C Site, Windsor, Connecticut, continued to have no adverse effect on human health and the quality of the environment during calendar year 2000. The effluent and environmental monitoring programs conducted by KAPL are designed to determine the effectiveness of treatment and control methods, to provide measurement of the concentrations in effluents for comparison with applicable standards, and to assess resultant concentrations in the environment. The monitoring programs include analyses of samples of liquid and gaseous effluents for chemical constituents and radioactivity as well as monitoring of environmental air, water, sediment, and fish. Radiation measurements are also made around the perimeter of each Site and at off-site background locations. Monitoring programs at the S1C Site were reduced in scope during calendar year 2000 due to completion of site dismantlement activities during 1999.

Monitoring of atmospheric 3H around Narora Atomic Power Station

International Nuclear Information System (INIS)

Gautam, Y.P.; Sharma, A.K.; Sharma, S.; Rao, K.S.; Kumar, J.; Kumar, V.; Singh, B.; Kumar, A.; Hedge, A.G.

2010-01-01

Atmospheric tritium activity is measured regularly around Narora Atomic Power Station (NAPS) since gaseous waste, which contains tritium, is being released through a 145 m high stack at NAPS site. Atmospheric data collected during 2004-2008 shows a large variation of 3 H concentration in air, fluctuating in the range of ≤0.2-91.6 Bq m -3 . Significantly, higher tritium levels were measured in samples near the site boundary (1.6 km) of NAPS compared to off-site locations. The atmospheric dilution factor was found to be in the range of 1.1 x 10 -7 -7.3 x 10 -7 s m -3 . The scavenging ratio of NAPS site was found to be varying from 0.2 x 10 4 to 14.1 x 10 4 (Bq m -3 rain water per Bq m -3 air). The inhalation dose to a member of general public at different distances (1.6-30 km) from NAPS site was found to be ranged from 0.08-0.21 μSv year -1 . (author)

Commissioning and operation of distillation column at Madras Atomic Power Station (Paper No. 1.10)

International Nuclear Information System (INIS)

Neelakrishnan, G.; Subramanian, N.

1992-01-01

In Madras Atomic Power Station (MAPS), an upgrading plant based on vacuum distillation was constructed to upgrade the downgraded heavy water collected in vapor recovery dryers. There are two distillation columns and each having a capacity of 77.5 tonne per annum of reactor grade heavy water with average feed concentration of 30% IP. The performance of the distillation columns has been very good. The column I and column II have achieved an operating factor of 92% and 90% respectively. The commissioning activities, and subsequent improvements carried out in the distillation columns are described. (author)

Quantitative evaluation of the fault tolerance of systems important to the safety of atomic power plants

International Nuclear Information System (INIS)

Malkin, S.D.; Sivokon, V.P.; Shmatkova, L.V.

1989-01-01

Fault tolerance is the property of a system to preserve its performance upon failures of its components. Thus, in nuclear-reactor technology one has only a qualitative evaluation of fault tolerance - the single-failure criterion, which does not enable one to compare and perform goal-directed design of fault-tolerant systems, and in the field of computer technology there are no generally accepted evaluations of fault tolerance that could be applied effectively to reactor systems. This paper considers alternative evaluations of fault tolerance and a method of comprehensive automated calculation of the reliability and fault tolerance of complex systems. The authors presented quantitative estimates of fault tolerance that develop the single-failure criterion. They have limiting processes that allow simple and graphical standardization. They worked out a method and a program for comprehensive calculation of the reliability and fault tolerance of systems of complex structure that are important to the safety of atomic power plants. The quantitative evaluation of the fault tolerance of these systems exhibits a degree of insensitivity to failures and shows to what extent their reliability is determined by a rigorously defined structure, and to what extent by the probabilistic reliability characteristics of the components. To increase safety, one must increase the fault tolerance of the most important systems of atomic power plants

Atomic Energy Act 1953-1966

International Nuclear Information System (INIS)

1970-01-01

The Atomic Energy Act 1953-1966 establishes the Australian Atomic Energy Commission and lays down its powers, duties, rules of procedure and financing. The members of the Commission are appointed by the Governor-General. It is responsible, inter alia, for all activities covering uranium research, mining and trading as well as for atomic energy development and nuclear plant construction and operation. Its duties also include training of scientific research workers and collection and dissemination of information on atomic energy. For purposes of security, the Act further-more prescribes sanctions in relation to unauthorised acquisition or communication of information on this subject. Finally, the Act repeals the Atomic Energy (Control of Materials) Act 1946 and 1952. (NEA) [fr

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...

Atoms at work

International Nuclear Information System (INIS)

1982-07-01

This illustrated booklet discusses the following: atoms; fission of uranium; nuclear power plants; reactor types; plutonium (formation, properties, uses); radioactive waste (fuel cycle, reprocessing, waste management); nuclear fusion; fusion reactors; radiation; radioisotopes and their uses. (U.K.)

Design and analysis of reactor headers for Narora Atomic Power Project

International Nuclear Information System (INIS)

Danak, M.R.

1975-01-01

Reactor header for Narora Atomic Power Reactor is a 400 mm O.D. 10 metres long pressure vessel in the primary coolant circuit connecting 153 feeders to PHT pumps or steam generators. The vessel dimensions are restricted are by containment philosophy. The outlet connections for pumps or steam generators are to be of the size of vessel diameter and DO/t ratio for the vessel is approximately 10. The design and stresses induced meet the code requirements except that at times it is difficult to get precise stress values in absence of certain data and lack of code or available literature giving practical approach to the problem. It can be seen that the 400 mm equal tees used as part of the vessel cannot be penetrated in the light of code reinforcement requirements. However if the tees have to penetrated to retain established feeder layout, it should be established experimentally or by some detailed stress analysis that it will meet the intent of code. (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)

Safety evaluation report related to the operation of Enrico Fermi Atomic Power Plant, Unit No. 2. Docket No. 50-341

International Nuclear Information System (INIS)

1983-01-01

Supplement No. 3 to the Safety Evaluation Report related to the operation of the Enrico Fermi Atomic Power Plant, Unit 2, provides the staff's evaluation of additional information submitted by the applicant regarding outstanding review issues identified in Supplement No. 2 to the Safety Evaluation Report, dated January 1982

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)

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.

Dielectric barrier discharge plasma atomizer for hydride generation atomic absorption spectrometry—Performance evaluation for selenium

Energy Technology Data Exchange (ETDEWEB)

Duben, Ondřej [Institute of Analytical Chemistry of the CAS, v.v.i., Veveří 97, CZ-602 00 Brno (Czech Republic); Faculty of Science, Department of Analytical Chemistry, Charles University in Prague, Hlavova 8, Prague, CZ 128 43 Czech Republic (Czech Republic); Boušek, Jaroslav [Faculty of Electrical Engineering and Communications, Brno University of Technology, Technická 1058/10, 61600 Brno (Czech Republic); Dědina, Jiří [Institute of Analytical Chemistry of the CAS, v.v.i., Veveří 97, CZ-602 00 Brno (Czech Republic); Kratzer, Jan, E-mail: jkratzer@biomed.cas.cz [Institute of Analytical Chemistry of the CAS, v.v.i., Veveří 97, CZ-602 00 Brno (Czech Republic)

2015-09-01

Atomization of selenium hydride in a quartz dielectric barrier discharge (DBD) atomizer was optimized and its performance was compared to that of the externally heated quartz multiatomizer. Argon was found as the best DBD discharge gas employing a flow rate of 75 ml min{sup −1} Ar while the DBD power was optimized at 14 W. The detection limits reached 0.24 ng ml{sup −1} Se in the DBD and 0.15 ng ml{sup −1} Se in the multiatomizer. The tolerance of DBD to interferences is even better than with the multiatomizer. - Highlights: • SeH{sub 2} atomization in a dielectric barrier discharge (DBD) was optimized for AAS. • Atomizer performance was compared for DBD and externally heated quartz atomizer. • Detection limits were quantified and interferences were studied in both atomizers. • Atomization efficiency in the DBD was estimated.

Controlling the atom

International Nuclear Information System (INIS)

Mazuzan, G.T.; Walker, J.S.

1984-01-01

The authors trace the early history of nuclear power regulation in the US. Focusing on the Atomic Energy Commission, they describe the role of other groups that figured in the development of regulatory policies, including the Congressional Joint Committee on Atomic Energy, other federal agencies, state governments, the nuclear industry, and scientific organizations. They consider changes in public perceptions of and attitudes toward atomic energy and the dangers of radiation exposure. The basic purpose of the book is to provide the Nuclear Regulatory Commission and the general public with information on the historical antecedents and background of regulatory issues so that there will be continuity in policy decisions. The book concludes with an annotated bibliography of selected references. 19 figures

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

Report of fact-finding survey for atomic energy in dustry, fiscal 1995

International Nuclear Information System (INIS)

1996-12-01

Japanese economy in fiscal year 1995 progressed with the tendency of gradual business recovery, and the real rate of economic growth was 2.4%. The final energy consumption has become the growth rate of 3.2% as compared with that in the previous year. Classifying by energy supply sources, the share of petroleum was 55.8% which was slight decrease, and nuclear power has become 12%, the highest so far. The share of coal was 16.5%, natural gas 10.8%, and water power 3.5%. Total supply of primary energy increased by 1.9%, and the demand of electric power increased by 1.6% as compared with those in the previous year. As for the circumstances of atomic energy industries in fiscal year 1995, the outlay related to atomic energy of electric power industry decreased sharply by about 13%, while the sales related to atomic energy of mining and manufacturing industries turned to the increase by about 5%. The outlay related to atomic energy of mining and manufacturing industries decreased by 8% as compared with that in the previous year. As the perspective for future, the outlay related to atomic energy of electric power industry is expected to increase. The total number of the persons who engage in private atomic energy enterprises was 60,540. The average capacity factor of 49 nuclear power plants in operation was 80.2%. The share of nuclear power taken in total generated electric power was 33.8%. Four nuclear power plants were under construction as of the end of fiscal year 1995. (K.I.)

Considerations in the evaluation of concrete structures for continued service in aged Nuclear Power Plants (NPPs)

International Nuclear Information System (INIS)

Naus, D.; Marchbanks, M.; Oland, B.; Arndt, G.; Brown, T.

1989-01-01

Currently, there are /approximately/119 commercial nuclear power plants (NPPs) in the US either under construction, operating at low-to-full power, or awaiting an operating license. Together, these units have a net generating capacity of /approximately/110 GW(e). Assuming no life extension of present facilities, the operating licenses for these plants will start to expire in the middle of the next decade with Yankee Rowe being the first plant to attain this status. Where it is noted that with no life extension of facilities, a potential loss of electrical generating capacity in excess of 75 GW(e) could occur during the time period 2006 to 2020 when the operating licenses of 80 to 90 NPPs are scheduled to expire. A potential timely and cost-effective solution to meeting future electricity demand, which has worked well for non-nuclear generating plants, is to extend the service life (operating licenses) of existing NPPs. Since the concrete components in these plants provide a vital safety function, any continued service considerations must include an in-depth assessment of the safety-related concrete structures. 7 refs

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.)

Atoms for peace: thirtieth anniversary

International Nuclear Information System (INIS)

Ramey, J.T.

1983-01-01

This paper was prepared for the thirtieth anniversary of President Eisenhower's programme: ''Atoms for Peace''. The author wants to demonstrate that nuclear power has made major contributions to reduction of oil imports and that at the same time, despite repeated predictions of unbridled proliferation, the fact is that proliferation has proceeded at a dramatically slower pace than foreseen by some. To date no country has employed plutonium derived from the nuclear power fuel cycle to initiate its nuclear explosion program. The author concludes that the ''Atoms for Peace'' programme, from the viewpoint of its goal of reducing the spread of nuclear weapons, has been a successful policy. (NEA) [fr

Atomic Energy Authority Act 1954

International Nuclear Information System (INIS)

1954-01-01

This Act provides for the setting up of an Atomic Energy Authority for the United Kingdom. It also makes provision for the Authority's composition, powers, duties, rights and liabilities, and may amend, as a consequence of the establishment of the Authority and in connection therewith, the Atomic Energy Act, 1946, the Radioactive Substances Act 1948 and other relevant enactments. (NEA) [fr

1989 basic plan for atomic energy development and utilization

International Nuclear Information System (INIS)

1989-01-01

A Basic Plan for Atomic Energy Development and Utilization has been established each year based on the guidelines set up by the Atomic Energy Commission of Japan, with the aim of promoting the development and utilization of atomic energy schematically and efficiently. The Basic Plan shows specific projects to achieve the objectives specified in the Long-Range Plan for Atomic Energy Development and Utilization. The Basic Plan specifies efforts to be made for overall strengthening of safety measures (safety policies, safety research, disaster prevention, etc.), promotion of nuclear power generation, establishment of the nuclear fuel cycle (securing of uranium, technology for uranium enrichment, reprocessing, etc.), development of new types of power reactors (fast breeder reactor, new types of converter reactors, plutonium fuel processing technology), promotion of leading projects (nuclear fusion, utilization of radiations, atomic powered ships, high-temperature engineering tests), promotion of basic technology development (basic research, training of scientists and engineers), voluntary and active international activities (international cooperation), and acquisition of understanding and cooperation of the general public. (N,K.)

Marine biofouling and its implications in the use of seawater as a heat transfer fluid in Madras Atomic Power Station

International Nuclear Information System (INIS)

Nair, K.V.K.; Venugopalan, V.P.

1996-01-01

Even though the problem of fouling is quite severe in the tropics because of rich diversity of species and longer periods available for breeding activity, most of the literature is from the temperate waters. In this paper, an attempt is made to illustrate the potential of biofouling to compromise the economical operation of coastal power plants by taking Madras Atomic Power Station (MAPS) as an example. The significance of acquiring information on biological aspects of the fouling species in successfully combating the problems is also highlighted. 3 refs., 3 tabs., 1 fig

Nuclear power for beginners

International Nuclear Information System (INIS)

Croall, S.; Sempler, K.

1979-01-01

Witty, critically, and with expert knowledge, 'Atomic power for beginners' describes the development of nuclear power for military purposes and its 'peaceful uses' against the will of the population. Atomic power, the civil baby of the bomb is not only a danger to our lives - it is enemy to all life as all hard technologies are on which economic systems preoccupied with growth put their hopes. Therefore, 'Atomic power for beginners' does not stop at nuclear engineering but proceeds to investigate its consequences, nationally and with a view to the Third World. And since the consequences are so fatal and it is not enough to say no to nuclear power, it gives some thoughts to a better future - with soft technology and alternative production. (orig.) 891 HP/orig. 892 MKO [de

Knolls Atomic Power Laboratory environmental monitoring report, calendar year 2001

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-12-31

The results of the effluent and environmental monitoring programs at the three Knolls Atomic Power Laboratory (KAPL) Sites are summarized and assessed in this report. Operations at the Knolls and Kesselring Sites and Site closure activities at the S1C Site (also known as the KAPL Windsor Site) continue to have no adverse effect on human health and the quality of the environment. The effluent and environmental monitoring programs conducted by KAPL at the Knolls and Kesselring Sites are designed to determine the effectiveness of treatment and control methods, to provide measurement of the concentrations in effluents for comparison with applicable standards, and to assess resultant concentrations in the environment. The monitoring programs include analyses of samples of liquid and gaseous effluents for chemical constituents and radioactivity as well as environmental monitoring of air, water, sediment, and fish. Radiation measurements are also made around the perimeter of the Knolls and Kesselring Sites and at off-site background locations. The environmental monitoring program for the S1C Site continues to be reduced in scope from previous years due to the completion of Site dismantlement activities during 1999 and a return to green field conditions during 2000.

Knolls Atomic Power Laboratory environmental monitoring report, calendar year 2001

International Nuclear Information System (INIS)

2002-01-01

The results of the effluent and environmental monitoring programs at the three Knolls Atomic Power Laboratory (KAPL) Sites are summarized and assessed in this report. Operations at the Knolls and Kesselring Sites and Site closure activities at the S1C Site (also known as the KAPL Windsor Site) continue to have no adverse effect on human health and the quality of the environment. The effluent and environmental monitoring programs conducted by KAPL at the Knolls and Kesselring Sites are designed to determine the effectiveness of treatment and control methods, to provide measurement of the concentrations in effluents for comparison with applicable standards, and to assess resultant concentrations in the environment. The monitoring programs include analyses of samples of liquid and gaseous effluents for chemical constituents and radioactivity as well as environmental monitoring of air, water, sediment, and fish. Radiation measurements are also made around the perimeter of the Knolls and Kesselring Sites and at off-site background locations. The environmental monitoring program for the S1C Site continues to be reduced in scope from previous years due to the completion of Site dismantlement activities during 1999 and a return to green field conditions during 2000

Knolls Atomic Power Laboratory environmental monitoring report, calendar year 1996

International Nuclear Information System (INIS)

1996-01-01

The results of the effluent and environmental monitoring programs at the three Knolls Atomic Power Laboratory (KAPL) sites are summarized and assessed in this report. The principal function at KAPL sites (Knolls, Kesselring, and Windsor) is research and development in the design and operation of Naval nuclear propulsion plants. The Kesselring Site is also used for the training of personnel in the operation of these plants. The Naval nuclear propulsion plant at the Windsor Site is currently being dismantled. Operations at the three KAPL sites resulted in no significant release of hazardous substances or radioactivity to the environment. The effluent and environmental monitoring programs conducted by KAPL are designed to determine the effectiveness of treatment and control methods, to provide measurement of the concentrations in effluents for comparison with applicable standards, and to assess resultant concentrations in the environment. The monitoring programs include analyses of samples of liquid and gaseous effluents for chemical constituents and radioactivity as well as monitoring of environmental air, water, sediment, and fish. Radiation measurements are also made around the perimeter of each site and at off-site background locations

Knolls Atomic Power Laboratory environmental monitoring report, calendar year 1996

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-12-31

The results of the effluent and environmental monitoring programs at the three Knolls Atomic Power Laboratory (KAPL) sites are summarized and assessed in this report. The principal function at KAPL sites (Knolls, Kesselring, and Windsor) is research and development in the design and operation of Naval nuclear propulsion plants. The Kesselring Site is also used for the training of personnel in the operation of these plants. The Naval nuclear propulsion plant at the Windsor Site is currently being dismantled. Operations at the three KAPL sites resulted in no significant release of hazardous substances or radioactivity to the environment. The effluent and environmental monitoring programs conducted by KAPL are designed to determine the effectiveness of treatment and control methods, to provide measurement of the concentrations in effluents for comparison with applicable standards, and to assess resultant concentrations in the environment. The monitoring programs include analyses of samples of liquid and gaseous effluents for chemical constituents and radioactivity as well as monitoring of environmental air, water, sediment, and fish. Radiation measurements are also made around the perimeter of each site and at off-site background locations.

Earthworm populations in soils contaminated by the Chernobyl atomic power station accident, 1986-1988

International Nuclear Information System (INIS)

Krivolutzkii, D.A.; Pokarzhevskii, A.D.; Viktorov, A.G.

1992-01-01

A study of earthworm populations in the 30 km zone around the Chernobyl atomic power station was carried out in 1986-1988. Significant differences in earthworm population numbers were found between highly contaminated and control plots in summer and autumn 1986 and in April 1987. But in the autumn of 1988 the earthworm population numbers in contaminated plots were higher than in the control plots. The ratio of mature to immature specimens was higher in 1986 in the contaminated plots in comparison with the control plots. Only one species of earthworms, Dendrobaena octahedra, was found in contaminated forest plots during the first 2 yr following the accident but in the control forest plots Apporectodea caliginosa was also found. (author)

Extreme value analysis of meteorological parameters observed during the period 1994-2001 at Kakrapar Atomic Power Station

International Nuclear Information System (INIS)

Ramkumar, S.; Dole, M.L.; Nankar, D.P.; Rajan, M.P.; Gurg, R.P.

2003-01-01

In the design of engineering structures, an understanding of extreme weather conditions that may occur at the site of interest is very essential, so that the structures can be designed to withstand such situations. In this report an analysis of extreme values of meteorological parameters observed at Kakrapar Atomic Power Station site for the period 1994 -2001 is described. The parameters considered are maximum and minimum air temperature, maximum wind speed and gust, and maximum rainfall in a month, in a day, in an hour and annual rainfall. The extreme value analysis reveals that annual rainfall, maximum monthly rainfall, minimum air temperature and maximum wind speed at 10 m obey Fisher-Tippet Type -1 distribution whereas maximum daily rainfall, maximum hourly rainfall, maxinlum air temperature and maximum wind speed at 30 m obey Fisher-Tippet Type -2 distribution function. There is no difference in correlation coefficients and fit both extreme value distribution function. Co-efficients of the distribution functions for each variable are established. Extreme values of parameters corresponding to return periods of 50 and 100 years are derived. These derived extreme values are particularly useful for arriving at suitable design basis values to ensure the safety of any civil structure in and around Kakrapar Atomic Power Station site with respect to stresses due to weather conditions. (author)

Collisional effects on metastable atom population in vapour generated by electron beam heating

International Nuclear Information System (INIS)

Dikshit, B; Majumder, A; Bhatia, M S; Mago, V K

2008-01-01

The metastable atom population distribution in a free expanding uranium vapour generated by electron beam (e-beam) heating is expected to depart from its original value near the source due to atom-atom collisions and interaction with electrons of the e-beam generated plasma co-expanding with the vapour. To investigate the dynamics of the electron-atom and atom-atom interactions at different e-beam powers (or source temperatures), probing of the atomic population in ground (0 cm -1 ) and 620 cm -1 metastable states of uranium was carried out by the absorption technique using a hollow cathode discharge lamp. The excitation temperature of vapour at a distance ∼30 cm from the source was calculated on the basis of the measured ratio of populations in 620 to 0 cm -1 states and it was found to be much lower than both the source temperature and estimated translational temperature of the vapour that is cooled by adiabatic free expansion. This indicated relaxation of the metastable atoms by collisions with low energy plasma electrons was so significant that it brings the excitation temperature below the translational temperature of the vapour. So, with increase in e-beam power and hence atom density, frequent atom-atom collisions are expected to establish equilibrium between the excitation and translational temperatures, resulting in an increase in the excitation temperature (i.e. heating of vapour). This has been confirmed by analysing the experimentally observed growth pattern of the curve for excitation temperature with e-beam power. From the observed excitation temperature at low e-beam power when atom-atom collisions can be neglected, the total de-excitation cross section for relaxation of the 620 cm -1 state by interaction with low energy electrons was estimated and was found to be ∼10 -14 cm 2 . Finally using this value of cross section, the extent of excitational cooling and heating by electron-atom and atom-atom collisions are described at higher e-beam powers

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.)

Point kernel technique for calculating dose rates due to cobalt-60 hot particles

International Nuclear Information System (INIS)

Thornhill, M.J.; McCarthy, J.T.; Morrissette, R.R.; Leach, B.N.

1989-01-01

This paper reports on a computer code called BETA that has been developed by health physicists at the Vermont Yankee Nuclear Power Station which accounts for the mass and size of hot particles of Cobalt-60, and therefore corrects the Loevinger-based dose calculation for self-absorption

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

Consistency considerations in the use of point kinetics for BWR application

International Nuclear Information System (INIS)

Holzer, J.M.; Habert, R.; Pilat, E.E.

1981-01-01

The basic question of producing point reactivity parameters for use in RETRAN anaylses is addressed. The technique used in establishing a methodology consists of a stepwise reduction of resolution, in space and time, so as to identify possible areas in which error may be induced and to establish procedures that retain consistency and accuracy. The presented calculational flow plan culminating from this analysis will ultimately be used at Yankee Atomic Electric for design application

Collision-produced atomic states

International Nuclear Information System (INIS)

Andersen, N.; Copenhagen Univ.

1988-01-01

The last 10-15 years have witnessed the development of a new, powerful class of experimental techniques for atomic collision studies, allowing partial or complete determination of the state of the atoms after a collision event, i.e. the full set of quantum-mechanical scattering amplitudes or - more generally - the density matrix describing the system. Evidently, such studies, involving determination of alignment and orientation parameters, provide much more severe tests of state-of-the-art scattering theories than do total or differential cross section measurements which depend on diagonal elements of the density matrix. The off-diagonal elements give us detailed information about the shape and dynamics of the atomic states. Therefore, close studies of collision-produced atomic states are currently leading to deeper insights into the fundamental physical mechanisms governing the dynamics of atomic collision events. The first part of the lectures deals with the language used to describe atomic states, while the second part presents a selection of recent results for model systems which display fundamental aspects of the collision physics in particularly instructive ways. I shall here restrict myself to atom-atom collisions. The discussion will be focused on states decaying by photon emission though most of the ideas can be easily modified to include electron emission as well. (orig./AH)

White paper on atomic energy in 1980

International Nuclear Information System (INIS)

1981-01-01

The nuclear power generation in Japan attained the scale of 21 plants with 15 million kW capacity, and its proportion in electric power supply exceeded 13%. Now it is indispensable for various economic activities and national life, and it is expected that its role as the substitute energy for petroleum will grow more and more in future. The Atomic Energy Commission took up preponderantly the promotion of nuclear power generation and the related measures in view of such situation when the trend in the development and utilization of atomic energy in Japan is reviewed in this white paper. When nuclear power generation is promoted, efforts are exerted on the improvement of safety, and it is necessary to tackle with all might the subjects such as the settlement of LWRs more firmly, the development of new reactors, the establishment of nuclear fuel cycle, and the countermove to complex international situation, while giving consideration to the development of independent technologies. It is most important to obtain national consensus when atomic energy is developed and utilized, as seen in the difficulty of locating nuclear power stations. In this annual report, the events for about one year from October, 1979, are described. Also the related data and documents are shown. (Kako, I.)

Evaluation of a hydride generation-atomic fluorescence system for the determination of arsenic using a dielectric barrier discharge atomizer

International Nuclear Information System (INIS)

Zhu Zhenli; Liu Jixin; Zhang Sichun; Na Xing; Zhang Xinrong

2008-01-01

A new atomizer based on atmospheric pressure dielectric barrier discharge (DBD) plasma was specially designed for atomic fluorescence spectrometry (AFS) in order to be applied to the measurement of arsenic. The characteristics of the DBD atomizer and the effects of different parameters (power, discharge gas, gas flow rate, and KBH 4 concentration) were discussed in the paper. The DBD atomizer shows the following features: (1) low operation temperature (between 44 and 70 deg. C, depending on the operation conditions); (2) low power consumption; (3) operation at atmospheric pressure. The detection limit of As(III) using hydride generation (HG) with the proposed DBD-AFS was 0.04 μg L -1 . The analytical results obtained by the present method for total arsenic in reference materials, orchard leaves (SRM 1571) and water samples GBW(E) 080390, agree well with the certified values. The present HG-DBD-AFS is more sensitive and reliable for the determination of arsenic. It is a very promising technique allowing for field arsenic analysis based on atomic spectrometry

Trace determination of antimony by hydride generation atomic absorption spectrometry with analyte preconcentration/atomization in a dielectric barrier discharge atomizer.

Science.gov (United States)

Zurynková, Pavla; Dědina, Jiří; Kratzer, Jan

2018-06-20

Atomization conditions for antimony hydride in the plasma atomizer based on a dielectric barrier discharge (DBD) with atomic absorption spectrometric detection were optimized. Argon was found as the best discharge gas under a flow rate of 50 mL min - 1 while the DBD power was optimum at 30 W. Analytical figures of merit including interference study of As, Se and Bi have been subsequently investigated and the results compared to those found in an externally heated quartz tube atomizer (QTA). The limit of detection (LOD) reached in DBD (0.15 ng mL -1  Sb) is comparable to that observed in QTA (0.14 ng mL -1  Sb). Finally, possibility of Sb preconcentration by stibane in situ trapping in a DBD atomizer was studied. For trapping time of 300 s, the preconcentration efficiency and LOD, respectively, were 103 ± 2% and 0.02 ng mL -1 . Copyright © 2018 Elsevier B.V. All rights reserved.

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

Tunable atom-light beam splitter using electromagnetically induced transparency

Science.gov (United States)

Zhu, Xinyu; Wen, Rong; Chen, J. F.

2018-06-01

With electromagnetically induced transmission (EIT), an optical field can be converted into collective atomic excitation and stored in the atomic medium through switching off the strong-coupling field adiabatically. By varying the power of the coupling pulse, we can control the ratio between the transmitted optical field and the stored atomic mode. We use a cloud of cold 85Rb atoms prepared in magneto-optical trap as the experimental platform. Based on a model of EIT dark-state polariton, we consider the real case where the atomic medium has a finite length. The theoretical calculation gives numerical results that agree well with the experimental data. The results show that the ratio can be changed approximately from 0 to 100%, when the maximum power of the coupling pulse (the pulse length is 100 ns) varies from 0 to 20 mW, in the cold atomic ensemble with an optical depth of 40. This process can be used to achieve an atom-light hybrid beam splitter with tunable splitting ratio and thus find potential application in interferometric measurement and quantum information processing.

Some problems on cost of nuclear power

Energy Technology Data Exchange (ETDEWEB)

Yamada, A [Japan Energy Economic Research Inst., Tokyo

1975-12-01

The price of thermal power from oil has risen sharply. On the other hand, the price of atomic energy which has been expected to be favorable as compared with thermal power is rising slowly. In addition, the financial strength of electric utilities if lower, which results in difficulty of financing atomic power development. The course and the motivation of introducing nuclear power generation are briefly summarized. The economy and the usefulness of nuclear power generation and the problem of the financing for developing atomic energy are also examined.

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.)

Atoms for peace and war, 1953-1961

International Nuclear Information System (INIS)

Hewlett, R.G.; Holl, J.M.

1989-01-01

This is the third book in a series by the author dealing with the Atomic Energy Commission (AEC). The material ranges from debates over how to use nuclear power to generate electricity to the development of the deadliest weapons in human history. Also included are a concise account of the Oppenheimer affair, a clear history of Eisenhower's Atoms for Peace initiative, and a balanced report of the partisan battle over the development of nuclear power, with Democrats insisting on a major role for government while the Republicans championed a free enterprise approach. The nearly 600 pages of text are organized around three central themes: (1) the close connection between the two seemingly different concerns of the AEC - atoms for peace and atoms for war; (2) the conflict of interest the AEC faced over the issue of nuclear testing; and (3) the central role played by Dwight D. Eisenhower in shaping American nuclear policy in the 1950s

Fifty years of 'Atoms for Peace'

International Nuclear Information System (INIS)

Heller, W.

2004-01-01

Fifty years ago, on December 8, 1953, the then U.S. President, Dwight D. Eisenhower, in his famous speech before the General Assembly of the United Nations proclaimed his 'Atoms for Peace' program, which was to initiate a policy of international cooperation. The event had been preceded by a policy of the United States intended to guarantee to the United States the monopoly in the production and use of nuclear weapons, which ultimately failed because of the resistance of the Soviet Union. The doctrine of a technological monopoly in the nuclear field was to be changed in favor of cooperative ventures under the rigorous control of the United States. The 1954 Atomic Energy Act clearly formulated the will to cooperate. Following a U.S. initiative, the International Atomic Energy Agency (IAEA) was founded in 1956 to assist in transfers of nuclear technology and assume controlling functions to prevent abuse for non-peaceful purposes. Quite a number of countries used the 'Atoms for Peace' offer to develop nuclear power in very close cooperation with American industry and depending on U.S. nuclear fuel supply. On the whole, 'Atoms for Peace' has paved the way to a worldwide peaceful use of nuclear power. (orig.)

Technology and automation of atomic power engineering and industry. TAAPEI-2009. Materials of branch scientific and technical conference covers the fiftieth anniversary of the Seversk State Engineering Academy

International Nuclear Information System (INIS)

2009-01-01

Materials of the branch scientific and technical conference Technology and automation of atomic power engineering and industry (18-22 May, 2009, Seversk) are performed. Scientific and practical results of investigations into chemical technological developments, creation of machinery and apparatuses, automation of technological processes, application of present-day information technologies in atomic industry as well as ecological and nuclear weapons proliferation problems are shown. Besides issues of professional education and social-economic problems of the atomic branch are considered [ru

Report of investigation on the radiation leak of the atomic powered ship 'Mutsu'

International Nuclear Information System (INIS)

1975-01-01

Radiation leak of the atomic powered ship Mutsu was investigated. The radiation leak from the reactor shield was caused at the time of the test run, and serious social and political problem was raised. The phenomena is the streaming of neutron and caused by the technical lack of designing. There were, however, many cause of this technical lack. The organization for construction of the ship Mutsu was politically incomplete, the system of the organization was changed frequently, and then it was very hard to call together qualified engineers. Check of the design and the mock-up test were incomplete, and improvements of design in the course of construction was not made. Responsibilities of the persons in charge were not clear. Contract concerning the shield was defective. This report proposes improvement on the above mentioned problem. (Kato, T.)

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

Advanced technologies and atomic energy

International Nuclear Information System (INIS)

1995-01-01

The expert committee on the research 'Application of advanced technologies to nuclear power' started the activities in fiscal year 1994 as one of the expert research committees of Atomic Energy Society of Japan. The objective of its foundation is to investigate the information on the advanced technologies related to atomic energy and to promote their practice. In this fiscal year, the advanced technologies in the fields of system and safety, materials and measurement were taken up. The second committee meeting was held in March, 1995. In this report, the contents of the lectures at the committee meeting and the symposium are compiled. The topics in the symposium were the meaning of advanced technologies, the advanced technologies and atomic energy, human factors and control and safety systems, robot technology and microtechnology, and functionally gradient materials. Lectures were given at two committee meetings on the development of atomic energy that has come to the turning point, the development of advanced technologies centering around ULSI, the present problems of structural fine ceramics and countermeasures of JFCC, the material analysis using laser plasma soft X-ray, and the fullerene research of advanced technology development in Power Reactor and Nuclear Fuel Development Corporation. (K.I.)

FAO and atomic energy

Energy Technology Data Exchange (ETDEWEB)

NONE

1960-07-15

During the past six years FAO has become more engaged in work concerned with atomic energy. In 1957 it established an Atomic Energy Branch. The new forces and new tools which have become available for use in the fight against poverty, disease and malnutrition can be of the greatest assistance in FAO's work in nearly all phases of the production, storage and distribution of food and other agricultural products. The Organization promotes their use to improve the standards of feeding, clothing and housing throughout the world. Another side of work related to atomic energy is concerned with combating contamination from the use of atomic energy for power production and other purposes. This raises considerable problems for food and agriculture, so that FAO also has a responsibility for assisting Governments in safeguarding their food and food-producing resources from contamination. FAO is essentially concerned with fostering wider knowledge of the many contributions that atomic science can make to agriculture, forestry, fisheries and nutrition. It is also concerned in assisting governments to establish sound programmes for applying atomic science in food and agriculture. One way of spreading such knowledge is through the publication of documents and reports

FAO and atomic energy

International Nuclear Information System (INIS)

1960-01-01

During the past six years FAO has become more engaged in work concerned with atomic energy. In 1957 it established an Atomic Energy Branch. The new forces and new tools which have become available for use in the fight against poverty, disease and malnutrition can be of the greatest assistance in FAO's work in nearly all phases of the production, storage and distribution of food and other agricultural products. The Organization promotes their use to improve the standards of feeding, clothing and housing throughout the world. Another side of work related to atomic energy is concerned with combating contamination from the use of atomic energy for power production and other purposes. This raises considerable problems for food and agriculture, so that FAO also has a responsibility for assisting Governments in safeguarding their food and food-producing resources from contamination. FAO is essentially concerned with fostering wider knowledge of the many contributions that atomic science can make to agriculture, forestry, fisheries and nutrition. It is also concerned in assisting governments to establish sound programmes for applying atomic science in food and agriculture. One way of spreading such knowledge is through the publication of documents and reports

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

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.)

(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.

Annual report 1982-83 [of the Department of Atomic Energy, India

International Nuclear Information System (INIS)

1983-01-01

The annual report of the Department of Atomic Energy (DAE) of the Government of India for the financial year 1982-83 surveys the work of its various establishments. The major thrust of the DAE's programme is directed towards peaceful uses of atomic ener%y - primarily for electric power generation and applications of radiation and radioisotopes in medicine, agriculture and industry. The Bhabha Atomic Research Centre at Bombay is the major R and D establishment of the DAE and its activities in the fields of nuclear physics, chemistry and materials science, radiochemistry, nuclear fuels, reactor engineering, radiation protection, radioactive waste management and applications of radiation and radioactive isotopes are described in detail. The R and D activities of the Reactor Research Centre at Kanpakkam, the Tata Institute of Fundamental Research and the Tata A1emorial Centre, both at Bombay, and the Saha Institute of Nuclear Physics at Calcutta are described in brief. The performance of the Tarapur Atomic Power Station, the Rajasthan Atomic Power Station, the Nuclear Fuel Complex at Hyderabad, the Atomic Minerals Division, Uranium Corporation of India Ltd at Jaduguda, various heavy water plants and other industrial units of DAE is reported. Progress of nuclear power projects at Narora and Kakrapar, R-5 Project at Bombay and FBTR Project at Kalpakkam is described. India's participation in the activities of the International Atomic Energy Agency is also mentioned. (M.G.B.)

Nuclear Power Plants. Revised.

Science.gov (United States)

Lyerly, Ray L.; Mitchell, Walter, III

This publication is one of a series of information booklets for the general public published by the United States Atomic Energy Commission. Among the topics discussed are: Why Use Nuclear Power?; From Atoms to Electricity; Reactor Types; Typical Plant Design Features; The Cost of Nuclear Power; Plants in the United States; Developments in Foreign…

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

Compact, Low-Power Atomic Time and Frequency Standards

Science.gov (United States)

2008-12-01

2007). This is consistent with other reports of survival of CSAC devices with thin polymide tethers to 500g ( Lutwak et al., 2007). • Humidity...InterPACK 󈧋 , July 8-12, 2007, Vancouver, British Columbia, CANADA Lutwak , R., et al., “The chip-scale atomic clock – prototype evaluation

Annual report of the Department of Atomic Energy 1975-76

International Nuclear Information System (INIS)

1976-01-01

The activities of the various constituent units of the Department of Atomic Energy such as the Bhabha Atomic Research Centre, Reactor Research Centre, Variable Energy Cyclotron, the power stations and a few others during the year 1975-76 are reported. The progress achieved in the field of atomic minerals, nuclear medicine, nuclear power, development of radioisotopes etc. are presented in detail. The responsibilities and achievements of the public sector undertakings under Department of Atomic Energy such as the Indian Rare Earth Ltd., Electronics Corporation of India Ltd., Uranium Corporation of India Ltd., are highlighted. Other activities such as planning and execution, economic and personnel health aspects, international relations etc. are also mentioned. (A.K.)

The system of legal regulations and supervisory powers in the German Atomic Energy Law

International Nuclear Information System (INIS)

Weber, K.H.

1984-01-01

The first part of the book deals with the practical implementation of the legal provisions governing examination and subsequent licensing and judicial restraint, and the effects of actual practice on the energy industry, for the purpose of showing the chain of cause and effect of the frequently lamented delays in the further utilisation of nuclear energy, and of analysing the role of the administrative courts in the process, pointing to the explosiveness in terms of economics of this issue. The second part analyses the risk assessments from the legal and technical point of view in order to ascertain whether the findings of risk assessments are suitable to serve as scale models for decisions to be taken by the courts. The third part is a critical evaluation of the numerous attempts to incorporate the general doctrine of discretionary power into the system of atomic energy law in a way conformable with the existing system. This analysis resulting in the statement that the attempts have failed so far, the fourth part of the book discusses the necessity to look for other solutions, among other things by critically screening the dogma of discretionary power. The author comes to the conclusion that judicial restraint is to be cut back in the licensing procedure, however not to the extent that control over the authorities is abandoned altogether, but rather in such a way that the power of administrative courts does not develop into judgments executing the law. It is to be avoided that licensing procedures for nuclear power plants degenerate into 'administrative procedures preceded by administrative procedures'. This may not be confounded with giving up all possibilities of legal protection. (orig./HSCH) [de

The World Power Conference and atomic energy

Energy Technology Data Exchange (ETDEWEB)

NONE

1962-01-15

The possibility that emerged after the last World War that useful power could be produced from nuclear fission led to optimistic estimates that nuclear power would prove to be the solution to the world's energy problems. The possible advantages of nuclear methods of power production compared with conventional means are discussed at the World Power Conference. The 1962 Conference with its theme 'The Changing Pattern of Power' will undoubtedly attract great interest in a world where the change-over from conventional to nuclear fuels for power production has started in some countries and is being actively examined in others. It is generally being realized that even though a country may possess indigenous supplies of uranium or thorium minerals, the building up of a nuclear industry i s a long and expensive process and the alternative of depending on countries more advanced in nuclear technology for the supply of materials, skill and know-how is costly in foreign exchange and international prestige. Many of the industrialized countries, still possessing supplies of conventional fuels, are preparing for the day when their reserves will become depleted and are embarking on training schemes to ensure a continuing supply of engineers and scientists skilled in nuclear arts

Atomic power or windmills. [Denmark

Energy Technology Data Exchange (ETDEWEB)

Korsbech, U [Danmarks Tekniske Hoejskole, Lyngby

1976-01-01

It is argued that if the Danish Ministry of Trade's plans for nuclear power in the nineties are changed to windpower, the price will be 5 times as high. A thorough estimation of the economy of a big Danish windpower program is given.

Recent results from the chemistry of recoiling carbon and silicon atoms: The interplay between hot atom chemistry and gas kinetics

International Nuclear Information System (INIS)

Gaspar, P.P.; Garmestani, K.; Ferrieri, R.A.; Wolf, A.P.

1990-01-01

Recent results from the chemistry of recoiling carbon and silicon atoms illustrate the power of an experimental approach to the solution of complex mechanistic problems that combines the study of the reactions of recoiling atoms with conventional gas kinetic techniques. Included will be the reactions of 11 C atoms with anisole, addressing the question whether an aromatic pi-electron system can compete as a reactive site with carbon-hydrogen bonds

The situation of Chinese atomic energy and cooperation

International Nuclear Information System (INIS)

Nagasaki, Takao

2003-01-01

China will have 8.7 million kW atomic energy in 2005. Japan will complete with China in a sale war of international atomic energy and domestic power source. The position, development and situation of Chinese atomic energy and the future nuclear fuel cycle are reported. 5.4 million kW of 7 atomic power plants in China and 45.9 million kW of 53 plants in Japan are running. 3.3 million kW of 4 plants in China and 4 million kW of 4 plants in Japan are building. New type reactor, the fast breeder and high temperature gas-cooled reactor are developing. Radiation exposure to food, radiation therapy, Radio-pharmaceuticals, polymerization and treatment of sewage and smoke are carried out. The situation of atomic energy co-operation between China and Japan and other countries are stated. Japan has to change to advance mutual interests type co-operation with China. Construction of the nuclear community in Asia area and development of the international long big project are proposed. (S.Y.)

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

Department of Atomic Energy [India]: Annual report 1979-1980

International Nuclear Information System (INIS)

1980-01-01

The work of the research establishments, projects undertaken and public sector undertakings of the Department of Atomic Energy during the financial year 1979-80 is surveyed. The research and development activities of the Bhabha Atomic Research Centre at Bombay, the Reactor Research Centre at Kalpakkam, the Tata Institute of Fundamental Research at Bombay, the Saha Institute of Nuclear Physics at Calcutta and the Tata Memorial Centre at Bombay are described. An account of the progress of heavy water production plant projects, the Madras and Narora Atomic Power Projects, the MHD project and the 100 MW thermal research reactor R-5 Project at Trombay is given. Performance of the Tarapur and Rajasthan Atomic Power Stations, Nuclear Fuel Complex at Hyderabad, Atomic Minerals Division, ISOMED (the radiation sterilisation plant for medical products) at Bombay, the Indian Rare Earths Ltd., the Uranium Corporation of India Ltd., and the Electronics Corporation of India Ltd., Hyderabad is reported. (M.G.B.)

High-energy atomic physics

CERN Document Server

Drukarev, Evgeny G

2016-01-01

This self-contained text introduces readers to the field of high-energy atomic physics - a new regime of photon-atom interactions in which the photon energies significantly exceed the atomic or molecular binding energies, and which opened up with the recent advent of new synchrotron sources. From a theoretical point of view, a small-parameter characteristic of the bound system emerged, making it possible to perform analytic perturbative calculations that can in turn serve as benchmarks for more powerful numerical computations. The first part of the book introduces readers to the foundations of this new regime and its theoretical treatment. In particular, the validity of the small-parameter perturbation expansion and of the lowest-order approximation is critically reviewed. The following chapters then apply these insights to various atomic processes, such as photoionization as a many-body problem, dominant mechanisms for the production of ions at higher energies, Compton scattering and ionization accompanied b...

The Atomic Energy Commission's Annual Report to Congress for 1961. Major Activities in the Atomic Energy Programs, January - December 1961

Energy Technology Data Exchange (ETDEWEB)

Seaborg, Glenn T.

1962-01-31

The document represents the 1961 Annual Report of the Atomic Energy Commission (AEC) to Congress. This year's report consists of four parts: Part One, The Atomic Energy Industry for 1961 and Related Activities; Part Two, Nuclear Power Programs for 1961; Part Three, Major Activities in Atomic Energy Programs; and Part Four, Regulatory Activities. Sixteen appendices are also included.

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

Atomic vapor laser isotope separation

International Nuclear Information System (INIS)

Stern, R.C.; Paisner, J.A.

1985-01-01

Atomic vapor laser isotope separation (AVLIS) is a general and powerful technique. A major present application to the enrichment of uranium for light-water power reactor fuel has been under development for over 10 years. In June 1985 the Department of Energy announced the selection of AVLIS as the technology to meet the nation's future need for the internationally competitive production of uranium separative work. The economic basis for this decision is considered, with an indicated of the constraints placed on the process figures of merit and the process laser system. We then trace an atom through a generic AVLIS separator and give examples of the physical steps encountered, the models used to describe the process physics, the fundamental parameters involved, and the role of diagnostic laser measurements

Proposed general amendments to the atomic energy control regulations

International Nuclear Information System (INIS)

1986-01-01

Canada's Atomic Energy Control Act defines the powers and responsibilities of the Atomic Energy Control Board (AECB). Among these is to make regulations to control the development, application and use of atomic energy. In these proposed general amendments to the Atomic Energy Control Regulations substantial changes are proposed in the designation of the authority of AECB staff, exemptions from licensing, international safeguards, duties of licensees and atomic radiation workers, security of information, and provision for hearings. The scope of the control of atomic energy has been redefined as relating to matters of health, safety, security, international safeguards, and the protection of the environment

Outline of renovation for Mihama Public Relations (PR) Center on atomic power generation and nuclear applications

Energy Technology Data Exchange (ETDEWEB)

1983-05-01

The Mihama PR Center of Kansai Electric Power Co. on atomic power generation and nuclear applications is now under entire renovation. It was constructed accompanying the construction of No. 1 unit in Mihama Nuclear Power Station, and opened in November, 1967, as the only PR facility of open house system. Since then, more than 1.9 million persons visited there in 15 years. Recently the space has become difficult to provide satisfactorily sophisticated exhibits because the importance of nuclear power generation has increased, and the diversified contents have been required. On the other hand, its building was cramped since many rooms were accommodated in the single round building of total area 815 m/sup 2/. In addition, the building has required drastic looking-over because of its deterioration and damages due to aging. The promotion of the understanding for the early securing of nuclear power plant location has been decided as the principal promotion item. The plan includes the modification of the existing building to the exhibition hall only as well as the completion and re-arrangement of the exhibits. It has been determined to construct a new building connected to the existing building, which accommodates a meeting hall, offices, utility machine room, etc., a total area being increased to 1457 m/sup 2/. The fund required is about 600 million yen. The construction work has started on December 1, 1982, aiming at the opening in July, 1983. The meeting hall is designed to seat about 120 persons and to employ multi-screen image techniques.

Atomic energy and you

International Nuclear Information System (INIS)

1975-01-01

The film discusses the peaceful applications of atomic energy in agriculture, engineering, industry and medicine. Shows exploration, prospecting and mining of uraninum ores at Larap, Camarines Norte and the study of geographical conditions of the site for the proposed Nuclear Power Plant in Bataan

Atomic profits, no thanks

International Nuclear Information System (INIS)

Bartels, W.; Dietrich, K.; Moeller, H.; Speier, C.

1980-01-01

The authors deal with the following topics: The secret of nuclear energy; the atom programmes of Bonn; on some arguments of the present nuclear energy discussion; how socialist countries solve the problems of nuclear energy. From the socialist point of view they discuss sociological, ideological and moral reasons for a peaceful utilization of nuclear energy. Nevertheless they refuse Bonn's atom programme because the high finance's interests concerning profit and power make it a danger. The biggest danger is said to lie in the creation of a plutonium-industry and the militaristic abuse which would be connected with it. The socialist way of utilizing atomic energy is seen by them as a way with a high feeling of responsibility towards all people and towards a guaranteed energy supply. (HSCH) [de

Atomic Energy Authority (Weapons Group) Act 1973

International Nuclear Information System (INIS)

1973-01-01

This Act, which came into force on 6th March 1973 and modified Section 2 of the Atomic Energy Authority Act 1954 in respect of the Authority's power to do work on explosive nuclear devices, made provision for the transfer to the Secretary of State for Defence of the Weapons Group of the Atomic Energy Authority. (NEA) [fr

Thermal plume behaviour and dispersion in the vicinity of Madras Atomic Power Station (east coast of India)

International Nuclear Information System (INIS)

Anup Kumar, B.; Rao, T.S.; Narasimhan, S.V.

2002-01-01

Thermal ecology studies were carried out in the vicinity of Madras Atomic Power Station (MAPS). During the course of the investigations (monthly cruises) both vertical and spatial distribution of temperature in the vicinity of the power plant out fall and mixing zone were measured using temperature probes (Accuracy ± 0.05 deg C.) The boat cruises covered an sea of 2.5 km 2 and in this region the sea surface temperature ranged from 28 to 34 deg C. At a depth of 2 m and below the temperature reaches ambient sea temperature levels (27-28 deg C). During the majority of cruises carried out, the sea current was towards north; hence most the sampling points were fixed towards north of the MAPS. The area occupied by the thermal plume was 1.3 sq. km. The sea surface temperature was found to be dependent on the seasonal current variations. (author)

Design considerations regarding an atomizer for multi-element electrothermal atomic absorption spectrometry

Energy Technology Data Exchange (ETDEWEB)

Katskov, Dmitri A., E-mail: katskovda@tut.ac.za [Department of Chemistry, Tshwane University of Technology, Private Bag X680, Pretoria 0001 (South Africa); Sadagov, Yuri M. [All-Russian Scientific Research Institute of Optical and Physical Measurements (VNIIOFI), Ozernaya St. 46, Moscow 119361 (Russian Federation)

2011-06-15

The methodology of simultaneous multi-element electrothermal atomic absorption spectrometry (ETAAS-Electrothermal Atomic Absorption Spectrometry) stipulates rigid requirements to the design and operation of the atomizer. It must provide high degree of atomization for the group of analytes, invariant respective to the vaporization kinetics and heating ramp residence time of atoms in the absorption volume and absence of memory effects from major sample components. For the low resolution spectrometer with a continuum radiation source the reduced compared to traditional ETAAS (Electrothermal Atomic Absorption Spectrometry) sensitivity should be, at least partially, compensated by creating high density of atomic vapor in the absorption pulse. The sought-for characteristics were obtained for the 18 mm in length and 2.5 mm in internal diameter longitudinally heated graphite tube atomizer furnished with 2-4.5 mg of ring shaped carbon fiber yarn collector. The collector located next to the sampling port provides large substrate area that helps to keep the sample and its residue in the central part of the tube after drying. The collector also provides a 'platform' effect that delays the vaporization and stipulates vapor release into absorption volume having already stabilized gas temperature. Due to the shape of external surface of the tube, presence of collector and rapid (about 10 {sup o}C/ms) heating, an inverse temperature distribution along the tube is attained at the beginnings of the atomization and cleaning steps. The effect is employed for cleaning of the atomizer using the set of short maximum power heating pulses. Preparation, optimal maintenance of the atomizer and its compliance to the multi-element determination requirements are evaluated and discussed. The experimental setup provides direct simultaneous determination of large group of element within 3-4 order concentration range. Limits of detection are close to those for sequential single element

Report of fact-finding survey in atomic energy industries, 1990

International Nuclear Information System (INIS)

Anon.

1992-01-01

In fiscal year 1990, Japanese economy maintained steady domestic civilian demands, and the real rate of economical growth became 5.7%. The total supply of primary energy increased by 5.3% as compared with that in the last year. The share of nuclear power recovered to 9.4% due to the increase of the capacity factor after the lapse of three years. The demand of electric power increased by 7.3% as compared with that in the previous year, and the share of nuclear power in the total generated electric power was 26.3%. The outlay of electric power industry related to atomic energy was 1735.4 billion yen, and 6% increase as compared with that in the previous year. The sales of mining and manufacturing industries related to atomic energy was 1768.1 billion yen and 2% increase as compared with that in the previous year. The construction cost of nuclear power stations was 658.3 billion yen and 17% increase. The civilian workers related to atomic energy in electric power, mining and manufacturing industries were 57687 persons and 7% increase. Kashiwazaki-Kariwa No. 2 plant (1100 MWe BWR) and No. 5 plant (1100 MWe BWR) of Tokyo Electric Power Co., Inc. started the operation, and installed nuclear power generation capacity reached 31.48 million kW of 39 plants. (K.I.)

Status of Nuclear Activities of Bangladesh Atomic Energy Commission

Energy Technology Data Exchange (ETDEWEB)

Begum, Zakia [Planning and Development, Bangladesh Atomic Energy Commission - BAEC, Paramanu Bhaban, E 12/A, Agargoan, 01207 Shere Banglanagar, Dhaka (Bangladesh)

2008-07-01

Bangladesh Atomic Energy Commission (BAEC) is the national authority for acquisition, development and application of Nuclear Science and Technology and thus is playing the pioneering role for the development of the country's nuclear research programmes and thus helping to achieve the cherished goal of self-reliance through national efforts and international co-operation. Being firmly committed to the peaceful uses of Atomic Energy, programmes have been undertaken in Physical Sciences, Biological Sciences, Engineering and Nuclear Power Sector by Bangladesh Atomic Energy Commission and some of the results have been transferred from laboratories to hospitals, agriculture, industries and environment for practical applications. In spite of some major constrains, presently BAEC's activities have increased many folds and keeping in view of the overall power crisis of the country efforts have also been given to establish Nuclear Power Plant in the country. (author)

Safety Evaluation Report related to the operation of Enrico Fermi Atomic Power Plant, Unit No. 2 (Docket No. 50-341). Supplement No. 4

International Nuclear Information System (INIS)

1984-09-01

Supplement No. 4 to the Safety Evaluation Report related to the operation of the Enrico Fermi Atomic Power Plant, Unit 2, provides the staff's evaluation of additional information submitted by the applicant regarding outstanding review issues identified in Supplement No. 3 to the Safety Evaluation Report, dated January 1983

Atmospheric 3H impact assessment (2004-2008) around Narora Atomic Power Station

International Nuclear Information System (INIS)

Kumar, A.; Gautam, Y.P.; Sharma, A.K.; Sharma, S.; Rao, K.S.; Kumar, J.; Kumar, V.; Singh, B.; Hedge, A.G.

2010-01-01

Atmospheric tritium activity is measured regularly around Narora Atomic Power Station (NAPS) since gaseous waste, which contains tritium, is being released through a 145 m high stack at NAPS site. Atmospheric data collected during 2004-2008 shows a large variation of 3 H concentration in air, fluctuating in the range of ≤0.2-91.6 Bq.m -3 . Significantly, higher tritium levels were measured in samples near the site boundary (1.6 km) of NAPS compared to off-site locations. The atmospheric dilution factor was found to be in the range of 1.1x10 -7 -7.3x10 -7 s.m -3 . The scavenging of NAPS site was found to be varying from 0.2x10 4 to 14.1x10 4 (Bq.m -3 rain water per Bqm -3 air). The inhalation dose to a member of general public at different distances (1.6-30 km) from NAPS site was found to be in the range of 0.21 μSv.y -1 . (author)

Deep diode atomic battery

International Nuclear Information System (INIS)

Anthony, T.R.; Cline, H.E.

1977-01-01

A deep diode atomic battery is made from a bulk semiconductor crystal containing three-dimensional arrays of columnar and lamellar P-N junctions. The battery is powered by gamma rays and x-ray emission from a radioactive source embedded in the interior of the semiconductor crystal

DoD Is Not Properly Monitoring the Initiation of Maintenance for Facilities at Kandahar Airfield, Afghanistan (REDACTED)

Science.gov (United States)

2013-09-30

Not Fully Used and Await Addition to the Density List ________________________________________________ 15 Yankee and Zulu Ramps Were Deteriorating as...to the Density List as of March 15, 2013. • The Yankee and Zulu Ramps consist of Air Force expeditionary fighter shelters, aviation operations...the Yankee and Zulu Ramps were not added to the Density List as of March 15, 2013. 5 The LOGCAP contractor accepted the Command Central facility on

The site selection law and the anti-atom movement; Das Standortauswahlgesetz und die Anti-Atom-Bewegung

Energy Technology Data Exchange (ETDEWEB)

Haefner, Daniel

2015-07-01

The anti atom movement has reached many of their political claims with the German nuclear power phaseout. At the same time the government has regained the interpretive dominance with the in radioactive waste management with the new search for possible final repository sites. He anti-atom movement refuses most parts of the actual law but cannot abdicate from the responsibility of the process of site selection. The contribution shows using three actual research approaches that such a convergence is probable to occur in the future. A cooperation of anti-atom movement and the government is of high probability in the long term, but is not necessarily identical to a political acceptance.

Relativistic electron-atom scattering in an extremely powerful laser field: Relevance of spin effects

International Nuclear Information System (INIS)

Panek, P.; Kaminski, J.Z.; Ehlotzky, F.

2002-01-01

We reconsider the relativistic scattering of electrons by an atom, being approximated by a static potential, in an extremely powerful electromagnetic plane wave of frequency ω and linear polarization ε. Since to a first order of approximation spin effects can be neglected, we first describe the scattered electron by the Gordon solution of the Klein-Gordon equation. Then we investigate the same scattering process by including the spin effects, using for the electron the Volkov solution of the Dirac equation. For sufficiently energetic electrons, the first-order Born approximation can be employed to represent the corresponding scattering matrix element. We compare the results of the differential cross sections of induced and inverse bremsstrahlung, evaluated from both approximations, for various parameter values and angular configurations and we find that in most cases the spin effects are marginal, even at very high laser power. On the other hand, we recover the various asymmetries in the angular distributions of the scattered electrons and their respective energies due to the laser-induced drift motion of the electrons in the direction of propagation of the radiation field, thus confirming the findings of our previous work [Phys. Rev. A 59, 2105 (1999); Laser Physics 10, 163 (2000)

Spectroscopy of Rb atoms in hollow-core fibers

International Nuclear Information System (INIS)

Slepkov, Aaron D.; Bhagwat, Amar R.; Venkataraman, Vivek; Londero, Pablo; Gaeta, Alexander L.

2010-01-01

Recent demonstrations of light-matter interactions with atoms and molecules confined to hollow waveguides offer great promise for ultralow-light-level applications. The use of waveguides allows for tight optical confinement over interaction lengths much greater than what could be achieved in bulk geometries. However, the combination of strong atom-photon interactions and nonuniformity of guided light modes gives rise to spectroscopic features that must be understood in order to take full advantage of the properties of such systems. We use light-induced atomic desorption to generate an optically dense Rb vapor at room temperature inside a hollow-core photonic band-gap fiber. Saturable-absorption spectroscopy and passive slow-light experiments reveal large ac Stark shifts, power broadening, and transit-time broadening, that are present in this system even at nanowatt powers.

The atomic energy basic law

International Nuclear Information System (INIS)

1977-01-01

The law establishes clearly the principles that Japan makes R and D, and utilizations of atomic energy only for the peaceful purposes. All the other laws and regulations concerning atomic energy are based on the law. The first chapter lays down the above mentioned objective of the law, and gives definitions of basic concepts and terms, such as atomic energy, nuclear fuel material, nuclear source material, nuclear reactor and radiation. The second chapter provides for the establishment of Atomic Energy Commission which conducts plannings and investigations, and also makes decisions concerning R and D, and utilizations of atomic energy. The third chapter stipulates for establishment of two government organizations which perform R and D of atomic energy developments including experiments and demonstrations of new types of reactors, namely, Atomic Energy Research Institute and Power Reactor and Nuclear Fuel Development Corporation. Chapters from 4th through 8th provide for the regulations on development and acquisition of the minerals containing nuclear source materials, controls on nuclear fuel materials and nuclear reactors, administrations of the patents and inventions concerning atomic energy, and also prevention of injuries due to radiations. The last 9th chapter requires the government and its appointee to compensate the interested third party for damages in relation to the exploitation of nuclear source materials. (Matsushima, A.)

Annual report of the Department of Atomic Energy, 1976-77

International Nuclear Information System (INIS)

1977-01-01

Research and development work in various research units, and activities and achievements of various public undertakings of the Department of Atomic Energy, India, during 1976-77 are reported. Construction of the 100 MW-thermal research reactor at Trombay and the Fast Breeder Test Reactor at Kalpakkam is in progress. Work on desalination, MHD and in seismology in continued. Report on performance of the Tarapur and Rajasthan Atomic Power Stations and progress of construction of the nuclear power stations at Kalpakkam and Narora is given. Fuelling machine carriage and shielding and plug assemblies for the second unit of the Rajasthan Atomic Power Station have been indigenously fabricated. A novel technique for prospecting nuclear minerals, termed as BARC-TEFUREX has been evolved and is being used successfully. The country-wide radiological protection programme covers 42,000 radiation workers in 2,280 institutions. (M.G.B.)

Application of resonance ionisation spectroscopy in atomic physics

International Nuclear Information System (INIS)

Kluge, H.J.

1997-01-01

Resonance ionization spectroscopy (RIS) and resonance ionization mass spectroscopy (RIMS) techniques have proved to be a powerful tool in atomic spectroscopy and trace analysis. Detailed atomic spectroscopy can be performed on samples containing less than 10 12 atoms. This sensitivity is especially important for investigating atomic properties of transuranium elements. RIMS is especially suitable for ultra trace determination of long lived radioactive isotopes. The extremely low detection limits allow analysis of samples in the sub-femtogram regime. High elemental and isotopic selectivity can be obtained. To produce isobarically pure ion beams, a RIS based laser ion source can be used

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.

International Atomic Energy Agency specialists meeting on experience in ageing, maintenance, and modernization of instrumentation and control systems for improving nuclear power plant availability

Energy Technology Data Exchange (ETDEWEB)

1993-10-01

This report presents the proceedings of the Specialist`s Meeting on Experience in Aging, Maintenance and Modernization of Instrumentation and Control Systems for Improving Nuclear Power Plant Availability that was held at the Ramada Inn in Rockville, Maryland on May 5--7, 1993. The Meeting was presented in cooperation with the Electric Power Research Institute, Oak Ridge National Laboratory and the International Atomic Energy Agency. There were approximately 65 participants from 13 countries at the Meeting. Individual reports have been cataloged separately.

International Atomic Energy Agency specialists meeting on experience in ageing, maintenance, and modernization of instrumentation and control systems for improving nuclear power plant availability

International Nuclear Information System (INIS)

1993-10-01

This report presents the proceedings of the Specialist's Meeting on Experience in Aging, Maintenance and Modernization of Instrumentation and Control Systems for Improving Nuclear Power Plant Availability that was held at the Ramada Inn in Rockville, Maryland on May 5--7, 1993. The Meeting was presented in cooperation with the Electric Power Research Institute, Oak Ridge National Laboratory and the International Atomic Energy Agency. There were approximately 65 participants from 13 countries at the Meeting. Individual reports have been cataloged separately

Atomic and molecular data for radiotherapy

International Nuclear Information System (INIS)

1989-05-01

An Advisory Group Meeting devoted solely to review the atomic and molecular data needed for radiotherapy was held in Vienna from 13 to 16 June 1988. The following items as related to the atoms and molecules of human tissues were reviewed: Cross sections differential in energy loss for electrons and other charged particles. Secondary electron spectra, or differential ionization cross sections. Total cross sections for ionization and excitation. Subexcitation electrons. Cross sections for charged-particle collisions in condensed matter. Stopping power for low-energy electrons and ions. Initial yields of atomic and molecular ions and their excited states and electron degradation spectra. Rapid conversion of these initial ions and their excited states through thermal collisions with other atoms and molecules. Track-structure quantities. Other relevant data. Refs, figs and tabs

Department of Atomic Energy: Annual report, 1983-84

International Nuclear Information System (INIS)

1984-01-01

The annual report of the Department of Atomic Energy for the financial year 1983-84 describes its activities under the headings: Nuclear Power, Research and Development, Public Sector Undertakings, and Other Activities. The report surveys: (1) the performance of nuclear power plants at Tarapur, Kota and Kalpakkam, heavy water plants, fuel fabrication and reprocessing plants, and waste management facilities, (2) the research and development activities of Bhabha Atomic Research Centre at Bombay and its constituent units at various locations in the country, Reactor Research Centre at Kalpakkam, the aided institutes, namely, Tata Institute of Fundamental Research and Tata Memorial Centre, both at Bombay, and Saha Institute of Nuclear Physics at Calcutta, (3) performance of public sector undertakings: Indian Rare Earths Ltd., Uranium Corporation of India Ltd., and Electronics Corporation of India Ltd., (4) progress of nuclear power projects at Narora and Kakrapar, Orissa Sand Complex Project, MHD project at Tiruchirapalli, DHRUVA (formerly known as R-5) project at Bombay, Fast Breeder Test Reactor and 500 MW Prototype Fast Breeder Reactor projects at Kalpakkam, and heavy water projects at Thal-Vaishet and Manuguru, and (5) other activities including technology transfer; training; service to industry, agriculture and medicine in use of radioisotopes and radiation, export of radioisotopes, allied products and nuclear instruments; international relations; countrywide radiation safety programme, exploration of atomic minerals; information and publicity etc. An Atomic Energy Regulatory Board was established during the report year for the special purpose of carrying out regulatory and safety functions specified in the Atomic Energy Act of the Government of India. (M.G.B.)

Atomic Energy Control Act, c A.19, s.1

International Nuclear Information System (INIS)

1985-01-01

The Revised Statutes of Canada 1985 entered into force on 12 December 1988, revoking the previous Atomic Energy Control Act and replacing it with a new version. The new Act (Chapter A-16 of the Revised Statutes) updates the previous text and makes some linguistic corrections. The Atomic Energy Control Act establishes the Atomic Energy Control Board and sets out its duties and powers which include, in particular, the making of regulations for developing, controlling and licensing the production, application and use of atomic energy [fr

Atom-by-atom assembly

International Nuclear Information System (INIS)

Hla, Saw Wai

2014-01-01

Atomic manipulation using a scanning tunneling microscope (STM) tip enables the construction of quantum structures on an atom-by-atom basis, as well as the investigation of the electronic and dynamical properties of individual atoms on a one-atom-at-a-time basis. An STM is not only an instrument that is used to ‘see’ individual atoms by means of imaging, but is also a tool that is used to ‘touch’ and ‘take’ the atoms, or to ‘hear’ their movements. Therefore, the STM can be considered as the ‘eyes’, ‘hands’ and ‘ears’ of the scientists, connecting our macroscopic world to the exciting atomic world. In this article, various STM atom manipulation schemes and their example applications are described. The future directions of atomic level assembly on surfaces using scanning probe tips are also discussed. (review article)

Atom Wavelike Nature Solved Mathematically

Science.gov (United States)

Sven, Charles

2010-03-01

Like N/S poles of a magnet the strong force field surrounding, confining the nucleus exerts an equal force [noted by this author] driving electrons away from the attraction of positively charged protons force fields in nucleus -- the mechanics for wavelike nature of electron. Powerful forces corral closely packed protons within atomic nucleus with a force that is at least a million times stronger than proton's electrical attraction that binds electrons. This then accounts for the ease of electron manipulation in that electron is already pushed away by the very strong atomic N/S force field; allowing electrons to drive photons when I strike a match. Ageless atom's electron requirements, used to drive light/photons or atom bomb, without batteries, must be supplied from a huge, external, super high frequency, super-cooled source, undetected by current technology, one that could exist 14+ billion years without degradation -- filling a limitless space prior to Big Bang. Using only replicable physics, I show how our Universe emanated from that event.

Analysis of the thermal monitoring data collected at the Peach Bottom Atomic Power Station

International Nuclear Information System (INIS)

Witten, A.J.; Gray, D.D.

1977-01-01

A comprehensive study of the data collected as part of the environmental technical specifications program for Units 2 and 3 of the Peach Bottom Atomic Power Station was conducted for the Office of Nuclear Regulatory Research of the U.S. Nuclear Regulatory Commission. The study included an analysis of both the hydrothermal and ecological data collected from 1967 through 1976. This paper presents the details of the hydrothermal analysis performed under this program. The two primary methods used for temperature monitoring, during both the preoperational and operational periods of the program, are a fixed thermograph network and boat survey measurements. Analysis of the boat survey data provides a fine resolution demonstrating variations in ambient temperature in Conowingo Pond, as well as providing a qualitative picture of the thermal plume produced by the Peach Bottom thermal discharge. The data from 18 thermograph stations was used for a quantitative probability analysis

The infancy of atomic physics Hercules in his cradle

CERN Document Server

Keller, Alex

1983-01-01

Atomic physics is a mighty Hercules that dominates modern civilization, promising immense reserves of power but threatening catastrophic war and radioactive pollution. The story of the atom's discovery and the development of techniques to harness its energy offers fascinating insights into the forces behind twenty-first-century technology. This compelling history portrays the human faces and lives behind the beginnings of atomic science.The Infancy of Atomic Physics ranges from experiments in the 1880s by William Crookes and others to the era just after the First World War, when Rutherford's f

Annual report 1984-85 [of the Department of Atomic Energy, of the Government of India

International Nuclear Information System (INIS)

1985-01-01

Research and Development (R and D) activities of the research establishments of the Department of Atomic Energy (DAE), performance of various production units and public sector undertakings of DAE and progress of various projects underway are reported. The report covers the period of the financial year 1984-85. The research establishments of DAE are the Bhabha Atomic Research Centre at Bombay and the Reactor Research Centre at Kalpakkam. DAE production units include atomic power stations for electricity generation at Tarapur, Kota and Kalpakkam; heavy water plants around the country and the Nuclear Fuel Complex at Hyderabad. Public sector undertaking of the Department are Indian Rare Earths Ltd., Electronic Corporation of India Ltd., and Uranium Corporation of India Ltd. The Atomic Minerals Division of the Department is mainly engaged in the R and D activities pertaining to exploration, prospecting and development of mineral resources needed for nuclear power programme. The Department's objective is to achieve the target of 10,000 MWe of nuclear power generating capacity by the year 2000. The Department's Nuclear Power Board operates the atomic power stations and is charged with the responsibility of design, construction and commissioning of atomic power projects at Narora and Kakrapar. The Department also financially supports the Tata Institute of Fundamental Research, the Tata Memorial Centre, both at Bombay and the Saha Institute of Nuclear Physics at Calcutta. The R and D activities of these institutions are also described in brief in this report. (M.G.B.)

X-ray spectroscopy from exotic atoms

International Nuclear Information System (INIS)

Hartmann, F.J.

1994-01-01

Why do experimentalists study exotic atoms, in particular antiprotonic atoms? The answer is simple: the information about electromagnetic, weak, and strong interactions that can be obtained by doing X-ray spectroscopy from exotic atoms is really worth the effort. It is possible to (1) enlarge the knowledge about the properties of exotic particles (such as mass and magnetic moment); (2) open a possibility to test quantum electrodynamics; (3) get detailed insight into the shape of nuclei (characterized by the nuclear radium and higher momenta) and even into the neutron distribution in the nucleus (neutron halo); and (4) use it as a powerful tool to learn about the strong interaction at very low relative hadron-nucleon velocities

A Compact, High-Flux Cold Atom Beam Source

Science.gov (United States)

Kellogg, James R.; Kohel, James M.; Thompson, Robert J.; Aveline, David C.; Yu, Nan; Schlippert, Dennis

2012-01-01

The performance of cold atom experiments relying on three-dimensional magneto-optical trap techniques can be greatly enhanced by employing a highflux cold atom beam to obtain high atom loading rates while maintaining low background pressures in the UHV MOT (ultra-high vacuum magneto-optical trap) regions. Several techniques exist for generating slow beams of cold atoms. However, one of the technically simplest approaches is a two-dimensional (2D) MOT. Such an atom source typically employs at least two orthogonal trapping beams, plus an additional longitudinal "push" beam to yield maximum atomic flux. A 2D atom source was created with angled trapping collimators that not only traps atoms in two orthogonal directions, but also provides a longitudinal pushing component that eliminates the need for an additional push beam. This development reduces the overall package size, which in turn, makes the 2D trap simpler, and requires less total optical power. The atom source is more compact than a previously published effort, and has greater than an order of magnitude improved loading performance.

Power programmes review: Nuclear power for India

International Nuclear Information System (INIS)

1959-01-01

India will require a substantial increase in the generation of electrical power to meet the demands of her developing economy. A survey of available resources has been made in the context of development envisaged under the country's five-year plans and it is felt that atomic energy will have to be used in increasing quantities to supplement conventional fuel resources in order to attain the anticipated power targets in the next two decades. It has, therefore, been decided that a small beginning will be made with the erection and commissioning of anatomic power station of 250 MW (electric) capacity by the end of 1964. The installation of a further 750 MW of nuclear power by the end of the third five-year plan period, i.e. by March 1966, is under consideration. Present Pattern and future demand of energy is discussed, as well as available resources and immediate needs. Concerning nuclear fuel cycle and cost estimates it is stated that India's uranium reserves are not large enough to sustain a very long-term programme of power generation, but the reserves for thorium are. Therefore India's nuclear power production will have to be based primarily on thorium with a rather complicated fuel cycles and first, second and third generation atomic power stations. The Atomic Energy Establishment Trombay is India's national centre for research in the peaceful uses of atomic energy. India's first reactor, Apsara, which is of the swimming pool type, has been in operation for more than three years now and two other research reactors are under construction. These are the Canada-India Reactor, which is being built under the Colombo Plan in collaboration with Canada, and Zerlina, which is being designed and built by Indian scientists and engineers. The Canada-India Reactor will be a versatile high flux research reactor and will have facilities in which various power reactor concepts can be tried out in the so-called loop experiments. In addition, it will produce considerable

Power programmes review: Nuclear power for India

Energy Technology Data Exchange (ETDEWEB)

NONE

1959-10-15

India will require a substantial increase in the generation of electrical power to meet the demands of her developing economy. A survey of available resources has been made in the context of development envisaged under the country's five-year plans and it is felt that atomic energy will have to be used in increasing quantities to supplement conventional fuel resources in order to attain the anticipated power targets in the next two decades. It has, therefore, been decided that a small beginning will be made with the erection and commissioning of anatomic power station of 250 MW (electric) capacity by the end of 1964. The installation of a further 750 MW of nuclear power by the end of the third five-year plan period, i.e. by March 1966, is under consideration. Present Pattern and future demand of energy is discussed, as well as available resources and immediate needs. Concerning nuclear fuel cycle and cost estimates it is stated that India's uranium reserves are not large enough to sustain a very long-term programme of power generation, but the reserves for thorium are. Therefore India's nuclear power production will have to be based primarily on thorium with a rather complicated fuel cycles and first, second and third generation atomic power stations. The Atomic Energy Establishment Trombay is India's national centre for research in the peaceful uses of atomic energy. India's first reactor, Apsara, which is of the swimming pool type, has been in operation for more than three years now and two other research reactors are under construction. These are the Canada-India Reactor, which is being built under the Colombo Plan in collaboration with Canada, and Zerlina, which is being designed and built by Indian scientists and engineers. The Canada-India Reactor will be a versatile high flux research reactor and will have facilities in which various power reactor concepts can be tried out in the so-called loop experiments. In addition, it will produce considerable

Power programmes review: Power reactors in the Federal Republic of Germany

Energy Technology Data Exchange (ETDEWEB)

NONE

1960-04-15

Compared with work in some other industrialized countries, the atomic energy programme in the Federal Republic of Germany got off to a somewhat late start. Nevertheless, after about four years of research and training of scientists, the country is today on the threshold of a major phase in atomic energy development. While research and training are being continued, the first concrete steps are also being initiated for the commercial utilization of nuclear energy as a source of power. Several experimental nuclear power stations are being set up, designed or planned

Department of Atomic Energy, annual report, 1980-81

International Nuclear Information System (INIS)

1981-01-01

The annual report of the Department of Atomic Energy (DAE) of the Government of India for the period of the fiscal year 1980-81 surveys the work of DAE, its various constituent units and aided institutions. The main thrust of the DAE's programme in the country is directed towards peaceful uses of atomic energy - primarily for generation of electric power and also for application of radioisotopes and radiation in medicine, agriculture, and industry. The research and development (R and D) activities of the Bhabha Atomic Research Centre (BARC) at Bombay, the major R and D establishment of DAE, in the fields of nuclear physics, solid state physics, chemistry and materials science, isotope and radiation applications, reactor technology and radioactive waste management are described in detail. The R and D activities of the Reactor Research Centre at Kalpakkam and the aided institutions such as the Tata Institute of Fundamental Research and the Tata Memorial Centre, both at Bombay, and the Saha Institute of Nuclear Physics at Calcutta are reviewed in brief. Progress of the MHD project, the heavy water plant projects, the thermal research reactor R-5 project at BARC and nuclear power plant projects at Narora and Kalpakkam is surveyed. Performance of industrial production units such as nuclear power stations at Tarapur and Kota, the Nuclear Fuel Complex at Hyderabad, Atomic Minerals Division, ISOMED - the radiation sterilisation plant for medical products, the Indian Rare Earths Ltd., the Electronics Corporation of India Ltd., and the Uranium Corporation of India Ltd., is reported. India's participation in the activities of the International Atomic Energy Agency and collaboration with other countries are also mentioned. (M.G.B.)

The Definition Method and Optimization of Atomic Strain Tensors for Nuclear Power Engineering Materials

Directory of Open Access Journals (Sweden)

Xiangguo Zeng

2016-01-01

Full Text Available A common measure of deformation between atomic scale simulations and the continuum framework is provided and the strain tensors for multiscale simulations are defined in this paper. In order to compute the deformation gradient of any atom m, the weight function is proposed to eliminate the different contributions within the neighbor atoms which have different distances to atom m, and the weighted least squares error optimization model is established to seek the optimal coefficients of the weight function and the optimal local deformation gradient of each atom. The optimization model involves more than 9 parameters. To guarantee the reliability of subsequent parameters identification result and lighten the calculation workload of parameters identification, an overall analysis method of parameter sensitivity and an advanced genetic algorithm are also developed.

The energy crisis and Bonn's atomic energy programme

International Nuclear Information System (INIS)

Steinhaus, K.; Heimbrecht, J.

1979-01-01

What are the background and causes of the energy crisis. In whose interest and on whose back is energy policy made in our country. Will the lights go out without nuclear power. Which are the real goals and dangers of Bonn's atomic energy programme. Is coal a real alternative to nuclear power in the Federal Republic of Germany. What possibilities and requirements are there for a national and democratic energy policy in the Federal Republic of Germany. Which are the central problems of the protest movement against the government's atomic energy programme. These questions, which are still in the centre of political discussion, are investigated by the authors. (orig.) [de

Compliance with Electrical and Fire Protection Standards of U.S. Controlled and Occupied Facilities in Afghanistan

Science.gov (United States)

2013-07-18

evaluate the entire system from the Pump House to all hangars on Yankee, Sierra and Zulu to make all repairs and recertify the systems and have a...system from the Pump House to all hangars on Yankee, Sierra and Zulu to make all repairs and recertify the systems and have a contract to perform O...entire system from the Pump House to all hangars on Yankee, Sierra and Zulu to make all repairs and recertify the systems and have a contract to

Annual report of the Japan Atomic Energy Research Institute, for fiscal 1989

International Nuclear Information System (INIS)

1990-01-01

Japan Atomic Energy Research Institute has promoted the research on nuclear safety, the research and development of high temperature engineering and nuclear fusion which are the leading projects bringing about the breakthrough in atomic energy technology, the research on radiation utilization and the research and development of nuclear-powered ships, following the 'Plan of development and long term utilization of atomic energy' decided in 1987, as the central, general research institute in atomic energy field in Japan. Also the advanced basic research for opening atomic energy frontier and various international cooperation as well as the cooperation in Japan have been promoted. The engineering safety of nuclear facilities and environmental safety, the construction of the Nuclear Fuel Cycle Safety Engineering Research Facility, the design of the High Temperature Engineering Test Reactor and the various tests related to it, the reconstruction of JT-60 for increasing the current, the design of a nuclear fusion reactor, the high utilization of radiation using ion beam, the construction of Sekinehama Port for the nuclear-powered ship 'Mutsu', the power increasing test of the reactor of the Mutsu, the reconstruction of JRR-3 and others are reported. (K.I.)

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

Australia's atomic conspiracy theory

International Nuclear Information System (INIS)

Binnie, A.

2001-01-01

The author questions claims by the Newcastle University historian Wayne Reynolds in his book 'Australia's Bid for the Bomb', that the impetus behind the Snowy Mountains Scheme was to provide a secure source of power for the enrichment of uranium and production of heavy water so that Australia could produce its own atomic bombs. Reynolds also argued that the Australian Atomic Energy Commission (AAEC) was set up so that Australia had a trained scientific workforce to produce plutonium for the bomb. While the book is well researched, Reynolds does not seem to understand the principles of basic science and engineering. After the Second World War, a manufacturing and industrial base with a skilled and trained workforce was needed so it could be converted to war or defence manufacturing when the need arose. This new manufacturing community would require electrical power to sustain it. Hydroelectricity and atomic energy could help provide these needs. Even though war was still raging, Prime Minister John Curtin looked ahead and set up a Department of Post-War Reconstruction. It was through this department that the Snowy Mountains Scheme would be established. Curtin did not live to see this. He died in 1945 but his successor, Ben Chifley, continued the vision. The author believes, an understanding of the science behind these developments and an appreciation of how how humans interact with each others when it comes to getting something they want is likely to give a more balanced view of the past

Nuclear Power, Nuclear Fuel Cycle and Waste Management 1980-1994. International Atomic Energy Agency Publications

International Nuclear Information System (INIS)

1995-05-01

This catalogue lists all sales publications of the International Atomic Energy Agency dealing with Nuclear Power and Nuclear Fuel Cycle and Waste Management issued during the period 1980-1994. Most publications are issued in English. Proceedings of conferences, symposia and panels of experts may contain some papers in languages other than English (French, Russian or Spanish), but all of these papers have abstracts in English. If publications are also available in other languages than English, this is noted as C for Chinese, F for French, R for Russian and S for Spanish by the relevant ISBN number. It should be noted that prices of books are quoted in Austrian Schillings. The prices do not include local taxes and are subject to change without notice. All books in this catalogue are 16 x 24 cm, paper-bound, unless otherwise stated

Assessment of macrofauna around Tarapur Atomic Power Station (TAPS), Maharashtra, India

International Nuclear Information System (INIS)

Kubal, Priti; Ambekar, Ajit; Prakash, Chandra; Sawant, Paramita B.; Pal, Asim K.; Lakra, W.S.; Baburajan, A.

2015-01-01

A study was carried out to observe the macrofaunal habitation in the coastal area of India's first commercial atomic power station at Tarapur, Maharashtra. Mostly macrobenthos are sedentary as well as sessile in nature; therefore, they are used as indicator organism to monitor health of marine ecosystem. The faunal record observed consisted of 25 groups with 16 different polychaete families dominated by nereidae, capitellidae and spionidae. Shannon wiener index (H') was highest at Varor for faunal groups (2.07) and polychaete families (2.89) and lowest at anthropogenically stressed Uchheli (faunal group -0.77 and polychaete family 1.94). These findings were further supported by dendrogram. Margalef's species richness was highest at Varor (fauna -1.93 and polychaete family -1.61) and lowest at Nandgoan (fauna-1.00 and polychaete family - 0.74) due to dominance of environmental bioindicators, polychaete (nereidae). Along with these observations, hydro-sedimentological parameters revealed comprehensive picture of community structure of macrobenthos and polychaetes families. The elevated water temperature was noticed at TAPS 3 and 4 (30.1 °C) which is under permissible limit (26-28°C ±7) accompanied by pH (7.0). Dissolved oxygen was lowest at Uchheli (4.1mgl -1 ) and maximum was observed at TAPS 1 and 2 area (7.5mgl -1 ). (author)

Ultrafast atomic process in X-ray emission by using inner-shell ionization method for sodium and carbon atoms

Energy Technology Data Exchange (ETDEWEB)

Moribayashi, Kengo; Sasaki, Akira; Tajima, Toshiki [Japan Atomic Energy Research Inst., Neyagawa, Osaka (Japan). Kansai Research Establishment

1998-07-01

An ultrafast inner-shell ionization process with X-ray emission stimulated by high-intensity short-pulse X-ray is studied. Carbon and sodium atoms are treated as target matter. It is shown that atomic processes of the target determine the necessary X-ray intensity for X-ray laser emission as well as the features of X-ray laser such as wavelength and duration time. The intensity also depends on the density of initial atoms. Furthermore, we show that as the intensity of X-ray source becomes high, the multi-inner-shell ionization predominates, leading to the formation of hollow atoms. As the density of hollow atoms is increased by the pumping X-ray power, the emission of X-rays is not only of significance for high brightness X-ray measurement but also is good for X-ray lasing. New classes of experiments of pump X-ray probe and X-ray laser are suggested. (author)

Entrainment and impingement of aquatic fauna at cooling water system of Madras Atomic Power Station (MAPS)

International Nuclear Information System (INIS)

Barath Kumar, S.; Das, N.P.I.; Satpathy, K.K.

2015-01-01

Marine organisms get impinged to the intake screens of Madras Atomic Power Station (MAPS) due to the suction force of the cooling water system of the power plant. The present work has studied the loss of aquatic organism at MAPS due to impingement at cooling water screens. In total 67 species of marine faunas impinged on the water intake screens of MAPS during the study. The proportion of fish, shrimp, crab, jellyfish and others, with respect to the total biomass of impinged organisms are 1.59 % (33 species), 0.30% (9), 2.77 % (16), 95.10% (3) and 0.24% (4), respectively. Jellyfishes were observed to be the largest entrained group covering around 44.85% of individual and constituting almost 94.82 % of biomass recorded during the study period and sea nettle jelly (Chrysaora quinquecirrha) was impinged with highest frequency. The diel study shows higher impingement occurred during night time, on full moon day and at low tides in contrast to their counterparts. Fishes accounts for 14.84 % of individual count and mere 1.67 % of biomass. Totally 33 number of fish species were observed. The highest impinged species were pony fishes (Secutor ruconius, Secutor insidiator, Photopectoralis bindus, Alepes kleinii and Leiognathus equulus) (21% occurrence). These few entrained fishes are mostly very small in size and have less commercial value. The total loss of marine fauna by impingement during study period was estimated to be 4779 (or 463.46 kg). The present data when compared with the impingement data from other coastal power plants, shows that the impinged fish biomass at MAPS cooling water system is much less than the other temperate and tropical power plants. (author)

Basic atomic interactions of accelerated heavy ions in matter atomic interactions of heavy ions

CERN Document Server

Tolstikhina, Inga; Winckler, Nicolas; Shevelko, Viacheslav

2018-01-01

This book provides an overview of the recent experimental and theoretical results on interactions of heavy ions with gaseous, solid and plasma targets from the perspective of atomic physics. The topics discussed comprise stopping power, multiple-electron loss and capture processes, equilibrium and non-equilibrium charge-state fractions in penetration of fast ion beams through matter including relativistic domain. It also addresses mean charge-states and equilibrium target thickness in ion-beam penetrations, isotope effects in low-energy electron capture, lifetimes of heavy ion beams, semi-empirical formulae for effective cross sections. The book is intended for researchers and graduate students working in atomic, plasma and accelerator physics.

Release criteria for decommissioning of the Shippingport Atomic Power Station

International Nuclear Information System (INIS)

Eger, K.J.; Gardner, D.L.; Giordano, R.J.

1986-01-01

The United States Department of Energy (DOE) has established guidelines for allowable levels of residual radioactivity at remote sites in the Surplus Facilities Management Program (SFMP). These guidelines specify that doses to the public from this residual radioactivity must not exceed 500 mrem/year (for up to five years) or 100 mrem/year (for a lifetime), regardless of the use of the land. The guidelines also specify that exposures be further limited, depending on ALARA considerations. The decommissioning of the Shippingport Atomic Power Station, done under the auspices of SFMP, is being performed in accordance with these guidelines. It follows that, at the conclusion of the project, the concentrations of residual radioactivity, identified both by isotope and location (x,y,z), must be low enough so that the guidelines (500,100) are not exceeded. Furthermore, the concentrations must be low enough so that additional action which might be taken to reduce them cannot cost effectively decrease the dose to the public. A cost-benefit analysis, based on actual conditions at Shippingport, is being prepared to identify these ''low-enough'' concentrations. Once identified, these concentrations will comprise the release criteria for the site. The analysis will be developed by (1) performing an initial site characterization, (2) employing pathways analyses to compute the dose to a future occupant, (3) costing of proposed site modifications, and (4) repeating a pathways analysis based on each ''as-modified'' location on the site. The result will be a paired set of data relating the cost of modification to the reduction in the dose to the future occupant

The four decades of Korea Atomic Energy Research Institute through pictures

International Nuclear Information System (INIS)

2000-04-01

This reports the process and development of Korea Atomic Energy Research Institute with a lot of photos. It is divided five parts, which includes the introduction of the purpose of publication, the quickening period of nuclear Atomic Energy during 1960s the period of building foundation on nuclear power during 1970s the period for technical independence for nuclear atomic energy during 1980s and maturity on technical independence for nuclear atomic energy during 1990s. It deals with the history of Korea Atomic Energy Research Institute from 1959 to 1990.

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

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.)

Theoretical study of electromagnetically induced transparency in a five-level atom and application to Doppler-broadened and Doppler-free Rb atoms

International Nuclear Information System (INIS)

Bhattacharyya, Dipankar; Ray, Biswajit; Ghosh, Pradip N

2007-01-01

We report theoretical studies of a Λ-type five-level atomic system. The density matrix equations are set up and solved numerically to obtain the probe absorption line shape of Rb D 2 transitions for cold (Doppler-free) and room temperature (Doppler-broadened) atoms. Simulated spectra for Doppler-broadened systems lead to four velocity-selective dips along with an electromagnetic induced transparency (EIT) peak as observed earlier from the co-propagating pump-probe spectroscopy of Rb D 2 transitions. Effects of pump power and spontaneous decay rate from the upper levels on the simulated spectra are also studied. For cold atoms a very pronounced EIT peak is observed when the pump frequency is on resonance with one allowed transition. We find that lower pump power leads to a much sharper EIT signal in this case. A simulated dispersion curve shows a rapid variation of the refractive index that may lead to a sharp reduction of the group velocity of photons

Applications of lasers in nuclear power plants

International Nuclear Information System (INIS)

Raj, Rupam; Sanyal, D.N.; Sil, Jaydeb

2013-01-01

Applications of lasers in nuclear power plants: Bellow lip cutting and high pressure feeder coupling stud (HPFC) cutting during en-masse coolant channel replacement (EMCCR) campaign at Narora Atomic Power Station Reactor 1 in May 2006; cutting of pressure tubes from Madras Atomic Power Station 1 (MAPS-1) for easy storage in April 2005; In-situ cutting of selected coolant channel S-7 at Kakrapar Atomic Power Station (KAPS-2) (cutting of 12 mm thick end fitting and 4 mm thick liner tube of stainless steel from inside) in January 2005; Development of a miniature cutting mechanism for steam generator tubes (14 mm i.d.) from inside, In-situ bellow repair for secondary shutdown system; LASER welding may be deployed for End shield of MAPS-1 leak repair

Fluorescence measurement of atomic oxygen concentration in a dielectric barrier discharge

Science.gov (United States)

Dvořák, P.; Mrkvičková, M.; Obrusník, A.; Kratzer, J.; Dědina, J.; Procházka, V.

2017-06-01

Concentration of atomic oxygen was measured in a volume dielectric barrier discharge (DBD) ignited in mixtures of Ar + O2(+ H2) at atmospheric pressure. Two-photon absorption laser induced fluorescence (TALIF) of atomic oxygen was used and this method was calibrated by TALIF of Xe in a mixture of argon and a trace of xenon. The calibration was performed at atmospheric pressure and it was shown that quenching by three-body collisions has negligible effect on the life time of excited Xe atoms. The concentration of atomic oxygen in the DBD was around 1021 m-3 and it was stable during the whole discharge period. The concentration did not depend much on the electric power delivered to the discharge provided that the power was sufficiently high so that the visible discharge filled the whole reactor volume. Both the addition of hydrogen or replacing of argon by helium led to a significant decrease of atomic oxygen concentration. The TALIF measurements of O concentration levels in the DBD plasma performed in this work are made use of e.g. in the field analytical chemistry. The results contribute to understanding the processes of analyte hydride preconcentration and subsequent atomization in the field of trace element analysis where DBD plasma atomizers are employed.

Atomic and molecular processes in fusion plasmas

Energy Technology Data Exchange (ETDEWEB)

Janev, R.K. [International Atomic Energy Agency, Vienna (Austria)

1997-01-01

The role of atomic and molecular processes in achieving and maintaining the conditions for thermonuclear burn in a magnetically confined fusion plasma is described. Emphasis is given to the energy balance and power and particle exhaust issues. The most important atomic and molecular processes which affect the radiation losses and impurity transport in the core plasma, the neutral particle transport in the plasma edge and the radiative cooling of divertor plasmas are discussed in greater detail. (author)

Progression of technology education for atomic energy engineering in Tsuyama National College of Technology

International Nuclear Information System (INIS)

Kato, M.; Kobayashi, T.; Okada, T.; Sato, M.; Sasai, Y.; Konishi, D.; Harada, K.; Taniguchi, H.; Toya, H.; Inada, T.; Sori, H.; Yagi, H.

2011-01-01

This paper describes the achievements of a program in which technology education is provided to cultivate practical core engineers for low-level radiation. It was made possible by means of (1) an introductory education program starting at an early age and a continuous agenda throughout college days and (2) regional collaboration. First, with regard to the early-age introductory education program and the continuous education agenda, the subjects of study related to atomic energy or nuclear engineering were reorganized as 'Subjects related to Atomic Power Education' for all grades in all departments. These subjects were included in the syllabus and the student guide book, emphasizing a continuous and consistent policy throughout seven-year college study, including the five-year system and additional two-year advanced course. Second, to promote practical education, the contents of lectures, experiments, and internships were enriched and realigned in collaboration with the Japan Atomic Energy Agency, Okayama University and The Cyugoku Electric Power Co., Inc. In addition to the expansion and rearrangement of atomic power education, research on atomic power conducted for graduation thesis projects were undertaken to enhance the educational and research activities. In consequence, it has been estimated that there is now a total of fourteen subject areas in atomic energy technology, more than eight-hundred registered students in the department, and thirteen members of the teaching staff related to atomic energy technology. Furthermore, the 'Tsuyama model' is still being developed. This program was funded by the Ministry of Education, Culture, Sports, Science and Technology. (author)

Progression of technology education for atomic energy engineering in Tsuyama National College of Technology

International Nuclear Information System (INIS)

Kato, Manabu; Kobayashi, Toshiro; Okada, Tadashi

2012-01-01

This paper describes the achievements of a program in which technology education is provided to cultivate practical core engineers for low-level radiation. It was made possible by means of (1) an introductory education program starting at an early age and a continuous agenda throughout college days and (2) regional collaboration. First, with regard to the early-age introductory education program and the continuous education agenda, the subjects of study related to atomic energy or nuclear engineering were reorganized as “Subjects related to Atomic Power Education” for all grades in all departments. These subjects were included in the syllabus and the student guide book, emphasizing a continuous and consistent policy throughout seven-year college study, including the five-year system and additional two-year advanced course. Second, to promote practical education, the contents of lectures, experiments, and internships were enriched and realigned in collaboration with the Japan Atomic Energy Agency, Okayama University and The Cyugoku Electric Power Co., Inc. In addition to the expansion and rearrangement of atomic power education, research on atomic power conducted for graduation thesis projects were undertaken to enhance the educational and research activities. In consequence, it has been estimated that there is now a total of fourteen subject areas in atomic energy technology, more than eight-hundred registered students in the department, and thirteen members of the teaching staff related to atomic energy technology. Furthermore, the “Tsuyama model” is still being developed. This program was funded by the Ministry of Education, Culture, Sports, Science and Technology. (author)

Interest of atomic physic for fusion

International Nuclear Information System (INIS)

Breton, C.; De Michelis, C.; Mattioli, M.; Platz, P.; Ramette, J.; Saoutic, B.

1984-01-01

Impurity radiation is one of the most important energy loss mechanism of fusion plasmas. Atomic processes and hypothesis of the model used in evaluating the power radiated are described. The use of radiation as a diagnostic tool for plasma physicist is reviewed [fr

Characteristic of lipid metabolism and state of free-radical processes in workers of 30-km alienation zone at Chernobyl Atomic Power Plant

International Nuclear Information System (INIS)

Chayalo, P.P.; Chobot'ko, G.M.; Palamar, L.A.; Kolesnik, L.L.; Kuznetsov, G.P.

1997-01-01

The study involved 54 men aged 35-50 working in 30 km alienation zone at the Chernobyl Atomic Power Plant. Blood serum and erythrocyte lipid peroxidation indices were estimated. Investigation of peroxidation processes in the erythrocytes allowed to reveal changes in glutation system, they being characterized by its amount elevation against the background of glutation transferase activity increase both in the persons, working in the 30 km zone, and in those from 'Ukryttia' Establishment

Hydrogen atom kinetics in capacitively coupled plasmas

Science.gov (United States)

Nunomura, Shota; Katayama, Hirotaka; Yoshida, Isao

2017-05-01

Hydrogen (H) atom kinetics has been investigated in capacitively coupled very high frequency (VHF) discharges at powers of 16-780 mW cm-2 and H2 gas pressures of 0.1-2 Torr. The H atom density has been measured using vacuum ultra violet absorption spectroscopy (VUVAS) with a micro-discharge hollow cathode lamp as a VUV light source. The measurements have been performed in two different electrode configurations of discharges: conventional parallel-plate diode and triode with an intermediate mesh electrode. We find that in the triode configuration, the H atom density is strongly reduced across the mesh electrode. The H atom density varies from ˜1012 cm-3 to ˜1010 cm-3 by crossing the mesh with 0.2 mm in thickness and 36% in aperture ratio. The fluid model simulations for VHF discharge plasmas have been performed to study the H atom generation, diffusion and recombination kinetics. The simulations suggest that H atoms are generated in the bulk plasma, by the electron impact dissociation (e + H2 \\to e + 2H) and the ion-molecule reaction (H2 + + H2 \\to {{{H}}}3+ + H). The diffusion of H atoms is strongly limited by a mesh electrode, and thus the mesh geometry influences the spatial distribution of the H atoms. The loss of H atoms is dominated by the surface recombination.

Study: control of atomic energy power plant; Etude de la regulation d'une installation atomique productrice d'energie

Energy Technology Data Exchange (ETDEWEB)

Dautray, R; Leny, J C [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1958-07-01

We are studying the control of a very flexible atomic power plant, able to supply an independent network. Two systems have been examined: in the first the moderator pre-heats the light water, in the second, this preheating is dispensed with, subsequent to a study of the dynamics of the plant. Very complete linear approximation study is being effected on the model of the second system, all effects being taken into account. The reactor is stable at all power levels, though slight reactivity or load variations cause undamped power oscillations around the equilibrium level. (author)Fren. [French] Nous etudions la regulation d'une installation atomique d'une grande souplesse, pouvant eventuellement fournir de l'energie a un reseau isole. Deux versions de l'installation sont etudiees: dans la premiere le moderateur sert a rechauffer l'eau industrielle, mais l'etude dynamique conduit a supprimer ce rechauffage, ce qui donne la deuxieme version. On effectue sur celle-ci une etude en approximation lineaire tres complete ou l'on tient compte de differents effets. L'installation se montre stable a tous les niveaux de puissance. Toutefois, de petites perturbations de reactivite ou de charge entrainent des oscillations de puissance mal amorties autour de la position d'equilibre. (auteur)

Giant atom smasher on hunt for "Sparticles"

CERN Multimedia

Moskowitz, Clara

2008-01-01

"Squarks, photinos, selectrons, neutralinos: these are just a few types of supersymmetrice particles, a special brand of particle that may be created when the world's most powerful atom smasher goes online this spring." (1 page)

Atom-surface potentials and atom interferometry

International Nuclear Information System (INIS)

Babb, J.F.

1998-01-01

Long-range atom-surface potentials characterize the physics of many actual systems and are now measurable spectroscopically in deflection of atomic beams in cavities or in reflection of atoms in atomic fountains. For a ground state, spherically symmetric atom the potential varies as -1/R 3 near the wall, where R is the atom-surface distance. For asymptotically large distances the potential is weaker and goes as -1/R 4 due to retardation arising from the finite speed of light. This diminished interaction can also be interpreted as a Casimir effect. The possibility of measuring atom-surface potentials using atomic interferometry is explored. The particular cases studied are the interactions of a ground-state alkali-metal atom and a dielectric or a conducting wall. Accurate descriptions of atom-surface potentials in theories of evanescent-wave atomic mirrors and evanescent wave-guided atoms are also discussed. (author)

Bremsstrahlung in atom-atom collisions

International Nuclear Information System (INIS)

Amus'ya, M.Y.; Kuchiev, M.Y.; Solov'ev, A.V.

1985-01-01

It is shown that in the collision of a fast atom with a target atom when the frequencies are on the order of the potentials or higher, there arises bremsstrahlung comparable in intensity with the bremsstrahlung emitted by an electron with the same velocity in the field of the target atom. The mechanism by which bremsstrahlung is produced in atom-atom collisions is elucidated. Results of specific calculations of the bremsstrahlung spectra are given for α particles and helium atoms colliding with xenon

Energy loading effects in the scaling of atomic xenon lasers

International Nuclear Information System (INIS)

Ohwa, M.; Kushner, M.J.

1990-01-01

The intrinsic power efficiency of the atomic xenon (5d → 6p) infrared (1.73--3.65 μm) laser is sensitive to the rate of pumping due to electron collision mixing of the laser levels. Long duration pumping at moderate power deposition may therefore result in higher energy efficiencies than pumping at higher powers. In this paper the authors examine the consequences of high energy deposition (100's J/1 atm) during long pumping pulses (100's μs) on the intrinsic power and energy efficiency and optimum power deposition of the atomic xenon laser. The dominant effect of high energy loading, gas heating, causes an increase in the electron density and therefore an increase in the electron collision mixing of the laser levels. The optimum power deposition for a given gas density therefore shifts to lower values with increasing gas temperature. For sufficiently long pumping pulses, nonuniform gas heating results in convection and rarification of highly pumped regions. The optimum power deposition therefore shifts to even lower values as the length of the pumping pulse increases. As a result, laser efficiency depends on the spatial distribution of power deposition as well as its magnitude

Strategy for designing stable and powerful nitrogen-rich high-energy materials by introducing boron atoms.

Science.gov (United States)

Wu, Wen-Jie; Chi, Wei-Jie; Li, Quan-Song; Li, Ze-Sheng

2017-06-01

One of the most important aims in the development of high-energy materials is to improve their stability and thus ensure that they are safe to manufacture and transport. In this work, we theoretically investigated open-chain N 4 B 2 isomers using density functional theory in order to find the best way of stabilizing nitrogen-rich molecules. The results show that the boron atoms in these isomers are aligned linearly with their neighboring atoms, which facilitates close packing in the crystals of these materials. Upon comparing the energies of nine N 4 B 2 isomers, we found that the structure with alternating N and B atoms had the lowest energy. Structures with more than one nitrogen atom between two boron atoms had higher energies. The energy of N 4 B 2 increases by about 50 kcal/mol each time it is rearranged to include an extra nitrogen atom between the two boron atoms. More importantly, our results also show that boron atoms stabilize nitrogen-rich molecules more efficiently than carbon atoms do. Also, the combustion of any isomer of N 4 B 2 releases more heat than the corresponding isomer of N 4 C 2 does under well-oxygenated conditions. Our study suggests that the three most stable N 4 B 2 isomers (BN13, BN24, and BN34) are good candidates for high-energy molecules, and it outlines a new strategy for designing stable boron-containing high-energy materials. Graphical abstract The structural characteristics, thermodynamic stabilities, and exothermic properties of nitrogen-rich N 4 B 2 isomers were investigated by means of density functional theory.

Nuclear Reactors for Space Power, Understanding the Atom Series.

Science.gov (United States)

Corliss, William R.

The historical development of rocketry and nuclear technology includes a specific description of Systems for Nuclear Auxiliary Power (SNAP) programs. Solar cells and fuel cells are considered as alternative power supplies for space use. Construction and operation of space power plants must include considerations of the transfer of heat energy to…

A versatile atomic number correction for electron-probe microanalysis

International Nuclear Information System (INIS)

Love, G.; Cox, M.G.; Scott, V.D.

1978-01-01

A new atomic number correction is proposed for quantitative electron-probe microanalysis. Analytical expressions for the stopping power S and back-scatter R factors are derived which take into account atomic number of the target, incident electron energy and overvoltage; the latter expression is established using Monte Carlo calculations. The correct procedures for evaluating S and R for multi-element specimens are described. The new method, which overcomes some limitations inherent in earlier atomic number corrections, may readily be used where specimens are inclined to the electron beam. (author)

Atomic force microscopy indentation of fluorocarbon thin films fabricated by plasma enhanced chemical deposition at low radio frequency power

International Nuclear Information System (INIS)

Sirghi, L.; Ruiz, A.; Colpo, P.; Rossi, F.

2009-01-01

Atomic force microscopy (AFM) indentation technique is used for characterization of mechanical properties of fluorocarbon (CF x ) thin films obtained from C 4 F 8 gas by plasma enhanced chemical vapour deposition at low r.f. power (5-30 W) and d.c. bias potential (10-80 V). This particular deposition method renders films with good hydrophobic property and high plastic compliance. Commercially available AFM probes with stiff cantilevers (10-20 N/m) and silicon sharpened tips (tip radius < 10 nm) are used for indentations and imaging of the resulted indentation imprints. Force depth curves and imprint characteristics are used for determination of film hardness, elasticity modulus and plasticity index. The measurements show that the decrease of the discharge power results in deposition of films with decreased hardness and stiffness and increased plasticity index. Nanolithography based on AFM indentation is demonstrated on thin films (thickness of 40 nm) with good plastic compliance.

Fast switching of alkali atom dispensers using laser-induced heating

International Nuclear Information System (INIS)

Griffin, P.F.; Weatherill, K.J.; Adams, C.S.

2005-01-01

We show that by using an intense laser source to locally heat an alkali atom dispenser, one can generate a high flux of atoms followed by fast recovery (<100 ms) of the background pressure when the laser is extinguished. For repeated heating pulses a switch-on time for the atomic flux of 200 ms is readily attainable. This technique is suited to ultracold atom experiments using simple ultrahigh vacuum (UHV) chambers. Laser-induced heating provides a fast repetition of the experimental cycle, which, combined with low atom loss due to background gas collisions, is particularly useful for experiments involving far-off resonance optical traps, where sufficient laser power (0.5-4 W) is readily available

Shadow-free multimers as extreme-performance meta-atoms

Science.gov (United States)

Safari, M.; Albooyeh, M.; Simovski, C. R.; Tretyakov, S. A.

2018-02-01

We generalize the concept of parity-time symmetric structures with the goal to create meta-atoms exhibiting extraordinary abilities to overcome the presumed limitations in the scattering of overall lossless particles, such as nonzero forward scattering and the equality of scattering and extinction powers for all lossless particles. Although the forward scattering amplitude and the extinction cross section of our proposed meta-atoms vanish, they scatter incident energy into other directions, with controllable directionality. These meta-atoms possess extreme electromagnetic properties not achievable for passive scatterers. As an example, we study meta-atoms consisting of two or three small dipole scatterers. We consider possible microwave realizations in the form of short dipole antennas loaded by lumped elements. The proposed meta-atom empowers extraordinary response of a shadow-free scatterer and theoretically enables most unusual material properties when used as a building block of an artificial medium.

Recent developments at the atomic and molecular data unit of the International Atomic Energy Agency

International Nuclear Information System (INIS)

Clark, R.E.H.; )

2002-01-01

The Atomic and Molecular (A+M) Data Unit of the IAEA main purpose is to establish and maintain databases in support of nuclear fusion energy research. This encompasses a very large number of processes in atomic, molecular, and plasma - material interaction physics. Recent improvements and additions to these databases are presented. A prototype search engine, which searches five different sites for radiative data and two sites for electron impact excitation and ionization data is introduced. It is available at the IAEA, Weizmann Institute and GAPHYOR web sites. Data on erosion materials produced by the Co-ordinated research project (CRP) 'Plasma-interaction induced erosion of fusion reactor materials' was evaluated, fitted to physically realistic forms for angle and energy dependence and the resulting fits were added to the online electronic database. In a CRP on radiative power losses in plasmas, many lenghtly modelling calculations were carried out. In addition to providing the calculated radiated power, effective ionisation and recombination rate coefficients were derived. These data were stored along with the populations of the ion stages as well as the total radiation from each ion stage. Thus, it is possible to use these data to interpolate in temperature and electron density to obtain the radiated power at an arbitrary temperature and density. A preliminary version of a new interface to the bibliographic database at the A+M Data unit was developed, it allows the user to search by author and/or keyword. The resulting references are displayed along with a link to the home page of the journal where possible. A code for calculation electron impact excitation cross sections using the so-called 'average approximation' and a version of the Hartree-Fock atomic structure code were installed in the unit and can be run through an interface at the web page. (nevyjel)

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)

Massachusetts nuclear power referendum: Lessons learned from the campaign trail

International Nuclear Information System (INIS)

Allen, S.R.

1989-01-01

Last November, Massachusetts voters cast their ballots on a binding initiative which, if passed, would have prohibited the production of high-level waste, thereby permanently shutting down the state's two nuclear power plants: Yankee and Pilgrim. Question 4, as the initiative became known, posed an unprecedented challenge for the state's six major utilities. Essentially, Question 4 was defeated for two reasons: compelling arguments and a well-founded strategy for communicating those arguments. One part of that strategy was the use of debates and public-speaking engagements before both civic groups and on radio/television. These debates and presentations were clearly the most interesting part of the campaign and provided many insights that may be applied to long-term public policy and informational programs. Obviously, there is a significant difference between an intense, focused campaign and an ongoing, diverse public information program-but many of the principles are the same. The purpose of this paper is to review some of the key lessons learned from over 300 debates and presentations in the highly emotional atmosphere of the Question 4 campaign. Throughout the campaign, debaters and speakers submitted after action reports, and it is from these as well as the overall campaign results that the lessons and anecdotes are derived

Thermoelectric transport and Peltier cooling of cold atomic gases

Science.gov (United States)

Grenier, Charles; Kollath, Corinna; Georges, Antoine

2016-12-01

This brief review presents the emerging field of mesoscopic physics with cold atoms, with an emphasis on thermal and 'thermoelectric' transport, i.e. coupled transport of particles and entropy. We review in particular the comparison between theoretically predicted and experimentally observed thermoelectric effects in such systems. We also show how combining well-designed transport properties and evaporative cooling leads to an equivalent of the Peltier effect with cold atoms, which can be used as a new cooling procedure with improved cooling power and efficiency compared to the evaporative cooling currently used in atomic gases. This could lead to a new generation of experiments probing strong correlation effects of ultracold fermionic atoms at low temperatures.

Applied atomic and collision physics special topics

CERN Document Server

Massey, H S W; Bederson, Benjamin

1982-01-01

Applied Atomic Collision Physics, Volume 5: Special Topics deals with topics on applications of atomic collisions that were not covered in the first four volumes of the treatise. The book opens with a chapter on ultrasensitive chemical detectors. This is followed by separate chapters on lighting, magnetohydrodynamic electrical power generation, gas breakdown and high voltage insulating gases, thermionic energy converters, and charged particle detectors. Subsequent chapters deal with the operation of multiwire drift and proportional chambers and streamer chambers and their use in high energy p

Atomic nanoscale technology in the nuclear industry

CERN Document Server

Woo, Taeho

2011-01-01

Developments at the nanoscale are leading to new possibilities and challenges for nuclear applications in areas ranging from medicine to international commerce to atomic power production/waste treatment. Progress in nanotech is helping the nuclear industry slash the cost of energy production. It also continues to improve application reliability and safety measures, which remain a critical concern, especially since the reactor disasters in Japan. Exploring the new wide-ranging landscape of nuclear function, Atomic Nanoscale Technology in the Nuclear Industry details the breakthroughs in nanosca

Experience with low-power x86 processors (Atom) for HEP usage. An initial analysis of the Intel® dual core Atom™ N330 processor

CERN Document Server

Balazs, G; Nowak, A; CERN. Geneva. IT Department

2009-01-01

In this paper we compare a system based on an Intel Atom N330 low-power processor to a modern Intel Xeon® dual-socket server using CERN IT’s standard criteria for comparing price-performance and performance per watt. The Xeon server corresponds to what is typically acquired as servers in the LHC Computing Grid. The comparisons used public pricing information from November 2008. After the introduction in section 1, section 2 describes the hardware and software setup. In section 3 we describe the power measurements we did and in section 4 we discuss the throughput performance results. In section 5 we summarize our initial conclusions. We then go on to describe our long term vision and possible future scenarios for using such low-power processors, and finally we list interesting development directions.

German Atomic Energy Act turns fifty

International Nuclear Information System (INIS)

Schneider, Horst

2009-01-01

The German Atomic Energy Act entered into force on January 1, 1960. It turns fifty at the beginning of 2010. Is this a reason to celebrate or rather the opposite? Lawyers, in principle, can view old pieces of legislation from 2 perspectives: On the one hand, aged laws are treated in a spirit of veneration and are celebrated as proven. On the other hand, an anniversary of this kind can be a welcome reason for demands to abolish or, at least, fundamentally renew that law. Over the past half century, the German Atomic Energy Act went through stormy and varied phases both of a legal and a political character. Its 50 th anniversary is likely to spark off very conflicting evaluations as well. A review of legal history shows that the German or, rather, the Federal German Atomic Energy Act (AtG) was not a first-of-its-kind piece of legislation but stemmed from the 1957 EURATOM Treaty, in a way representing a latecomer of that treaty. The Atomic Energy Act experienced a number of important developments throughout its history: - In 1975, compulsory licensing of fuel element factories was introduced. - The back end of the fuel cycle, especially final storage, were incorporated in the Atomic Energy Act comprehensively first in 1976. - In 1985, legislators decided in favor of unlimited nuclear liability. - In 1994 and 1998, only some innovations in special items were introduced under the headings of environmental impact assessment and suitability for repository storage because the controversy about nuclear power did not permit a fundamental alignment towards a more comprehensive modern safety law. - The decision to opt out of the peaceful uses of nuclear power in 2002 drew the final line so far of decisions about directions of nuclear law in a major amendment. In parallel, the decisions by the Federal Constitutional Court and the Federal Administrative Court in the late 1970s and, above all, the 1980s provided important assistance which has remained valid to this day. What is

French lessons in nuclear power

International Nuclear Information System (INIS)

Valenti, M.

1991-01-01

In stark contrast to the American atomic power experience is that of the French. Even the disaster at Chernobyl in 1986, which chilled nuclear programs throughout Western Europe, did not slow the pace of the nuclear program of the state-owned Electricite de France (EDF), based in Paris. Another five units are under construction and are scheduled to be connected to the French national power grid before the end of 1993. In 1989, the EDF's 58 nuclear reactors supplied 73 percent of French electrical needs, a higher percentage than any other country. In the United States, for example, only about 18 percent of electrical power is derived from the atom. Underpinning the success of nuclear energy in France is its use of standardized plant design and technology. This has been an imperative for the French nuclear power industry since 1974, when an intensive program of nuclear power plant construction began. It was then, in the aftermath of the first oil embargo, that the French government decided to reduce its dependence on imported oil by substituting atomic power sources for hydrocarbons. Other pillars supporting French nuclear success include retrofitting older plants with technological or design advances, intensive training of personnel, using robotic and computer aids to reduce downtime, controlling the entire nuclear fuel cycle, and maintaining a comprehensive public information effort about the nuclear program

Star power

International Nuclear Information System (INIS)

Kennedy, Tom

2003-01-01

Discusses the fight over the diminishing supply of fossil fuels and how there could be an unlimited, clean and politically free source of power just over the horizon. Fusion was discovered as a much better, inexhaustable supply of power, it only takes a few atoms to fuse for fusion to take off. Fusion once started will continue until all the fuel is exhausted. It is expected, that with the current rate of progess, in fifty years time scientists will achieve practical fusion power

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)

The first phase epidemiological study on the workers engaged in radiation business in facilities for atomic power generation

International Nuclear Information System (INIS)

Iwasaki, Tamiko; Kumatori, Toshiyuki

1996-01-01

Recently, the influence of long-lasting exposure to low-dose radiation on human bodies, especially on carcinogenesis have been attracting considerable attentions, however, there are few data available for the estimation of such risks. An epidemiological survey study on the workers for radiation business in atomic power stations was started in 1990 and its first phase study (1990-1994) was finished. This report describes the outlines of the results from the study, which has been made public by the Science and Technology Agency. The correlation between the exposure dose and carcinogenicity was observed only for the cancer in pancreas, but not in other organs. But, the previous studies in other countries and the data from the persons exposed to atomic bomb indicated that there was no significant correlation between the radiation and the incidence of pancreatic cancer. This causal relation found should be coped with carefully. The standardized mortality ratio, SMR for all kinds of death cause in the subjects was 0.89 (95% CI: 0.82-0.96), significantly lower than that in all Japanese men. This fact was consistent with the data in other countries, suggesting that the decreased SMR compared with the whole people would be due to so called 'healthy worker's effects'. (M.N.)

Silicon carbide transparent chips for compact atomic sensors

Science.gov (United States)

Huet, L.; Ammar, M.; Morvan, E.; Sarazin, N.; Pocholle, J.-P.; Reichel, J.; Guerlin, C.; Schwartz, S.

2017-11-01

Atom chips [1] are an efficient tool for trapping, cooling and manipulating cold atoms, which could open the way to a new generation of compact atomic sensors addressing space applications. This is in particular due to the fact that they can achieve strong magnetic field gradients near the chip surface, hence strong atomic confinement at moderate electrical power. However, this advantage usually comes at the price of reducing the optical access to the atoms, which are confined very close to the chip surface. We will report at the conference experimental investigations showing how these limits could be pushed farther by using an atom chip made of a gold microcircuit deposited on a single-crystal Silicon Carbide (SiC) substrate [2]. With a band gap energy value of about 3.2 eV at room temperature, the latter material is transparent at 780nm, potentially restoring quasi full optical access to the atoms. Moreover, it combines a very high electrical resistivity with a very high thermal conductivity, making it a good candidate for supporting wires with large currents without the need of any additional electrical insulation layer [3].

White paper on atomic energy, for 1974 and 1975

International Nuclear Information System (INIS)

1975-01-01

Nearly 20 years have passes since the initiation of peaceful uses of atomic energy in Japan. Close to the end of this period, there had occurred the so-called oil crisis, which emphasizes the keen need for nuclear power development. In the meanwhile, voices of the people in Japan are varied concerning the nuclear power, as in siting of the power plants and the n.s. (nuclear ship) Mutsu. The white paper describes the following: safety, environment preservation, nuclear power generation, nuclear fuel cycle, power reactor development and fusion reactor, nuclear-powered ship, radiation utilization, etc. (Mori, K.)

Prospects for Precise Measurements with Echo Atom Interferometry

Directory of Open Access Journals (Sweden)

Brynle Barrett

2016-06-01

Full Text Available Echo atom interferometers have emerged as interesting alternatives to Raman interferometers for the realization of precise measurements of the gravitational acceleration g and the determination of the atomic fine structure through measurements of the atomic recoil frequency ω q . Here we review the development of different configurations of echo interferometers that are best suited to achieve these goals. We describe experiments that utilize near-resonant excitation of laser-cooled rubidium atoms by a sequence of standing wave pulses to measure ω q with a statistical uncertainty of 37 parts per billion (ppb on a time scale of ∼50 ms and g with a statistical precision of 75 ppb. Related coherent transient techniques that have achieved the most statistically precise measurements of atomic g-factor ratios are also outlined. We discuss the reduction of prominent systematic effects in these experiments using off-resonant excitation by low-cost, high-power lasers.

Optical atomic phase reference and timing

Science.gov (United States)

Hollberg, L.; Cornell, E. H.; Abdelrahmann, A.

2017-06-01

Atomic clocks based on laser-cooled atoms have made tremendous advances in both accuracy and stability. However, advanced clocks have not found their way into widespread use because there has been little need for such high performance in real-world/commercial applications. The drive in the commercial world favours smaller, lower-power, more robust compact atomic clocks that function well in real-world non-laboratory environments. Although the high-performance atomic frequency references are useful to test Einstein's special relativity more precisely, there are not compelling scientific arguments to expect a breakdown in special relativity. On the other hand, the dynamics of gravity, evidenced by the recent spectacular results in experimental detection of gravity waves by the LIGO Scientific Collaboration, shows dramatically that there is new physics to be seen and understood in space-time science. Those systems require strain measurements at less than or equal to 10-20. As we discuss here, cold atom optical frequency references are still many orders of magnitude away from the frequency stability that should be achievable with narrow-linewidth quantum transitions and large numbers of very cold atoms, and they may be able to achieve levels of phase stability, ΔΦ/Φtotal ≤ 10-20, that could make an important impact in gravity wave science. This article is part of the themed issue 'Quantum technology for the 21st century'.

Building the Strategic Action Plan of the Vietnam Atomic Energy Institute during 2014-2019

International Nuclear Information System (INIS)

Hoang Sy Than; Tran Chi Thanh; Nguyen Hao Quang; Nguyen Nhi Dien; Nguyen Viet Hung; Tran Ngoc Toan; Mai Dinh Trung

2015-01-01

In the Decisions by the Prime Minister in the Strategy on Peaceful Utilization of Atomic Energy up to 2020, Vietnam Atomic Energy Institute (VINATOM) was assigned as the Technical Support Organization of the nuclear power projects; and as a key role-player in the decision-making process and in building the national nuclear power infrastructure. Therefore, Building the Strategic Action Plan (SAP) is necessary when VINATOM in present is facing several challenges of varying importance. This report will show the SAP of VINATOM during 2014-2019. The goal of SAP is to develop VINATOM up to the regional advanced level in the field of atomic energy application, such as radiation application, nuclear power and train human resources. The plan of Organizational development, Implementation roadmap and Implementation Solutions of SAP is presented in this report. (author)

Powerful effective one-electron Hamiltonian for describing many-atom interacting systems

International Nuclear Information System (INIS)

Lugo, J.O.; Vergara, L.I.; Bolcatto, P.G.; Goldberg, E.C.

2002-01-01

In this paper, we present an alternative way to build the effective one-electron picture of a many-atom interacting system. By simplifying the many-body general problem we present two different options for the bond-pair model Hamiltonian. We have found that the successive approximations in order to achieve the effective description have a dramatic influence on the result. Thus, only the model that introduces the correct renormalization in the diagonal term due to the overlap is able to reproduce, even in a quantitative fashion, the main properties of simple homonuclear diatomic molecules. The success of the model resides in the accurate definitions (free of parametrization) of the Hamiltonian terms, which, therefore, could be used to describe more complex interacting systems such as polyatomic molecules, adsorbed species, or atoms scattered by a surface

Atom Mirny: The World’S First Civilian Nuclear Power Plant

International Nuclear Information System (INIS)

Kaiser, Peter; Madsen, Michael

2013-01-01

The world’s first civilian nuclear power plant was commissioned on June 27, 1954 in Obninsk, which was at that time in the Soviet Union, today, the Russian Federation. The Obninsk nuclear power plant generated electricity and supported experimental nuclear research. The Obninsk nuclear power plant operated without incident for 48 years. In September 2002, the last fuel subassembly was unloaded, when the Obninsk nuclear power plant set another first: it became the first nuclear power plant to be decommissioned in Russia

Why? The nuclear and atomic energy

International Nuclear Information System (INIS)

Lee, Kwangwoong

2009-01-01

This book is a science comic book for students in elementary school, which contains energy and life such as our body and energy, animal and energy, plant and energy, kinetic energy, potential energy and the principle of the conservation of energy in the first part. The second part explains fossil fuel like coal, petroleum and natural gas. Next it deals with electric power, nuclear energy such as atom and molecule, nuclear fusion and energy for future like solar cell and black hole power plant.

Why? The nuclear and atomic energy

Energy Technology Data Exchange (ETDEWEB)

Lee, Kwangwoong

2009-01-15

This book is a science comic book for students in elementary school, which contains energy and life such as our body and energy, animal and energy, plant and energy, kinetic energy, potential energy and the principle of the conservation of energy in the first part. The second part explains fossil fuel like coal, petroleum and natural gas. Next it deals with electric power, nuclear energy such as atom and molecule, nuclear fusion and energy for future like solar cell and black hole power plant.

Nuclear power reactor safety

International Nuclear Information System (INIS)

Pon, G.A.

1976-10-01

This report is based on the Atomic Energy of Canada Limited submission to the Royal Commission on Electric Power Planning on the safety of CANDU reactors. It discusses normal operating conditions, postulated accident conditions, and safety systems. The release of radioactivity under normal and accident conditions is compared to the limits set by the Atomic Energy Control Regulations. (author)

Annual report of the Department of Atomic Energy 1977-78

International Nuclear Information System (INIS)

1978-01-01

The activities during the financial year 1977-78 of the research organizations and laboratories, various projects underway and public sector undertakings of the Department of Atomic Energy (India) have been reported. The R and D Work of the Bhabha Atomic Research Centre, Bombay and Reactor Research Centre, Kalpakkam in the fields of nuclear physics, radio- and radiation chemistry and other physical sciences; biological sciences including nuclear medicine, food irradiation and plant breeding by radiation mutation; reactor engineering and application of radiation and radioisotopes has been surveyed. The progress of heavy water projects, MHD project, nuclear power plant projects and 100 Mw thermal research reactor R-5 project has been described. Performance of Tarapur and Rajasthan Atomic Power Stations, Nuclear Fuel Complex and Electronics Corporation of India Ltd., both at Hyderabad, Uranium Corporation of India Ltd. at Jaduguda and Indian Rare Earths Ltd. has been reported. Major achievements during the period of report are : (1) completion of construction work of the Power Reactor Fuel Reprocessing Plant at Tarapur and (2) Commissioning of the Variable Energy Cyclotron, Calcutta for the internal circulating beam of alpha particles. (M.G.B.)

Atom Skimmers and Atom Lasers Utilizing Them

Science.gov (United States)

Hulet, Randall; Tollett, Jeff; Franke, Kurt; Moss, Steve; Sackett, Charles; Gerton, Jordan; Ghaffari, Bita; McAlexander, W.; Strecker, K.; Homan, D.

2005-01-01

Atom skimmers are devices that act as low-pass velocity filters for atoms in thermal atomic beams. An atom skimmer operating in conjunction with a suitable thermal atomic-beam source (e.g., an oven in which cesium is heated) can serve as a source of slow atoms for a magneto-optical trap or other apparatus in an atomic-physics experiment. Phenomena that are studied in such apparatuses include Bose-Einstein condensation of atomic gases, spectra of trapped atoms, and collisions of slowly moving atoms. An atom skimmer includes a curved, low-thermal-conduction tube that leads from the outlet of a thermal atomic-beam source to the inlet of a magneto-optical trap or other device in which the selected low-velocity atoms are to be used. Permanent rare-earth magnets are placed around the tube in a yoke of high-magnetic-permeability material to establish a quadrupole or octupole magnetic field leading from the source to the trap. The atoms are attracted to the locus of minimum magnetic-field intensity in the middle of the tube, and the gradient of the magnetic field provides centripetal force that guides the atoms around the curve along the axis of the tube. The threshold velocity for guiding is dictated by the gradient of the magnetic field and the radius of curvature of the tube. Atoms moving at lesser velocities are successfully guided; faster atoms strike the tube wall and are lost from the beam.

Atoms in strong laser fields

International Nuclear Information System (INIS)

L'Huillier, A.

2002-01-01

When a high-power laser focuses into a gas of atoms, the electromagnetic field becomes of the same magnitude as the Coulomb field which binds a 1s electron in a hydrogen atom. 3 highly non-linear phenomena can happen: 1) ATI (above threshold ionization): electrons initially in the ground state absorb a large number of photons, many more than the minimum number required for ionization; 2) multiple ionization: many electrons can be emitted one at a time, in a sequential process, or simultaneously in a mechanism called direct or non-sequential; and 3) high order harmonic generation (HHG): efficient photon emission in the extreme ultraviolet range, in the form of high-order harmonics of the fundamental laser field can occur. The theoretical problem consists in solving the time dependent Schroedinger equation (TDSE) that describes the interaction of a many-electron atom with a laser field. A number of methods have been proposed to solve this problem in the case of a hydrogen atom or a single-active electron atom in a strong laser field. A large effort is presently being devoted to go beyond the single-active approximation. The understanding of the physics of the interaction between atoms and strong laser fields has been provided by a very simple model called ''simple man's theory''. A unified view of HHG, ATI, and non-sequential ionization, originating from the simple man's model and the strong field approximation, expressed in terms of electrons trajectories or quantum paths is slowly emerging. (A.C.)

Development of laser excited atomic fluorescence and ionization methods

International Nuclear Information System (INIS)

Winefordner, J.D.

1991-01-01

Progress report: May 1, 1988 to December 31, 1991. The research supported by DE-FG05-88ER13881 during the past (nearly) 3 years can be divided into the following four categories: (1) theoretical considerations of the ultimate detection powers of laser fluorescence and laser ionization methods; (2) experimental evaluation of laser excited atomic fluorescence; (3) fundamental studies of atomic and molecular parameters in flames and plasmas; (4) other studies

Systematic evaluation program, status summary report

International Nuclear Information System (INIS)

1983-01-01

Status reports are presented on the systematic evaluation program for the Big Rock Point reactor, Dresden-1 reactor, Dresden-2 reactor, Ginna-1 reactor, Connecticut Yankee reactor, LACBWR reactor, Millstone-1 reactor, Oyster Creek-1 reactor, Palisades-1 reactor, San Onofre-1 reactor, and Rowe Yankee reactor

Feasibility and usefulness of reconstructing obsolete power blocks of VVER-440 reactors

International Nuclear Information System (INIS)

Kirichenko, A.M.; Krushenik, S.D.; Sigal, M.V.; Kustov, V.P.

1993-01-01

At the present time, in Russia and in the East European countries there are atomic power stations with first-generation VVER-440 reactors built according to specification which no longer satisfy the more rigorous modern safety standards. Among these power stations are, in particular, the Novovoronezh and the Armenian Atomic Power Station and two blocks of the Kola Atomic Power Station. The search for technical solutions for modernizing these power blocks is complicated because two conditions which are hard to reconcile must be fulfilled: an acceptable safety level must be obtained and the rebuilding must be economically justifiable (particularly since the time of operation of a power block until its standard service life is over is short). Research work undertaken in the All-Union Scientific Research Institute of Atomic Power Stations has shown that one way of overcoming these difficulties may involve changing the operating conditions of the reactor assembly to a less demanding mode of operation. This solution implies an economically justified minimum of structural improvements, provides the required safety level, and prolongs the service life of the power block. The reduction of the thermal power, and consequently, the necessary transfer of a power block to another option

Possible health hazards of nuclear power

International Nuclear Information System (INIS)

Kneale, G.W.

1981-01-01

In considering the possible health hazards of nuclear power, evidence is examined that official estimates of risks, on which governments may be supposed to base their decisions as to the acceptibility of a nuclear power programme, may be understated. In particular the case that the Hanford survey is more appropriate as a basis of risk estimation than the survey of the survivors of the atomic bombs dropped on Japan, The Atomic Bomb Casualty Commission Study, is discussed. (U.K.)

Thermonuclear Propaganda: Presentations of Nuclear Strategy in the Early Atomic Age

Science.gov (United States)

2014-06-01

United States of the epoch of total war in the 20th century took responsibility for educating its population and ensuring they were behind its... comics .17 One scholar of atomic culture noted the ambiguity of the duality of the atomic age as a central tenant to building the “most powerful of all...2004). 18 Ferenc Morton Szasz, Atomic Comics : Cartoonists Confront the Nuclear World (Reno, NV: University of Nevada Press, 2012), 135. 19 Ibid

Amendment of Atomic Energy Basic Law and the development of Atomic Energy Administration

International Nuclear Information System (INIS)

Ochi, Kenji

1978-01-01

This article explains the key points of the major development of Atomic Energy Administration recently made by amendments of Atomic Energy Basic Law and other two relating laws. These amendments passed through the Diet and were enacted on 7th, June, 1978. The aim of them is focussed on reinforcement and rearrangement of safety controls on nuclear reactors. Previously, although the approval of the installation plan with basic designs of a nuclear reactor has been done by Prime Minister, further approvals of detailed designs and process of construction works, as well as inspections before and after operation have been conducted by each responsible minister, respectively. That is, those controls for power reactors have been within jurisdiction of minister of Trade and Industry, and for nuclear ships' reactors minister of Transportation has been responsible. Under the new system, above mentioned ministers continue to exercise almost same controls over reactors within their jurisdiction respectively, however the new laws have established so-called ''double check'' principle in that: when each responsible minister approves the installation, detailed designs and further stages of construction and operation of the reactor, he should hear and pay a great regard for opinions of Atomic Energy Commission and Atomic Energy Safety Commission. The latter is newly established organization which has similar status and authority to the former. (J.P.N.)

Materials Investigation for Power Plants and Power Industry. Seminar

International Nuclear Information System (INIS)

Szteke, W.; Wasiak, J.; Bilous, W.; Przyborska, M.; Wagner, T.; Wojciechowska, J.; Zubowski, B.

2005-01-01

The Report is an assembly of the papers concerning the present state and perspectives of evolution of power industry in Poland, in this the development of atomic energy. The material and diagnostic problems occurring the exploitation of power station as well as gas pipelines are also discussed. The progress in the accommodation of the Polish technical prescriptions to the European law is also described. (authors)

Analysis of radiation exposure during creep adjustment to the coolant channels at Madras Atomic Power Station

International Nuclear Information System (INIS)

Varadhan, R.S.; Venkataramana, K.; Kannan, R.K.; Sreekumaran Nair, B.; Chudalayandi, K.

1994-01-01

In pressurised heavy water reactors the coolant channels made of zircaloy-2 undergo creep deformation used intense neutron irradiation in the reactor core. In order to measure and provide for the changes in the dimensions, base line data of internal diameters, sag and length of the 306 coolant channels are measured as pre service inspection (PSI) before the reactor is loaded with fuel prior to criticality. Subsequently as part of in service inspection (ISI), axial creep of every channel is measured in every annual shutdown of the reactor and creep adjustment is done on those channels where creep expansion margin for the next one year operation is low. A study was carried out to assess the radiological impact of the job at Madras Atomic Power Station (MAPS). Various measures adopted for reducing the individual and collective doses on the job are discussed in this report. (author). 3 refs., 2 tabs

Atomic-Resolution Spectrum Imaging of Semiconductor Nanowires.

Science.gov (United States)

Zamani, Reza R; Hage, Fredrik S; Lehmann, Sebastian; Ramasse, Quentin M; Dick, Kimberly A

2018-03-14

Over the past decade, III-V heterostructure nanowires have attracted a surge of attention for their application in novel semiconductor devices such as tunneling field-effect transistors (TFETs). The functionality of such devices critically depends on the specific atomic arrangement at the semiconductor heterointerfaces. However, most of the currently available characterization techniques lack sufficient spatial resolution to provide local information on the atomic structure and composition of these interfaces. Atomic-resolution spectrum imaging by means of electron energy-loss spectroscopy (EELS) in the scanning transmission electron microscope (STEM) is a powerful technique with the potential to resolve structure and chemical composition with sub-angstrom spatial resolution and to provide localized information about the physical properties of the material at the atomic scale. Here, we demonstrate the use of atomic-resolution EELS to understand the interface atomic arrangement in three-dimensional heterostructures in semiconductor nanowires. We observed that the radial interfaces of GaSb-InAs heterostructure nanowires are atomically abrupt, while the axial interface in contrast consists of an interfacial region where intermixing of the two compounds occurs over an extended spatial region. The local atomic configuration affects the band alignment at the interface and, hence, the charge transport properties of devices such as GaSb-InAs nanowire TFETs. STEM-EELS thus represents a very promising technique for understanding nanowire physical properties, such as differing electrical behavior across the radial and axial heterointerfaces of GaSb-InAs nanowires for TFET applications.

Sustainable progression of technology education for atomic energy engineering in Tsuyama National College of Technology

International Nuclear Information System (INIS)

Kobayashi, Toshiro; Kato, Manabu; Sori, Hitoshi; Okada, Tadashi; Sasai, Yuji; Sato, Makoto; Inada, Tomomi; Harada, Kanji

2014-01-01

This study describes the achievements of a program that provides technology education about radiation to develop practical core engineers, then the effects of the programed were discussed. An education program starting at an early age and continuous and consistent educational agendas through seven years of college has been constructed in collaboration with regional organizations. Subjects relating to atomic energy or nuclear engineering were regrouped as “Subjects Related to Atomic Power Education” for most grades in each department. These subjects were included in the syllabus and the student guide book to emphasize a continuous and consistent policy throughout the seven-year period of college study, comprising the five-year system and the additional two-year advanced course. Furthermore, the content of lectures, experiments, and internships was enriched and realigned in collaboration with the Japan Atomic Energy Agency (JAEA), Okayama University, and Chugoku Electric Power Co., Inc. Additional educational materials were developed from inspection visits by teaching staff to atomic energy facilities were also used in the classes. Two student experiment textbooks were developed to promote two of the subjects related to atomic energy: “Cloud Chamber Experiment” and “A Test of γ-ray Inverse Square Law.” In addition to the expansion and rearrangement of atomic power education, research on atomic power conducted for graduation thesis projects was undertaken to enhance educational and research activities. Some examples are as follows: “Study on the Relation between γ Dose Rate and Rainfall in Northern Okayama Area,” “Remote Sensing of Radiation Dose Rate by Customizing an Autonomous Robot,” and “Nuclear Reaction Analysis for Composition Measurement of BN Thin Films.” It should be noted that an atomic-energy-related education working group has been in place officially to continue the above activities in the college since 2011. In consequence

Condition monitoring and signature analysis techniques as applied to Madras Atomic Power Station (MAPS) [Paper No.: VIA - 1

International Nuclear Information System (INIS)

Rangarajan, V.; Suryanarayana, L.

1981-01-01

The technique of vibration signature analysis for identifying the machine troubles in their early stages is explained. The advantage is that a timely corrective action can be planned to avoid breakdowns and unplanned shutdowns. At the Madras Atomic Power Station (MAPS), this technique is applied to regularly monitor vibrations of equipment and thus is serving as a tool for doing corrective maintenance of equipment. Case studies of application of this technique to main boiler feed pumps, moderation pump motors, centrifugal chiller, ventilation system fans, thermal shield ventilation fans, filtered water pumps, emergency process sea water pumps, and antifriction bearings of MAPS are presented. Condition monitoring during commissioning and subsequent operation could indicate defects. Corrective actions which were taken are described. (M.G.B.)

AtomDB: Expanding an Accessible and Accurate Atomic Database for X-ray Astronomy

Science.gov (United States)

Smith, Randall

Since its inception in 2001, the AtomDB has become the standard repository of accurate and accessible atomic data for the X-ray astrophysics community, including laboratory astrophysicists, observers, and modelers. Modern calculations of collisional excitation rates now exist - and are in AtomDB - for all abundant ions in a hot plasma. AtomDB has expanded beyond providing just a collisional model, and now also contains photoionization data from XSTAR as well as a charge exchange model, amongst others. However, building and maintaining an accurate and complete database that can fully exploit the diagnostic potential of high-resolution X-ray spectra requires further work. The Hitomi results, sadly limited as they were, demonstrated the urgent need for the best possible wavelength and rate data, not merely for the strongest lines but for the diagnostic features that may have 1% or less of the flux of the strong lines. In particular, incorporation of weak but powerfully diagnostic satellite lines will be crucial to understanding the spectra expected from upcoming deep observations with Chandra and XMM-Newton, as well as the XARM and Athena satellites. Beyond incorporating this new data, a number of groups, both experimental and theoretical, have begun to produce data with errors and/or sensitivity estimates. We plan to use this to create statistically meaningful spectral errors on collisional plasmas, providing practical uncertainties together with model spectra. We propose to continue to (1) engage the X-ray astrophysics community regarding their issues and needs, notably by a critical comparison with other related databases and tools, (2) enhance AtomDB to incorporate a large number of satellite lines as well as updated wavelengths with error estimates, (3) continue to update the AtomDB with the latest calculations and laboratory measurements, in particular velocity-dependent charge exchange rates, and (4) enhance existing tools, and create new ones as needed to

Laser-driven source of spin-polarized atomic hydrogen and deuterium

International Nuclear Information System (INIS)

Poelker, M.

1995-01-01

A laser-driven source of spin-polarized hydrogen (H) and deuterium (D) that relies on the technique of optical pumping spin exchange has been constructed. In this source, H or D atoms and potassium atoms flow continuously through a drifilm-coated spin-exchange cell where potassium atoms are optically pumped with circularly-polarized laser light in a high magnetic field. The H or D atoms become polarized through spin-exchange collisions with polarized potassium atoms. High electron polarization (∼80%) has been measured for H and D atoms at flow rates ∼2x10 17 atoms/s. Lower polarization values are measured for flow rates exceeding 1x10 18 atoms/s. In this paper, we describe the performance of the laser-driven source as a function of H and D atomic flow rate, magnetic field strength, alkali density and pump-laser power. Polarization measurements as a function of flow rate and magnetic field suggest that, despite a high magnetic field, atoms within the optical-pumping spin-exchange apparatus evolve to spin-temperature equilibrium which results in direct polarization of the H and D nuclei. (orig.)

The quantum exodus jewish fugitives, the atomic bomb, and the holocaust

CERN Document Server

Fraser, Gordon Murray

2012-01-01

It was no accident that the Holocaust and the Atomic Bomb happened at the same time. When the Nazis came into power in 1933, their initial objective was not to get rid of Jews. Rather, their aim was to refine German culture: Jewish professors and teachers at fine universities were sacked. Atomic science had attracted a lot of Jewish talent, and as Albert Einstein and other quantum exiles scattered, they realized that they held the key to a weapon of unimaginable power. Convincedthat their gentile counterparts in Germany had come to the same conclusion, and having witnessed what the Nazis were

Post-irradiation examination of fuel elements of Tarapur Atomic Power Station (Report-I)

International Nuclear Information System (INIS)

Bahl, J.K.; Sah, D.N.; Chatterjee, S.; Sivaramkrishnan, K.S.

1979-01-01

Detailed post-irradiation examination of three initial load fuel elements of the Tarapur Atomic Power Station (TAPS) has been carried out. The causes of the element failures have been analysed. It was observed that almost 90% of the length of the elements exoerienced nodular corrosion. It has been estimated that nodular corrosion would seriously affect the wall thickness and surface temperature of higher rated elements. Lunar shaped fret marks have also been observed at some spacer grid locations in the elements. The depth of the largest fret mark was measured to be 16.9% clad wall thickness. Detailed metallographic examination of the clad and fuel in the three elements has been done. The temperatures at different structural regions of the fuel cross-sections have been estimated. The change in fuel density during irradiation has been evaluated by comparing the irradiated fuel diameter with the mean pellet design diameter. The performance of the end plug welds and spacer grid sites in the elements has been assessed. The burnup distribution along the length of the elements has been evaluated by gamma scanning. The redistribution of fission products in the fuel has been examined by gamma scanning and beta-gamma autoradiography. Mechanical properties of the irradiated cladding have been examined by ring tensile testing. (auth.)

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

Atoms

International Nuclear Information System (INIS)

Fuchs, Alain; Villani, Cedric; Guthleben, Denis; Leduc, Michele; Brenner, Anastasios; Pouthas, Joel; Perrin, Jean

2014-01-01

Completed by recent contributions on various topics (atoms and the Brownian motion, the career of Jean Perrin, the evolution of atomic physics since Jean Perrin, relationship between scientific atomism and philosophical atomism), this book is a reprint of a book published at the beginning of the twentieth century in which the author addressed the relationship between atomic theory and chemistry (molecules, atoms, the Avogadro hypothesis, molecule structures, solutes, upper limits of molecular quantities), molecular agitation (molecule velocity, molecule rotation or vibration, molecular free range), the Brownian motion and emulsions (history and general features, statistical equilibrium of emulsions), the laws of the Brownian motion (Einstein's theory, experimental control), fluctuations (the theory of Smoluchowski), light and quanta (black body, extension of quantum theory), the electricity atom, the atom genesis and destruction (transmutations, atom counting)

Solar and Geothermal Energy: New Competition for the Atom

Science.gov (United States)

Carter, Luther J.

1974-01-01

Describes new emphasis on research into solar and geothermal energy resources by governmental action and recent legislation and the decreased emphasis on atomic power in supplementing current energy shortages. (BR)

Fire fighting precautions at Bohunice Atomic Power Plants

International Nuclear Information System (INIS)

Anon.

1984-01-01

Some shortcomings are discussed of the project design of fire protection at the V-1 and V-2 nuclear power plants. The basic shortcoming of the system is insufficient division of the units for fire protection. Fire fighting measures are described for cable areas, switch houses and outside transformers, primary and secondary circuits and auxiliary units. Measures are presented for increasing fire safety in Jaslovske Bohunice proceedi.ng from experience gained with a fire which had occurred at a nuclear power plant in Armenia. (E.S.)

Nuclear power and physics

International Nuclear Information System (INIS)

Xu Mi

2006-01-01

During the 30s and 40s of the last century atomic physicists discovered the fission of uranium nuclei bombarded by neutrons and realized the first self-sustaining controlled fission chain reaction, which ushered in the atomic age. After 50 years of electricity production, in 2003 nuclear power plants were generating 16% of the total electricity in the world. Of these, thermal neutron reactors make up over 99%. For the large scale production of nuclear power, say up to hundreds of GWe, it is very important to speed up the development and deployment of fast breeder reactors to avoid the future lack of uranium resources. (authors)

A rational approach to heavy-atom derivative screening

International Nuclear Information System (INIS)

Joyce, M. Gordon; Radaev, Sergei; Sun, Peter D.

2010-01-01

In order to overcome the difficulties associated with the ‘classical’ heavy-atom derivatization procedure, an attempt has been made to develop a rational crystal-free heavy-atom-derivative screening method and a quick-soak derivatization procedure which allows heavy-atom compound identification. Despite the development in recent times of a range of techniques for phasing macromolecules, the conventional heavy-atom derivatization method still plays a significant role in protein structure determination. However, this method has become less popular in modern high-throughput oriented crystallography, mostly owing to its trial-and-error nature, which often results in lengthy empirical searches requiring large numbers of well diffracting crystals. In addition, the phasing power of heavy-atom derivatives is often compromised by lack of isomorphism or even loss of diffraction. In order to overcome the difficulties associated with the ‘classical’ heavy-atom derivatization procedure, an attempt has been made to develop a rational crystal-free heavy-atom derivative-screening method and a quick-soak derivatization procedure which allows heavy-atom compound identification. The method includes three basic steps: (i) the selection of likely reactive compounds for a given protein and specific crystallization conditions based on pre-defined heavy-atom compound reactivity profiles, (ii) screening of the chosen heavy-atom compounds for their ability to form protein adducts using mass spectrometry and (iii) derivatization of crystals with selected heavy-metal compounds using the quick-soak method to maximize diffraction quality and minimize non-isomorphism. Overall, this system streamlines the process of heavy-atom compound identification and minimizes the problem of non-isomorphism in phasing