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Sample records for bar nuclear plant

  1. Applications of bar code technology at nuclear power plants

    International Nuclear Information System (INIS)

    Bar code is an emerging technology that can eliminate handwritten and keyboard data-entry errors. With application-specific software, bar code technology can provide inventory control, reducing staff time and paperwork. This paper summarizes bar code technology, describes hardware commercially available, and reviews application software systems for use in nuclear power plants

  2. Lead test assembly irradiation and analysis Watts Bar Nuclear Plant, Tennessee and Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    The U.S. Department of Energy (DOE) needs to confirm the viability of using a commercial light water reactor (CLWR) as a potential source for maintaining the nation's supply of tritium. The Proposed Action discussed in this environmental assessment is a limited scale confirmatory test that would provide DOE with information needed to assess that option. This document contains the environmental assessment results for the Lead test assembly irradiation and analysis for the Watts Bar Nuclear Plant, Tennessee, and the Hanford Site in Richland, Washington

  3. Safety evaluation report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2

    International Nuclear Information System (INIS)

    This report supplements the Safety Evaluation Report (SER), NUREG-0847 (June 1982), Supplement No. 1 (September 1982), Supplement No. 2 (January 1984), Supplement No. 3 (January 1985). Supplement No. 4 (March 1985), Supplement No. 5 (November 1990), Supplement No. 6 (April 1991), Supplement No. 7 (September 1991), Supplement No. 8 (January 1992). Supplement No. 9 (June 1992), Supplement No. 10 (October 1992), Supplement No. 11 (April 1993), Supplement No. 12 (October 1993). Supplement No. 13 (April 1994), Supplement No. 14 (December 1994), and Supplement No. 15 (June 1995) issued by the Office of Nuclear Reactor Regulation of the U.S. Nuclear Regulatory Commission with respect to the application filed by the Tennessee Valley Authority, as applicant and owner, for licenses to operate the Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos, 50-390 and 50-391). The facility is located in Rhea County, Tennessee, near the Watts Bar Dam on the Tennessee River. This supplement provides recent information regarding resolution of some of the outstanding and confirmatory items, and proposed license conditions identified in the SER

  4. Safety evaluation report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2, (Docket Nos. 50-390 and 50-391). Supplement No. 2

    International Nuclear Information System (INIS)

    This report supplements the Safety Evaluation Report, NUREG-0847 (June 1982) and Supplement No. 1 (September 1982), issued by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by the Tennessee Valley Authority, as applicant and owner, for licenses to operate the Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). The facility is located in Rhea County, Tennessee, near the Watts Bar Dam on the Tennessee River. This supplement provides recent information regarding resolution of some of the open and confirmatory items and license conditions identified in the Safety Evaluation Report

  5. Bar code usage in nuclear materials accountability

    International Nuclear Information System (INIS)

    The age old method of physically taking an inventory of materials by listing each item's identification number has lived beyond its usefulness. In this age of computerization, which offers the local grocery store a quick, sure, and easy means to inventory, it is time for nuclear materials facilities to automate accountability activities. The Oak Ridge Y-12 Plant began investigating the use of automated data collection devices in 1979. At that time, bar code and optical-character-recognition (OCR) systems were reviewed with the purpose of directly entering data into DYMCAS (Dynamic Special Nuclear Materials Control and Accountability System). Both of these systems appeared applicable; however, other automated devices already employed for production control made implementing the bar code and OCR seem improbable. However, the DYMCAS was placed on line for nuclear material accountability, a decision was made to consider the bar code for physical inventory listings. For the past several months a development program has been underway to use a bar code device to collect and input data to the DYMCAS on the uranium recovery operations. Programs have been completed and tested, and are being employed to ensure that data will be compatible and useful. Bar code implementation and expansion of its use for all nuclear material inventory activity in Y-12 is presented

  6. Preliminary systems-interaction results from the Digraph Matrix Analysis of the Watts Bar Nuclear Power Plant safety-injection systems

    Energy Technology Data Exchange (ETDEWEB)

    Sacks, I.J.; Ashmore, B.C.; Champney, J.M.; Alesso, H.P.

    1983-06-01

    This report provides preliminary results generated by a Digraph Matrix Analysis (DMA) for a Systems Interaction analysis performed on the Safety Injection System of the Tennessee Valley Authority Watts Bar Nuclear Power Plant. An overview of DMA is provided along with a brief description of the computer codes used in DMA.

  7. Bar code usage in nuclear materials accountability

    International Nuclear Information System (INIS)

    The Oak Ridge Y-12 Plant began investigating the use of automated data collection devices in 1979. At this time, bar code and optical-character-recognition (OCR) systems were reviewed with the purpose of directly entering data into DYMCAS (Dynamic Special Nuclear Materials Control and Accountability System). Both of these systems appeared applicable, however, other automated devices already employed for production control made implementing the bar code and OCR seem improbable. However, the DYMCAS was placed on line for nuclear material accountability, a decision was made to consider the bar code for physical inventory listings. For the past several months a development program has been underway to use a bar code device to collect and input data to the DYMCAS on the uranium recovery operations. Programs have been completed and tested, and are being employed to ensure that data will be compatible and useful. Bar code implementation and expansion of its use for all nuclear material inventory activity in Y-12 is presented

  8. Safety evaluation report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391): Supplement No. 19

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-11-01

    Supplement No. 19 to the Safety Evaluation Report for the application filed by the Tennessee Valley Authority for license to operate Watts Bar Nuclear Plant, Units 1 and 2, Docket Nos. 50-390 and 50-391, located in Rhea County Tennessee, has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission. The purpose of this supplement is to update the Safety Evaluation with (1) additional information submitted by the applicant since Supplement No. 18 was issued, and (2) matters that the staff had under review when Supplement No. 18 was issued.

  9. Safety evaluation report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391): Supplement No. 19

    International Nuclear Information System (INIS)

    Supplement No. 19 to the Safety Evaluation Report for the application filed by the Tennessee Valley Authority for license to operate Watts Bar Nuclear Plant, Units 1 and 2, Docket Nos. 50-390 and 50-391, located in Rhea County Tennessee, has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission. The purpose of this supplement is to update the Safety Evaluation with (1) additional information submitted by the applicant since Supplement No. 18 was issued, and (2) matters that the staff had under review when Supplement No. 18 was issued

  10. Safety Evaluation Report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). Supplement No. 12

    Energy Technology Data Exchange (ETDEWEB)

    Tam, P.S.

    1993-10-01

    Supplement No. 12 to the Safety Evaluation Report for the application filed by the Tennessee Valley Authority for license to operate Watts Bar Nuclear Plant, Units 1 and 2, Docket Nos. 50-390 and 50-391, located in Rhea County, Tennessee, has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission. The purpose of this supplement is to update the Safety Evaluation of (1) additional information submitted by the applicant since Supplement No. 11 was issued, and (2) matters that the staff had under review when Supplement No. 11 was issued.

  11. Safety evaluation report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). Supplement No. 14

    International Nuclear Information System (INIS)

    Supplement No. 14 to the Safety Evaluation Report for the application filed by the Tennessee Valley Authority for license to operate Watts Bar Nuclear Plant, Units 1 and 2, Docket Nos. 50-390 and 50-391, located in Rhea County, Tennessee, has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission. The purpose of this supplement is to update the Safety Evaluation with additional information submitted by the applicant since Supplement No. 13 was issued, and matters that the staff had under review when Supplement No. 13 was issued

  12. Safety Evaluation Report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391)

    International Nuclear Information System (INIS)

    Supplement No. 12 to the Safety Evaluation Report for the application filed by the Tennessee Valley Authority for license to operate Watts Bar Nuclear Plant, Units 1 and 2, Docket Nos. 50-390 and 50-391, located in Rhea County, Tennessee, has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission. The purpose of this supplement is to update the Safety Evaluation of (1) additional information submitted by the applicant since Supplement No. 11 was issued, and (2) matters that the staff had under review when Supplement No. 11 was issued

  13. Safety Evaluation Report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). Supplement No. 3

    International Nuclear Information System (INIS)

    This report supplements the Safety Evaluation Report, NUREG-0847 (June 1982), Supplement No. 1 (September 1982), and Supplement No. 2 (January 1984) issued by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by the Tennessee Valley Authority, as applicant and owner, for licenses to operate the Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). The facility is located in Rhea County, Tennessee, near the Watts Bar Dam on the Tennessee River. This supplement provides recent information regarding resolution of some of the open and confirmatory items and license conditions identified in the Safety Evaluation Report

  14. Safety Evaluation Report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391)

    International Nuclear Information System (INIS)

    This report supplements the Safety Evaluation Report (SER), NUREG-0847 (June 1982), Supplement No. 1 (September 1982), Supplement No. 2 (January 1984), Supplement No. 3 (January 1985), Supplement No. 4 (March 1985), Supplement No. 5 (November 1990), Supplement No. 6 (April 1991), Supplement No. 7 (September 1991), Supplement No. 8 (January 1992), and Supplement No. 9 (June 1992) issued by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by the Tennessee Valley Authority, as applicant and owner, for licenses to operate the Watts Bar Nuclear Plant, Units I and 2 (Docket Nos. 50-390 and 50-391). The facility is located in Rhea County, Tennessee, near the Watts Bar Dam on the Tennessee River. This supplement provides recent information regarding resolution of some of the outstanding and confirmatory items, and proposed license conditions identified in the SER

  15. Safety Evaluation Report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). Supplement No. 4

    International Nuclear Information System (INIS)

    This report supplements the Safety Evaluation Report, NUREG-0847 (June 1982), Supplement No. 1 (September 1982), Supplement No. 2 (January 1984), and Supplement No. 3 (January 1985) issued by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by the Tennessee Valley Authority, as applicant and owner, for licenses to operate the Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). The facility is located in Rhea County, Tennessee, near the Watts Bar Dam on the Tennessee River. This supplement provides recent information regarding resolution of some of the open and confirmatory items and license conditions identified in the Safety Evaluation Report

  16. Safety Evaluation Report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391)

    International Nuclear Information System (INIS)

    This report supplements the Safety Evaluation Report (SER), NUREG- 0847 (June 1982), Supplement No. 1' (September 1982), Supplement No. 2 (January 1984), Supplement No. 3 (January 1985), Supplement No. 4 (March 1985), and Supplement No. 5 (November 1990) issued by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory commission with respect to the application filed by the Tennessee Valley Authority, as applicant and owner, for licenses to operate the Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50--390 and 50--391). The facility is located in Rhea County, Tennessee, near the Watts Bar Dam on the Tennessee River. This supplement provides recent information regarding resolution of some of the outstanding and confirmatory items, and proposed license conditions identified in the SER

  17. Safety evaluation report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). Supplement No. 17

    Energy Technology Data Exchange (ETDEWEB)

    Tam, P.S.

    1995-10-01

    This report supplements the Safety Evaluation Report (SER), NUREG-0847 (June 1982), Supplement No. 1 (September 1982), Supplement No. 2 (January 1984), Supplement No. 3 (January 1985), Supplement No. 4 (March 1985), Supplement No. 5 (November 1990), Supplement No. 6 (April 1991), Supplement No. 7 (September 1991), 1991), Supplement No. 8 (January 1992), Supplement No. 9 (June 1992), Supplement No. 10 (October 1992), Supplement No. 11 (April.1993), Supplement No. 12 (October 1993), Supplement No. 13 (April 1994), Supplement No. 14 (December 1994), Supplement No. 15 (June 1995), and Supplement No. 16 (September 1995) issued by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by the Tennessee Valley Authority, as applicant and owner, for licenses to operate the Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50--390 and 50--391). The facility is located in Rhea county, Tennessee, near the Watts Bar Dam on the Tennessee River. In this supplement, NRC examines the significant problems of construction quality and quality assurance effectiveness that led TVA to withdraw its certification in 1985 that Watts Bar Unit I was ready to load fuel. Also discussed are the extensive corrective actions performed by TVA according to its nuclear performance plans and other supplemental programs, and NRC`s extensive oversight to determine whether the Watts Bar Unit 1 construction quality and TVA`s operational readiness and quality assurance effectiveness are adequate for a low-power operating license to be issued. SSER 17 does not address Watts Bar Unit 2, except for the systems which are necessary to support Unit 1 operation.

  18. {bar K}-NUCLEAR Deeply Bound States?

    Science.gov (United States)

    Gal, Avraham

    Following the prediction by Akaishi and Yamazaki of relatively narrow {bar K}-nuclear states, deeply bound by over 100 MeV where the main decay channel {bar K} N -> π Σ is closed, several experimental signals in stopped K- reactions on light nuclei have been interpreted recently as due to such states. In this talk I review (i) the evidence from K--atom data for a deep bar K-nucleus potential, as attractive as V{bar K}(ρ 0) ˜ -(150 - 200) MeV at nuclear matter density, that could support such states; and (ii) the theoretical arguments for a shallow potential, V{bar K}(ρ 0) ˜ -(40 - 60) MeV. I then review a recent work by Mareš, Friedman and Gal in which {bar K}-nuclear bound states are generated dynamically across the periodic table, using a RMF Lagrangian that couples the {bar K} to the scalar and vector meson fields mediating the nuclear interactions. The reduced phase space available for {bar K} absorption from these bound states is taken into account by adding a density- and energy-dependent imaginary term, underlying the corresponding {bar K}-nuclear level widths, with a strength constrained by K--atom fits. Substantial polarization of the core nucleus is found for light nuclei, with central nuclear densities enhanced by almost a factor of two. The binding energies and widths calculated in this dynamical model differ appreciably from those calculated for a static nucleus. These calculations provide a lower limit of Γ {bar K} ˜ 50 ± 10 MeV on the width of nuclear bound states for {bar K} binding energy in the range B{bar K} = 100 - 200 MeV.

  19. $\\bar K$-Nuclear Deeply Bound States?

    CERN Document Server

    Gal, A

    2006-01-01

    Following the prediction by Akaishi and Yamazaki of relatively narrow $\\bar K$-nuclear states, deeply bound by over 100 MeV where the main decay channel $\\bar K N \\to \\pi \\Sigma$ is closed, several experimental signals in stopped $K^-$ reactions on light nuclei have been interpreted recently as due to such states. In this talk I review (i) the evidence from $K^-$-atom data for a {\\it deep} $\\bar K$-nucleus potential, as attractive as $V_{\\bar K}(\\rho_0) \\sim -(150 - 200)$ MeV at nuclear matter density, that could support such states; and (ii) the theoretical arguments for a {\\it shallow} potential, $V_{\\bar K}(\\rho_0) \\sim -(40 - 60)$ MeV. I then review a recent work by Mare\\v{s}, Friedman and Gal in which $\\bar K$-nuclear bound states are generated dynamically across the periodic table, using a RMF Lagrangian that couples the $\\bar K$ to the scalar and vector meson fields mediating the nuclear interactions. Substantial polarization of the core nucleus is found for light nuclei, with central nuclear densities...

  20. Safety Evaluation Report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Numbers 50-390 and 50-391)

    International Nuclear Information System (INIS)

    This report supplements the Safety Evaluation Report (SER), NUREG-0847 (June 1982), Supplement No. 1 (September 1982), Supplement No. 2 (January 1984), Supplement No. 3 (January 1985), Supplement No. 4 (March 1985), Supplement No. 5 (November 1990), Supplement No. 6 (April 1991), Supplement No. 7 (September 1991), Supplement No. 8 (January 1992), Supplement No. 9 (June 1992), Supplement No. 10 (October 1992), Supplement No. 11 (April 1993), and Supplement No. 12 (October 1993), issued by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by the Tennessee Valley Authority, as applicant and owner, for licenses to operate the Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). The facility is located in Rhea County, Tennessee, near the Watts Bar Dam on the Tennessee River. This supplement provides recent information regarding resolution of some of the outstanding and confirmatory items, and proposed license conditions identified in the SER. These issues relate to: Design criteria -- structures, components, equipment, and systems; Reactor; Instrumentation and controls; Electrical power systems; Auxiliary systems; Conduct of operations; Accident analysis; and Quality assurance

  1. Safety evaluation report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). Supplement No. 15

    Energy Technology Data Exchange (ETDEWEB)

    Tam, P.S.

    1995-06-01

    This report supplements the Safety Evaluation Report (SER), NUREG-0847 (June 1982), Supplement No. 1 (September 1982), Supplement No. 2 (January 1984), Supplement No. 3 (January 1985), Supplement No. 4 (March 1985), Supplement No. 5 (November 1990), Supplement No. 6 (April 1991), Supplement No. 7 (September 1991), Supplement No. 8 (January 1992), Supplement No. 9 (June 1992), Supplement No. 10 (October 1992), Supplement No. 11 (April 1993), Supplement No. 12 (October 1993), Supplement No. 13 (April 1994), and Supplement No. 14 (December 1994) issued by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by the Tennessee Valley Authority, as applicant and owner, for licenses to operate the Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). The facility is located in Rhea County, Tennessee, near the Watts Bar Dam on the Tennessee River. This supplement provides recent information regarding resolution of some of the outstanding and confirmatory items, and proposed license conditions identified in the SER.

  2. Safety evaluation report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). Supplement No. 18

    Energy Technology Data Exchange (ETDEWEB)

    Tam, P.S.

    1995-10-01

    In June 1982, the Nuclear Regulatory Commission staff (NRC staff or staff) issued a Safety Evaluation Report, NUREG-0847, regarding the application by the Tennessee Valley Authority (TVA or the applicant) for licenses to operate the Watts Bar Nuclear Plant, Units 1 and 2. Each of the following sections and appendices of this supplement is numbered the same as the section or appendix of the SER that is being updated, and the discussions are supplementary to, and not in lieu of, the discussion in the SER, unless otherwise noted. Accordingly, Appendix A continues the chronology of the safety review. Appendix E lists principal contributors to this supplement. Appendix FF is added in this supplement. The other appendices are not changed by this supplement.

  3. Safety evaluation report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). Supplement No. 18

    International Nuclear Information System (INIS)

    In June 1982, the Nuclear Regulatory Commission staff (NRC staff or staff) issued a Safety Evaluation Report, NUREG-0847, regarding the application by the Tennessee Valley Authority (TVA or the applicant) for licenses to operate the Watts Bar Nuclear Plant, Units 1 and 2. Each of the following sections and appendices of this supplement is numbered the same as the section or appendix of the SER that is being updated, and the discussions are supplementary to, and not in lieu of, the discussion in the SER, unless otherwise noted. Accordingly, Appendix A continues the chronology of the safety review. Appendix E lists principal contributors to this supplement. Appendix FF is added in this supplement. The other appendices are not changed by this supplement

  4. NGC 4340 Double Bar + Fossil Nuclear Ring

    CERN Document Server

    Erwin, P; Beckman, J E

    2000-01-01

    NGC 4340 is a double-barred SB0 galaxy in the Virgo cluster (Wozniak et al. 1995, A&AS 111, 115). Here, we show that this galaxy also posseses a luminous stellar nuclear ring of relatively old stars with little or no gas. The ring lies just outside the inner bar, at the probable inner inner Lindblad resonance (IILR) of the outer bar. Careful inspection of the isophotes and unsharp masks shows that the two bars are slightly misaligned, which suggests they may be independently rotating. The bright nuclear ring distorts the isophotes and ellipse fits and is most clearly seen in the unsharp mask (an inner bar also visible). B-R color maps show no features associated with the ring: it is the same color as the surrounding bulge, and thus probably an old, ``fossil'' remnant of an earlier star-formation episode. We use Simien & Prugniel's (1997, A&AS 126, 15) major-axis velocities to compute resonance curves; we use our spectrum along the outer-bar major axis to estimate that bar's pattern speed. The Omeg...

  5. The Influence of Bars on Nuclear Activity

    CERN Document Server

    Ho, L C; Sargent, W L W; Ho, Luis C.; Filippenko, Alexei V.; Sargent, Wallace L. W.

    1997-01-01

    We test ideas on fueling of galactic nuclei by bar-driven inflow by comparing the detection rate and intensity of nuclear H II regions and AGNs among barred and unbarred galaxies in a sample of over 300 spirals selected from our recent optical spectroscopic survey of nearby galaxies. Among late-type spirals (Sc-Sm), but not early-type (S0/a-Sbc), we observe in the barred group a very marginal increase in the detection rate of H II nuclei and a corresponding decrease in the incidence of AGNs. The minor differences in the detection rates, however, are statistically insignificant, most likely stemming from selection effects and not from a genuine influence from the bar. The presence of a bar seems to have no noticeable impact on the likelihood of a galaxy to host either nuclear star formation or an AGN. The nuclei of early-type barred spirals do exhibit measurably higher star-formation rates than their unbarred counterparts, as indicated by either the luminosity or the equivalent width of H-alpha emission. By co...

  6. Bar code application to nuclear material accountancy

    International Nuclear Information System (INIS)

    For the purpose of efficient implementation of IAEA safeguards inspection, operators ought to prepare the information which is related to the strata for flow verification in a timely manner, such as physical inventory listing and summary of the fuel bundles. Today the use of bar code technique in tracing of products related data or counting number of items has been more and more applied to many facets of industry. From these points of view, the Japan Nuclear Fuel Company (NF) has been developing JNF Total Bar Code System. Now JNF has established an on-line input system of the fuel bundle accountability data by use of the bar code system to quickly prepare the information necessary for the inspection. As the first step, JNF implemented this bar code system at the flow verification to prepare physical inventory summary and location map of the fuel bundles in the storage. This paper reports that as a result of this, NF confirmed that this bar code system made it possible to input easily and quickly nuclear material accountancy information, and therefore this system is utilized as an effective and efficient measure of timely preparation for the inspection

  7. 77 FR 41811 - In the Matter of Tennessee Valley Authority Watts Bar Nuclear Plant EA-12-021; Confirmatory Order...

    Science.gov (United States)

    2012-07-16

    ... need for such training thereafter. f. TVA will enhance existing 10 CFR 50.9-related general employee training (GET) for new employees, including contractor and subcontractor employees located at TVA nuclear... training (both manager/supervisor as well as craft-level) to employees, including contractor...

  8. Bar code instrumentation for nuclear safeguards

    International Nuclear Information System (INIS)

    This paper presents a brief overview of the basic principles of bar codes and the equipment used to make and to read bar code labels, and a summary of some of the more important factors that need to be considered in integrating bar codes into an information system

  9. Hydrodynamical Simulations of Nuclear Rings in Barred Galaxies

    OpenAIRE

    Li, Zhi; Shen, Juntai; Kim, Woong-Tae

    2015-01-01

    Dust lanes, nuclear rings, and nuclear spirals are typical gas structures in the inner region of barred galaxies. Their shapes and properties are linked to the physical parameters of the host galaxy. We use high-resolution hydrodynamical simulations to study 2D gas flows in simple barred galaxy models. The nuclear rings formed in our simulations can be divided into two groups: one group is nearly round and the other is highly elongated. We find that roundish rings may not form when the bar pa...

  10. Final environmental statement related to the operation of Watts Bar Nuclear Plant, Units 1 and 2: Docket Numbers 50-390 and 50-391, Tennessee Valley Authority. Supplement Number 1

    International Nuclear Information System (INIS)

    The Final Environmental Statement-Operating License (FES-OL) issued in 1978 represents the Nuclear Regulatory Commission's (NRC's) previous environmental review related to the operation of Watts Bar Nuclear (WBN) Plant. The NRC staff has determined that it is appropriate to re-examine the issues associated with the environmental review before issuance of an operating license. The purpose of this NRC review is to discuss the effects of observed changes in the environment and to evaluate the changes in environmental impacts that have occurred as a result of changes in the WBN Plant design and proposed methods of operations since the last environmental review. A full scope of environmental topics has been evaluated, including regional demography, land and water use, meteorology, terrestrial and aquatic ecology, radiological and non-radiological impacts on humans and the environment, socioeconomic impacts, and environmental justice. The staff concluded that there are no significant changes in the environmental impacts since the NRC 1978 FES-OL from changes in plant design, proposed methods of operations, or changes in the environment. The Tennessee Valley Authority's (TVA's) preoperational and operational monitoring programs were reviewed and found to be appropriate for establishing baseline conditions and ongoing assessments of environmental impacts. The staff also conducted an analysis of plant operation with severe accident mitigation design alternatives (SAMDAs) and concluded that none of the SAMDAs, beyond the three procedural changes that the TVA committed to implement, would be cost-beneficial for further mitigating environmental impacts

  11. Systems interaction results from the digraph matrix analysis of the Watts Bar Nuclear Power Plant high pressure safety injection systems. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    Sacks, I.J.; Ashmore, B.C.; Alesso, H.P.

    1983-07-01

    Spatial and functional coupling (including human actions) of nuclear power plant systems that lead to interdependencies are called Systems Interactions. At present, the US Nuclear Regulatory Commission (NRC) is investigating ways of integrating a systems interactions study with existing Probabilistic Risk Assessment efforts. One approach is based on graph-theoretic methods utilizing matrix representations of logic diagrams called Digraph Matrix Analysis (DMA). The objective in this report is to demonstrate the capabilities of Digraph Matrix Analysis to model an accident sequence (including front-line systems, support systems and human actions) as a continuous, well-integrated logic model in order to identify and evaluate functional systems interactions. The selected accident sequence, loss of high pressure safety injection during a LOCA, was modeled and qualitative and quantitative comparisons were made to the Reactor Safety Study (WASH 1400) and other studies.

  12. Systems interaction results from the digraph matrix analysis of the Watts Bar Nuclear Power Plant high pressure safety injection systems. Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    Sacks, I.J.; Ashmore, B.C.; Alesso, H.P.

    1983-07-01

    Spatial and functional coupling of nuclear power plant systems that lead to interdependencies are called Systems Interactions. At present, the US Nuclear Regulatory Commission (NRC) is investigating ways of integrating a systems interactions study with existing Probabilistic Risk Assessment efforts. One approach is based on graph-theoretic methods utilizing matrix representations of logic diagrams called Digraph Matrix Analysis (DMA). The objective in this report is to demonstrate the capabilities of Digraph Matrix Analysis to model an accident sequence (including front line systems, support systems and human actions) as a continuous, well-integrated logic model in order to identify and evaluate functional systems interactions. The selected accident sequence, loss of high pressure safety injection during an S1 LOCA, was modeled and qualitative and quantitative comparisons were made to WASH 1400 aand other studies.

  13. Hydrodynamical Simulations of Nuclear Rings in Barred Galaxies

    Science.gov (United States)

    Li, Zhi; Shen, Juntai; Kim, Woong-Tae

    2015-08-01

    Dust lanes, nuclear rings, and nuclear spirals are typical gas structures in the inner region of barred galaxies. Their shapes and properties are linked to the physical parameters of the host galaxy. We use high-resolution hydrodynamical simulations to study 2D gas flows in simple barred galaxy models. The nuclear rings formed in our simulations can be divided into two groups: one group is nearly round and the other is highly elongated. We find that roundish rings may not form when the bar pattern speed is too high or the bulge central density is too low. We also study the periodic orbits in our galaxy models, and find that the concept of inner Lindblad resonance (ILR) may be generalized by the extent of x2 orbits. All roundish nuclear rings in our simulations settle in the range of x2 orbits (or ILRs). However, knowing the resonances is insufficient to pin down the exact location of these nuclear rings. We suggest that the backbone of round nuclear rings is the x2 orbital family, i.e. round nuclear rings are allowed only in the radial range of x2 orbits. A round nuclear ring forms exactly at the radius where the residual angular momentum of infalling gas balances the centrifugal force, which can be described by a parameter f_ring measured from the rotation curve. We find an empirical relation between the bar parameters and f_ring, and apply it to measure bar pattern speed in a sample of barred galaxies with nuclear rings.

  14. Formation of Nuclear Spirals in Barred Galaxies

    CERN Document Server

    Ann, H B; Thakur, Parijat

    2004-01-01

    We have performed smoothed particle hydrodynamics (SPH) simulations for the response of the gaseous disk to the imposed moderately strong non-axisymmetric potentials. The model galaxies are composed of the three stellar components (disk, bulge and bar) and two dark ones (supermassive black hole and halo) whose gravitational potentials are assumed to be invariant in time in the frame corotating with the bar. We found that the torques alone generated by the moderately strong bar that gives the maximum of tangential-to-radial force ratio as $(F_{Tan}/F_{Rad})_{max}= 0.3$ are not sufficient to drive the gas particles close to the center due to the barrier imposed by the inner Lindblad resonances (ILRs). In order to transport the gas particles towards the nucleus ($r<100$ pc), a central supermassive black hole (SMBH) and high sound speed of the gas are required to be present. The former is required to remove the inner inner Lindblad resonance (IILR) that prevents gas inflow close to the nucleus, while the latte...

  15. Impact on the bar value in hot by the introduction of advanced control bars in the Unit 1 of the Laguna Verde Nuclear power plant; Impacto sobre el valor de barra en caliente por la introduccion de barras de control avanzadas en la U1 de la CNLV

    Energy Technology Data Exchange (ETDEWEB)

    Montes, J.L.; Perusquia, R.; Ortiz, J.J.; Hernandez, J.L.; Ramirez, J.R. [ININ, Carretera Mexico-Toluca Km. 36.5, 52045 Estado de Mexico (Mexico)]. e-mail: jlmt@nuclear.inin.mx

    2004-07-01

    In recent dates the Laguna Verde Nuclear Power station (CNLV) has acquired new designs of control bars, this new type of bars presents modifications important in their design. For what is important to analyze their performance inside those reactors of this nuclear power station. Presently work is shown the behavior of the nucleus of the reactor in hot condition (HFP) when three different types of control bar are used. The first of them corresponds the one that initially has been used in this power station and that we will call original. The second type of control bars, it corresponds to an advanced type and it is the first design different from the original and it corresponds to a bar design that it includes Hafnium (Hf) like one of their neutronic absorption characteristics. The third, denoted as 2AV, include besides the material of the second type new design characteristics, and it is the last finish bar type that it has been introduced in the operation of the reactors of the CNLV. With base in the studied cases is found that the bars 2AV have a total power value, 7.6 % bigger respect the bars 1AV; and in turn the bars 1AV, 6.1 % bigger with respect the ORG control bars. (Author)

  16. Hydrodynamical Simulations of Nuclear Rings in Barred Galaxies

    CERN Document Server

    Li, Zhi; Kim, Woong-Tae

    2015-01-01

    Dust lanes, nuclear rings, and nuclear spirals are typical gas structures in the inner region of barred galaxies Their shapes and properties are linked to the physical parameters of the host galaxy. We use high-resolution hydrodynamical simulations to study 2D gas flows in simple barred galaxy models. The nuclear rings formed in our simulations can be divided into two groups: one group is nearly round and the other is highly elongated. We find that roundish rings may not form when the bar pattern speed is too high or the bulge central density is too low. We also study the periodic orbits in our galaxy models, and find that the concept of inner Lindblad resonance (ILR) may be generalized by the extent of $x_2$ orbits. All roundish nuclear rings in our simulations settle in the range of $x_2$ orbits (or ILRs). However, knowing the resonances is insufficient to pin down the exact location of these nuclear rings. We suggest that the backbone of round nuclear rings is the $x_2$ orbital family, i.e. round nuclear r...

  17. 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…

  18. Kondo effect of $\\bar{D}_{s}$ and $\\bar{D}_{s}^{\\ast}$ mesons in nuclear matter

    CERN Document Server

    Yasui, Shigehiro

    2016-01-01

    We study the Kondo effect for $\\bar{D}_{s}$ and $\\bar{D}_{s}^{\\ast}$ mesons as impurity particles in nuclear matter. The spin-exchange interaction between the $\\bar{D}_{s}$ or $\\bar{D}_{s}^{\\ast}$ meson and the nucleon induces the enhancement of the effective coupling in the low-energy scattering in the infrared region, whose scale of singularity is given by the Kondo scale. We investigate the Kondo scale in the renormalization group equation at nucleon one-loop level. We furthermore study the ground state with the Kondo effect in the mean-field approach, and present that the Kondo scale is related to the mixing strength between the $\\bar{D}_{s}$ or $\\bar{D}_{s}^{\\ast}$ meson and the nucleon in nuclear matter. We show the spectral function of the impurity when the Kondo effect occurs.

  19. Technical evaluation report TMI action -- NUREG-0737 (II.D.1). Relief and safety valve testing, Watts Bar Nuclear Plant, Units 1 and 2 (Dockets 50-390 and 50-391)

    International Nuclear Information System (INIS)

    In the past, safety and relief valves installed in the primary coolant system of light water reactors have performed improperly. As a result, the authors of NUREG-0578 (TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations) and, subsequently, NUREG-0737 (Clarification of TMI Action Plan Requirements) recommended development and completion of programs to do two things. First, they should reevaluate the functional performance capabilities of pressurized water reactor safety, relief, and block valves. Second, they should verify the integrity of the pressurizer safety and relief valve piping systems for normal, transient, and accident conditions. This report documents the review of those programs by Lockheed Idaho Technologies Company. Specifically, this report documents the review of the Watts Bar Nuclear Plant, Units 1 and 2, Applicant response to the requirements of NUREG-0578 and NUREG-0737. This review found the Applicant provided an acceptable response reconfirming they met General Design Criteria 14, 15, and 30 of Appendix A to 10 CFR 50 for the subject equipment. It should also be noted Lockheed Idaho performed this review for both Units 1 and 2. However, the applicability of this review to Unit 2 depends on verifying that the Unit 2 as-built system conforms to the Unit 1 design reviewed in this report

  20. Technical evaluation report TMI action -- NUREG-0737 (II.D.1). Relief and safety valve testing, Watts Bar Nuclear Plant, Units 1 and 2 (Dockets 50-390 and 50-391)

    Energy Technology Data Exchange (ETDEWEB)

    Fineman, C.P.

    1995-02-01

    In the past, safety and relief valves installed in the primary coolant system of light water reactors have performed improperly. As a result, the authors of NUREG-0578 (TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations) and, subsequently, NUREG-0737 (Clarification of TMI Action Plan Requirements) recommended development and completion of programs to do two things. First, they should reevaluate the functional performance capabilities of pressurized water reactor safety, relief, and block valves. Second, they should verify the integrity of the pressurizer safety and relief valve piping systems for normal, transient, and accident conditions. This report documents the review of those programs by Lockheed Idaho Technologies Company. Specifically, this report documents the review of the Watts Bar Nuclear Plant, Units 1 and 2, Applicant response to the requirements of NUREG-0578 and NUREG-0737. This review found the Applicant provided an acceptable response reconfirming they met General Design Criteria 14, 15, and 30 of Appendix A to 10 CFR 50 for the subject equipment. It should also be noted Lockheed Idaho performed this review for both Units 1 and 2. However, the applicability of this review to Unit 2 depends on verifying that the Unit 2 as-built system conforms to the Unit 1 design reviewed in this report.

  1. Nuclear power plant construction

    International Nuclear Information System (INIS)

    The legal aspects of nuclear power plant construction in Brazil, derived from governamental political guidelines, are presented. Their evolution, as a consequence of tecnology development is related. (A.L.S.L.)

  2. Nuclear Power Plant Technician

    Science.gov (United States)

    Randall, George A.

    1975-01-01

    The author recognizes a body of basic knowledge in nuclear power plant technoogy that can be taught in school programs, and lists the various courses, aiming to fill the anticipated need for nuclear-trained manpower--persons holding an associate degree in engineering technology. (Author/BP)

  3. Management of manufacture and installation of plant pipings by bar code system

    International Nuclear Information System (INIS)

    As for the piping system of nuclear power plants, the number of parts is very large, and the mill sheet is attached to each part, therefore, it is necessary to manage them individually, and large man power is required. In order to resolve the delay of mechanization in the factory, bar code system was adopted on full scale. At the time of taking parts out from the store, bar code labels are stuck to all piping parts. By this means, all the processes of manufacture and inspection are managed with a computer, and it is useful for labor saving and the prevention of mistaken input. This system is centering around the system of the progress management for piping manufacture, and is operated by being coupled with respective systems of production design, order and inventory, mill sheet management and installation management. The management of production design, manufacture, inspection and installation is explained. There is the problem of sticking bar code labels again as the labels become dirty or parts pass through coating and pickling processes. The direct carving of bar codes on parts by laser marker was tried, and it was successful for stainless steel, but in carbon steel pipes, it was hard to read. It is desirable to develop the bar codes which endure until the end of plant life. (K.I.)

  4. Safety evaluation report on Tennessee Valley Authority: Watts Bar Nuclear Performance Plan

    International Nuclear Information System (INIS)

    This safety evaluation report on the information submitted by the Tennessee Valley Authority in its Nuclear Performance Plan for the Watts Bar Nuclear Plant and in supporting documents has been prepared by the US Nuclear Regulatory Commission staff. The plan addresses the plant-specific corrective actions as part of the recovery program for licensing of Unit 1. The staff will be monitoring and inspecting the implementation of the programs. The plan does not address all licensing matters that will be required for fuel load and operation of Unit 1. Those remaining licensing matters have been addressed in previous safety evaluations or will be addressed in accordance with routing NRC licensing practices. 97 refs

  5. Nuclear Plant Inspection

    Science.gov (United States)

    1983-01-01

    Engineers from the Power Authority of the State of New York use a Crack Growth Analysis Program supplied by COSMIC (Computer Software Management and Information Center) in one stage of nuclear plant inspection. Welds of the nuclear steam supply system are checked for cracks; radiographs, dye penetration and visual inspections are performed to locate cracks in the metal structure and welds. The software package includes three separate crack growth analysis models and enables necessary repairs to be planned before serious problems develop.

  6. Initiative against nuclear power plants

    International Nuclear Information System (INIS)

    This publication of the Initiative of Austrian Nuclear Power Plant Opponents contains articles on radiactive waste dispoasal in Austria and and discusses safety issues of the nuclear power plant 'Zwentendorf'. (kancsar)

  7. Nuclear turbine power plant

    International Nuclear Information System (INIS)

    Purpose : To improve the heat cycle balance in a nuclear turbine power plant or the like equipped with a moisture separating and reheating device, by eliminating undesired overcooling of the drains in the pipes of a heat transmission pipe bundle. Constitution : A high pressure turbine is driven by main steams from a steam generator. The steams after driving the high pressure turbine are removed with moistures by way of a moisture separator and then re-heated. Extracted steams from the steam generator or the high pressure turbine are used as a heating source for the reheating. In the nuclear turbine power plant having such a constitution, a vessel for separating the drains and the steams resulted from the heat exchange is provided at the outlet of the reheating device and the steams in the vessel are introduced to the inlet of the moisture separator. (Aizawa, K.)

  8. Nuclear power plant

    International Nuclear Information System (INIS)

    Purpose: To suppress corrosion at the inner surfaces of equipments and pipeways in nuclear power plants. Constitution: An injection device comprising a chemical injection tank and a plunger type chemical injection pump for injecting hydrazine as an oxygen remover and ammonia as a pH controller is disposed to the downstream of a condensate desalter column for primary coolant circuits. Since dessolved oxygen in circuit water injected with these chemicals is substantially reduced to zero and pH is adjuted to about 10 - 11, occurrence of stress corrosion cracks in carbon steels and stainless steels as main constituent materials for the nuclear power plant and corrosion products are inhibited in high temperature water, and of corrosion products are inhibited from being introduced as they are through leakage to the reactor core, by which the operators' exposure does can be decreased significantly. (Sekiya, K.)

  9. Widths of $\\bar K$-nuclear deeply bound states in a dynamical model

    CERN Document Server

    Mares, J; Gal, A

    2004-01-01

    The relativistic mean field (RMF) model is applied to a system of nucleons and a $\\bar K$ meson, interacting via scalar and vector boson fields. The model incorporates the standard RMF phenomenology for bound nucleons and, for the $\\bar K$ meson, it relates to low-energy ${\\bar K}N$ and $K^-$ atom phenomenology. Deeply bound $\\bar K$ nuclear states are generated dynamically across the periodic table and are exhibited for $^{12}$C and $^{16}$O over a wide range of binding energies. Substantial polarization of the core nucleus is found for these light nuclei. Absorption modes are also included dynamically, considering explicitly the reduced phase space for $\\bar K$ absorption from deeply bound states. The behavior of the calculated width as function of the $\\bar K$ binding energy is studied in order to explore limits on the possible existence of narrow $\\bar K$ nuclear states.

  10. Nuclear fuel reprocessing plant

    International Nuclear Information System (INIS)

    The present invention concerns an improvement for corrosion resistance of the welded portion of materials which constitutes a reprocessing plant of spent nuclear fuels. That is, Mo-added austenite stainless steel is used for a plant member at the portion in contact with a nitric acid solution. Then, laser beams are irradiated to the welded portion of the plant member and the surface layer is heated to higher than 1,000degC. If such a heat treatment is applied, the degradation of corrosion resistance of the welded portion can be eliminated at the surface. Further, since laser beams are utilized, heating can be limited only to the surface. Accordingly, undesired thermal deformation of the plant members can be prevented. As a result, the plant member having high pit corrosion resistance against a dissolution solution for spent fuels containing sludges comprising insoluble residue and having resistance to nitric acid solution also in the welded portion substantially equal to that of the matrix can be attained. (I.S.)

  11. Obrigheim nuclear power plant

    International Nuclear Information System (INIS)

    In 1973 the 345 MW pressurized water nuclear power plant at Obrigheim operated on base load, generating approximately 2.63 TWh, approximately 2.5 TWh of which was supplied to the KWO members. The plant availability for the year was 89.9%. Of the 10.1% non-availability, 6.4% (23 d) was caused by refuelling, including inspection, overhaul and repair operations and routine tests carried out in September 1973. 3.3% was due to stoppages for repairs to a steam generator and the two main cooling pumps, while 0.4% resulted from failures in the electrical section of the plant. The plant was shut down seven times in all, including three scrams. The average core burnup at the end of the fourth cycle (1 September 1973) was 18900 MWd/tU, representing an average burnup of approximately 37500 MWd/tU for a fuel element used in all four cycles. The operating performance of the steam generators and the result of the steam generator inspection carried out during refuelling in 1973 suggest no progressive damage. The quantities of radioactive materials released to the environment in 1973 were well below the officially permitted levels. The availability of the plant from the beginning of pilot operation in 1969 to the end of 1973 was 83.7 %

  12. Obrigheim nuclear power plant

    International Nuclear Information System (INIS)

    The gross output of the 345MWe pressurized water nuclear power station at Obrigheim, operation on base load, amounted to about 2.57TWh in 1974, the net power fed to the grid being about 2.44TWh. The core was used to its full capacity until 10 May 1974. Thereafter, the reactor was on stretch-out operation with steadily decreasing load until refuelled in August 1974. Plant availability in 1974 amounted to 92.1%. Of the 7.9% non-availability, 7.87% was attributable to the refuelling operation carried out from 16 August to 14 September and to the inspection, overhaul and repair work and the routine tests performed during this period. The plant was in good condition. Only two brief shutdowns occurred in 1974, the total outage time being 21/2 hours. From the beginning of trial operation in March 1969 to the end of 1974, the plant achieved an availability factor of 85.2%. The mean core burnup at the end of the fifth cycle was 19600 MWd/tonne U, with one fuel element that had been used for four cycles achieving a mean burnup of 39000 MWd/tonne U. The sipping test on the fuel elements revealed defective fuel-rods in a prototype plutonium fuel element, a high-efficiency uranium fuel element and a uranium fuel element. The quantities of radioactive substances released to the environment in 1974 were far below the officially permitted values. In july 1974, a reference preparation made up in the nuclear power station in October 1973 was discovered by outsiders on the Obrigheim municipality rubbish tip. The investigations revealed that this reference preparation had very probably been abstracted from the plant in October 1973 and arrived at the rubbish tip in a most irregular manner shortly before its discovery

  13. Garigliano nuclear power plant

    International Nuclear Information System (INIS)

    During the period under review, the Garigliano power station produced 1,028,77 million kWh with a utilization factor of 73,41% and an availability factor of 85,64%. The disparity between the utilization and availability factors was mainly due to a shutdown of about one and half months owing to lack of staff at the plant. The reasons for nonavailability (14.36%) break down as follows: nuclear reasons 11,49%; conventional reasons 2,81%; other reasons 0,06%. During the period under review, no fuel replacements took place. The plant functioned throughout with a single reactor reticulation pump and resulting maximum available capacity of 150 MWe gross. After the month of August, the plant was operated at levels slightly below the maximum available capacity in order to lengthen the fuel cycle. The total number of outages during the period under review was 11. Since the plant was brought into commercial operation, it has produced 9.226 million kWh

  14. Practice of the bar reinforcement jointing technique in the second phase of Qinshan Nuclear Power Project

    International Nuclear Information System (INIS)

    The jointing modalities, including lapping, flash welding, sleeve cold squeezed jointing, tapered thread of uniform strength and straight thread, are utilized in the second phase of Qinshan Nuclear Power Project. The application of the mechanical joint of the large-diameter bars is introduced emphatically. Meanwhile the technical and economic comparison are given for several kinds of bar joint modalities

  15. Nuclear power plant

    International Nuclear Information System (INIS)

    Purpose: To prevent liquid wastes from being discharged out of the system by processing to recover them in the nuclear reactor and reusing them. Constitution: Discharge of liquid wastes to the surrounding atmosphere are completely eliminated by collecting floor drains, a part of processing water for the regeneration of liquid wastes, non-radioactive steam drains and laundry drains conventionally discharged so far out of the system, processing them in a concentrator, a desalter or the like into water of a high purity and extremely low radioactive concentration, storing the water in an exclusive storage tank and supplying it as a steam or supplementing water to each portion in the plant that requires water of such high purity and extremely low radioactivity. (Yoshihara, H.)

  16. Nuclear Power Plant

    Directory of Open Access Journals (Sweden)

    Analia Bonelli

    2012-01-01

    Full Text Available A description of the results for a Station Black-Out analysis for Atucha 2 Nuclear Power Plant is presented here. Calculations were performed with MELCOR 1.8.6 YV3165 Code. Atucha 2 is a pressurized heavy water reactor, cooled and moderated with heavy water, by two separate systems, presently under final construction in Argentina. The initiating event is loss of power, accompanied by the failure of four out of four diesel generators. All remaining plant safety systems are supposed to be available. It is assumed that during the Station Black-Out sequence the first pressurizer safety valve fails stuck open after 3 cycles of water release, respectively, 17 cycles in total. During the transient, the water in the fuel channels evaporates first while the moderator tank is still partially full. The moderator tank inventory acts as a temporary heat sink for the decay heat, which is evacuated through conduction and radiation heat transfer, delaying core degradation. This feature, together with the large volume of the steel filler pieces in the lower plenum and a high primary system volume to thermal power ratio, derives in a very slow transient in which RPV failure time is four to five times larger than that of other German PWRs.

  17. Nuclear Security for Floating Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Skiba, James M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Scherer, Carolynn P. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-10-13

    Recently there has been a lot of interest in small modular reactors. A specific type of these small modular reactors (SMR,) are marine based power plants called floating nuclear power plants (FNPP). These FNPPs are typically built by countries with extensive knowledge of nuclear energy, such as Russia, France, China and the US. These FNPPs are built in one country and then sent to countries in need of power and/or seawater desalination. Fifteen countries have expressed interest in acquiring such power stations. Some designs for such power stations are briefly summarized. Several different avenues for cooperation in FNPP technology are proposed, including IAEA nuclear security (i.e. safeguards), multilateral or bilateral agreements, and working with Russian design that incorporates nuclear safeguards for IAEA inspections in non-nuclear weapons states

  18. EMP and nuclear plant safety

    International Nuclear Information System (INIS)

    The electromagnetic pulse (EMP) from a high-altitude nuclear detonation consists of a transient pulse of high-intensity electromagnetic fields that induce current and voltage transients in electrical conductors. Although most nuclear power-plant cables are not directly exposed to these fields, the attenuated EMP fields that propagate into the plant will couple some EMP energy to these cables. The article attempts to predict the probable effects of the EMP transients that could be induced in critical circuits of safety-related systems. It is concluded that the most likely consequence of EMP for nuclear plants is an unscheduled shutdown. In general, EMP could be a nuisance to nuclear power plants, but it is not considered a serious threat to plant safety

  19. Nuclear Power Plant Simulation Game.

    Science.gov (United States)

    Weiss, Fran

    1979-01-01

    Presents a nuclear power plant simulation game which is designed to involve a class of 30 junior or senior high school students. Scientific, ecological, and social issues covered in the game are also presented. (HM)

  20. Using bar codes to manage radwaste in a nuclear power facility

    International Nuclear Information System (INIS)

    Maintaining accountability, and tracking the location of radioactive waste, has been simplified through the use of bar codes at the Peach Bottom and Limerick Power Plants. A system has been developed which utilizes portable, programmable bar code readers and a microcomputer to collect and report pertinent data on the generation and location of radwaste in the plant. The system, which was customized for each plant, was designed to collect data at the work place through the use of the portable bar code readers and menu cards. The program was designed in a modular format for easy modification and expansion and the system has been adapted for the tracking of equipment, tools, instruments, and respirators. The benefit from this inventory management system is more timely and accurate information for the control of radwaste generation, handling, storage, and shipping. The improved control has resulted in more efficient, cost effective radwaste operations, reduced radiation exposure to personnel, and a cleaner, more orderly plant

  1. Loviisa nuclear power plant analyzer

    International Nuclear Information System (INIS)

    The APROS Simulation Environment has been developed since 1986 by Imatran Voima Oy (IVO) and the Technical Research Centre of Finland (VTT). It provides tools, solution algorithms and process components for use in different simulation systems for design, analysis and training purposes. One of its main nuclear applications is the Loviisa Nuclear Power Plant Analyzer (LPA). The Loviisa Plant Analyzer includes all the important plant components both in the primary and in the secondary circuits. In addition, all the main control systems, the protection system and the high voltage electrical systems are included. (orig.)

  2. Maintenance of nuclear power plants

    International Nuclear Information System (INIS)

    This Safety Guide provides detailed guidance on the provisions of the Code on the Safety in Nuclear Power Plants: Operation, IAEA Safety Series No. 50-C-O(Rev.1) on the maintenance of structures, systems and components. Like the Code, the Guide forms part of the IAEA's programme, referred to as the NUSS programme, for establishing Codes and Safety Guides relating to nuclear power plants. Effective maintenance is essential for safe operation of a nuclear power plant. It not only ensures that the level of reliability and effectiveness of all plant structures, systems and components having a bearing on safety remains in accordance with design assumptions and intent, but also that the safety status of the plant is not adversely affected after commencement of operation. Nuclear power plant maintenance requires special attention because of: Limitations set by requirements that a minimum number of components remain operable even when the plant is shut down in order to ensure that all necessary safety functions are guaranteed; Difficulty of access to some plant items even when the plant is shut down, due to radiation protection constraints; Potential radiological hazards to site personnel and the public. This Guide covers the organizational and procedural aspects of maintenance but does not give detailed technical advice on the maintenance of particular plant items. It gives guidance on preventive and remedial measures necessary to ensure that all structures, systems and components important to safety are capable of performing as intended. The Guide covers the organizational and administrative requirements for establishing and implementing preventive maintenance schedules, repairing defective plant items, selecting and training maintenance personnel, providing maintenance facilities and equipment, procuring stores and spare parts, reviewing, controlling and carrying out plant modifications, and generating, collecting and retaining maintenance records for establishing and

  3. Investigating the Nuclear Activity of Barred Spiral Galaxies: The Case of NGC 1672

    Science.gov (United States)

    Jenkins, L. P.; Brandt, W. N.; Colbert, E. J.; Koribalski, B.; Kuntz, K. D.; Levan, A. J.; Ojha, R.; Roberts, T. P.; Ward, M. J.; Zezas, A.

    2011-01-01

    We have performed an X-ray study of the nearby barred spiral galaxy NGC 1672, primarily to ascertain the effect of the bar on its nuclear activity. We use both Chandra and XMM-Newton observations to investigate its X-ray properties, together with supporting high-resolution optical imaging data from the Hubble Space Telescope (HST) infrared imaging from the Spitzer Space Telescope, and Australia Telescope Compact Array ground-based radio data. We detect 28 X-ray sources within the D25 area of the galaxy; many are spatially correlated with star formation in the bar and spiral arms, and two are identified as background galaxies in the HST images. Nine of the X-ray sources are ultraluminous X-ray sources, with the three brightest (LX 5 * 10(exp 39) erg s(exp -1)) located at the ends of the bar. With the spatial resolution of Chandra, we are able to show for the first time that NGC 1672 possesses a hard (1.5) nuclear X-ray source with a 2-10 keV luminosity of 4 * 10(exp 38) erg s(exp -1). This is surrounded by an X-ray-bright circumnuclear star-forming ring, comprised of point sources and hot gas, which dominates the 2-10 keV emission in the central region of the galaxy. The spatially resolved multiwavelength photometry indicates that the nuclear source is a low-luminosity active galactic nucleus (LLAGN), but with star formation activity close to the central black hole. A high-resolution multiwavelength survey is required to fully assess the impact of both large-scale bars and smaller-scale phenomena such as nuclear bars, rings, and nuclear spirals on the fueling of LLAGN.

  4. World nuclear power plant capacity

    International Nuclear Information System (INIS)

    This report provides the background information for statistics and analysis developed by NUKEM in its monthly Market Report on the Nuclear Fuel Cycle. The assessments in this Special Report are based on the continuous review of individual nuclear power plant projects. This Special Report begins with tables summarizing a variety of nuclear power generating capacity statistics for 1990. It continues with a brief review of the year's major events regarding each country's nuclear power program. The standard NUKEM Market Report tables on nuclear plant capacity are given on pages 24 and 25. Owing to space limitations, the first year shown is 1988. Please refer to previous Special Reports for data covering earlier years. Detailed tables for each country list all existing plants as well as those expected by NUKEM to be in commercial operation by the end of 2005. An Appendix containing a list of abbreviations can be found starting on page 56. Only nuclear power plants intended for civilian use are included in this Special Report. Reactor lifetimes are assumed to be 35 years for all light water reactors and 30 years for all other reactor types, unless other data or definite decommissioning dates have been published by the operators. (orig./UA)

  5. Nuclear power plant

    International Nuclear Information System (INIS)

    The nuclear part with the negative pressure control system is installed in an underground chamber of a mountain. The containment consists of a sealing concrete layer directly sprayed to the rock and containing reinforcement inserts as well as of a consolidating concrete shell. The sealing concrete layer is combined with the rock by means of prestressed concrete tie rods. (DG)

  6. Nuclear plant undergrounding

    International Nuclear Information System (INIS)

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

  7. Submarine nuclear power plant

    International Nuclear Information System (INIS)

    Purpose: To provide a ballast tank, and nuclear power facilities within the containment shell of a pressure resistance structure and a maintenance operator's entrance and a transmission cable cut-off device at the outer part of the containment shell, whereby after the construction, the shell is towed, and installed by self-submerging, and it can be refloated for repairs by its own strength. Constitution: Within a containment shell having a ballast tank and a pressure resisting structure, there are provided nuclear power facilities including a nuclear power generating chamber, a maintenance operator's living room and the like. Furthermore, a maintenance operator's entrance and exit device and a transmission cable cut-off device are provided within the shell, whereby when it is towed to a predetermined a area after the construction, it submerges by its own strength and when any repair inspection is necessary, it can float up by its own strength, and can be towed to a repair dock or the like. (Yoshihara, H.)

  8. Use of hafnium in control bars of nuclear reactors; Uso de hafnio en barras de control de reactores nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Ramirez S, J.R.; Alonso V, G. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)]. e-mail: jrrs@nuclear.inin-mx

    2003-07-01

    Recently the use of hafnium as neutron absorber material in nuclear reactors has been reason of investigation by virtue of that this material has nuclear properties as to the neutrons absorption and structural that can prolong the useful life of the control mechanisms of the nuclear reactors. In this work some of those more significant hafnium properties are presented like nuclear material. Also there are presented calculations carried out with the HELIOS code for fuel cells of uranium oxide and of uranium and plutonium mixed oxides under controlled conditions with conventional bars of boron carbide and also with similar bars to which are substituted the absorbent material by metallic hafnium, the results are presented in this work. (Author)

  9. Elecnuc. Nuclear power plants in the world

    International Nuclear Information System (INIS)

    This 2003 version of Elecnuc contents information, data and charts on the nuclear power plants in the world and general information on the national perspectives concerning the electric power industry. The following topics are presented: 2002 highlights; characteristics of main reactor types and on order; map of the French nuclear power plants; the worldwide status of nuclear power plants on 2002/12/3; units distributed by countries; nuclear power plants connected to the Grid by reactor type groups; nuclear power plants under construction; capacity of the nuclear power plants on the grid; first electric generations supplied by a nuclear unit; electrical generation from nuclear plants by country at the end 2002; performance indicator of french PWR units; trends of the generation indicator worldwide from 1960 to 2002; 2002 cumulative Load Factor by owners; nuclear power plants connected to the grid by countries; status of license renewal applications in Usa; nuclear power plants under construction; Shutdown nuclear power plants; exported nuclear power plants by type; exported nuclear power plants by countries; nuclear power plants under construction or order; steam generator replacements; recycling of Plutonium in LWR; projects of MOX fuel use in reactors; electricity needs of Germany, Belgium, Spain, Finland, United Kingdom; electricity indicators of the five countries. (A.L.B.)

  10. Elecnuc. Nuclear power plants in the world

    International Nuclear Information System (INIS)

    This small booklet summarizes in tables all data relative to the nuclear power plants worldwide. These data come from the IAEA's PRIS and AREVA-CEA's GAIA databases. The following aspects are reviewed: 2007 highlights; Main characteristics of reactor types; Map of the French nuclear power plants on 2007/01/01; Worldwide status of nuclear power plants (12/31/2007); Units distributed by countries; Nuclear power plants connected to the Grid- by reactor type groups; Nuclear power plants under construction on 2007; Evolution of nuclear power plants capacities connected to the grid; First electric generations supplied by a nuclear unit in each country; Electrical generation from nuclear power plants by country at the end 2007; Performance indicator of French PWR units; Evolution of the generation indicators worldwide by type; Nuclear operator ranking according to their installed capacity; Units connected to the grid by countries at 12/31/2007; Status of licence renewal applications in USA; Nuclear power plants under construction at 12/31/2007; Shutdown reactors; Exported nuclear capacity in net MWe; Exported and national nuclear capacity connected to the grid; Exported nuclear power plants under construction; Exported and national nuclear capacity under construction; Nuclear power plants ordered at 12/31/2007; Long term shutdown units at 12/31/2007; COL (combined licences) applications in the USA; Recycling of Plutonium in reactors and experiences; Mox licence plants projects; Appendix - historical development; Meaning of the used acronyms; Glossary

  11. Docommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    The German utilities operating nuclear power plants have long concerned themselves with aspects of decommissioning and for this purpose an engineering company was given a contract to study the entire spectrum of decommissioning. The results of this study have been available in autumn 1980 and it is possible to discuss all the aspects of decommissioning on a new basis. Following these results no change in the design concept of LWR nuclear power plants in operation or under construction is necessary because the techniques, necessary for decommissioning, are fully available today. The technical feasibility of decommissioning for power plants of Biblis A and KRB type has been shown in detail. The calculations of the quantity of waste produced during removal of a nuclear power plant could be confirmed and it could be determined with high procedure. The radiation dose to the decommissioning personnel is in the range of the radiation protection regulations and is in the same range as the radiation dose to the personnel within a yearly inservice inspection. (AF)

  12. Providing emergency supply of nuclear power plants

    OpenAIRE

    ROZMILER, Jiří

    2013-01-01

    Work "Providing emergency power nuclear power plant" describes how solving their own consumption nuclear power plant, as emergency power supply is designed and how it should be a solution of known states of emergency, having an immediate impact on the power consumption of their own nuclear power plants. The aim of this thesis is to propose options to strengthen its own emergency power consumption of nuclear power plants, one might say-more resistant to harsh extremes, which could lead to loss...

  13. Investigating the nuclear activity of barred spiral galaxies: the case of NGC 1672

    CERN Document Server

    Jenkins, L P; Colbert, E J M; Koribalski, B; Kuntz, K D; Levan, A J; Ojha, R; Roberts, T P; Ward, M J; Zezas, A

    2011-01-01

    We have performed an X-ray study of the nearby barred spiral galaxy NGC1672, primarily to ascertain the effect of the bar on its nuclear activity. We use both Chandra and XMM-Newton observations to investigate its X-ray properties, together with supporting high-resolution optical imaging data from the Hubble Space Telescope (HST), infrared imaging from the Spitzer Space Telescope, and ATCA ground-based radio data. We detect 28 X-ray sources within the D25 area of the galaxy, many of which correlate spatially with star-formation in the bar and spiral arms, while two are identified as background galaxies in the HST images. Nine of the X-ray sources are ULXs, with the three brightest (LX > 5E39 erg/s) located at the ends of the bar. With the spatial resolution of Chandra, we are able to show for the first time that NGC1672 possesses a hard (Gamma~1.5) nuclear X-ray source with a 2-10 keV luminosity of 4E38 erg/s. This is surrounded by an X-ray bright circumnuclear star-forming ring, comprised of point sources an...

  14. QA programs in nuclear power plants

    International Nuclear Information System (INIS)

    As an overview of quality assurance programs in nuclear power plants, the energy picture as it appears today is reviewed. Nuclear power plants and their operations are described and an attempt is made to place in proper perspective the alleged ''threats'' inherent in nuclear power. Finally, the quality assurance programs being used in the nuclear industry are described

  15. Nuclear lamina in plant cells

    Institute of Scientific and Technical Information of China (English)

    汪健; 杨澄; 翟中和

    1996-01-01

    By using selective extraction and diethylene glycol distearate (DGD) embedment and embedment-free electron microscopy, the nuclear lamina was demonstrated in carrot and Ginkgo male generative cells. Western blotting revealed that the nuclear lamina was composed of A-type and B-type lamins which contained at least 66-ku and 84-ku or 66-ku and 86-ku polypeptides, respectively. These lamin proteins were localized at the nudear periphery as shown by immunogold-labelling. In situ hybridization for light microscope and electron microscope showed that plant cells have the homologous sequences of animal lamin cDNA. The sorting site of lamin mRNA is mainly distributed in the cytoplasm near the nudear envelope. The data have verified that there indeed exists nudear lamina in plant cells.

  16. Elecnuc. Nuclear power plants in the world

    International Nuclear Information System (INIS)

    This small booklet summarizes in tables all the numerical data relative to the nuclear power plants worldwide. These data come from the French CEA/DSE/SEE Elecnuc database. The following aspects are reviewed: 1997 highlights; main characteristics of the reactor types in operation, under construction or on order; map of the French nuclear power plants; worldwide status of nuclear power plants at the end of 1997; nuclear power plants in operation, under construction and on order; capacity of nuclear power plants in operation; net and gross capacity of nuclear power plants on the grid and in commercial operation; forecasts; first power generation of nuclear origin per country, achieved or expected; performance indicator of PWR units in France; worldwide trend of the power generation indicator; nuclear power plants in operation, under construction, on order, planned, cancelled, shutdown, and exported; planning of steam generators replacement; MOX fuel program for plutonium recycling. (J.S.)

  17. Nuclear power plants and environment

    International Nuclear Information System (INIS)

    The question of nuclear power plants is analysed in details. The fundamental principles of reactors are described as well as the problems of safety involved with the reactor operation and the quantity and type of radioactive released to the environment. It shows that the amount of radioactive is very long. The reactor accidents has occurred, as three mile island, are also analysed. (M.I.A.)

  18. Sabotage at Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Purvis, James W.

    1999-07-21

    Recently there has been a noted worldwide increase in violent actions including attempted sabotage at nuclear power plants. Several organizations, such as the International Atomic Energy Agency and the US Nuclear Regulatory Commission, have guidelines, recommendations, and formal threat- and risk-assessment processes for the protection of nuclear assets. Other examples are the former Defense Special Weapons Agency, which used a risk-assessment model to evaluate force-protection security requirements for terrorist incidents at DOD military bases. The US DOE uses a graded approach to protect its assets based on risk and vulnerability assessments. The Federal Aviation Administration and Federal Bureau of Investigation conduct joint threat and vulnerability assessments on high-risk US airports. Several private companies under contract to government agencies use formal risk-assessment models and methods to identify security requirements. The purpose of this paper is to survey these methods and present an overview of all potential types of sabotage at nuclear power plants. The paper discusses emerging threats and current methods of choice for sabotage--especially vehicle bombs and chemical attacks. Potential consequences of sabotage acts, including economic and political; not just those that may result in unacceptable radiological exposure to the public, are also discussed. Applicability of risk-assessment methods and mitigation techniques are also presented.

  19. Sabotage at Nuclear Power Plants

    International Nuclear Information System (INIS)

    Recently there has been a noted worldwide increase in violent actions including attempted sabotage at nuclear power plants. Several organizations, such as the International Atomic Energy Agency and the US Nuclear Regulatory Commission, have guidelines, recommendations, and formal threat- and risk-assessment processes for the protection of nuclear assets. Other examples are the former Defense Special Weapons Agency, which used a risk-assessment model to evaluate force-protection security requirements for terrorist incidents at DOD military bases. The US DOE uses a graded approach to protect its assets based on risk and vulnerability assessments. The Federal Aviation Administration and Federal Bureau of Investigation conduct joint threat and vulnerability assessments on high-risk US airports. Several private companies under contract to government agencies use formal risk-assessment models and methods to identify security requirements. The purpose of this paper is to survey these methods and present an overview of all potential types of sabotage at nuclear power plants. The paper discusses emerging threats and current methods of choice for sabotage--especially vehicle bombs and chemical attacks. Potential consequences of sabotage acts, including economic and political; not just those that may result in unacceptable radiological exposure to the public, are also discussed. Applicability of risk-assessment methods and mitigation techniques are also presented

  20. Effects of spiral arms on star formation in nuclear rings of barred-spiral galaxies

    International Nuclear Information System (INIS)

    We use hydrodynamic simulations to study the effect of spiral arms on the star formation rate (SFR) in nuclear rings of barred-spiral galaxies. We find that spiral arms can be an efficient means of gas transport from the outskirts to the central parts, provided that the arms are rotating slower than the bar. While the ring star formation in models with no arms or corotating arms is active only during around the bar growth phase, arm-driven gas accretion both significantly enhances and prolongs the ring star formation in models with slow-rotating arms. The arm-enhanced SFR is larger by a factor of ∼3-20 than in the no-arm model, with larger values corresponding to stronger and slower arms. Arm-induced mass inflows also make dust lanes stronger. Nuclear rings in slow-arm models are ∼45% larger than in the no-arm counterparts. Star clusters that form in a nuclear ring exhibit an age gradient in the azimuthal direction only when the SFR is small, whereas no notable age gradient is found in the radial direction for models with arm-induced star formation.

  1. Effects of Spiral Arms on Star Formation in Nuclear Rings of Barred-spiral Galaxies

    CERN Document Server

    Seo, Woo-Young

    2014-01-01

    We use hydrodynamic simulations to study the effect of spiral arms on the star formation rate (SFR) occurring in nuclear rings of barred-spiral galaxies. We find that spiral arms can be an efficient means of gas transport from the outskirts to the central parts, provided that the arms are rotating slower than the bar. While the ring star formation in models with no-arm or corotating arms is active only during about the bar growth phase, arm-driven gas accretion makes the ring star formation both enhanced and prolonged significantly in models with slow-rotating arms. The arm-enhanced SFR is larger by a factor of ~ 3-20 than in the no-arm model, with larger values corresponding to stronger and slower arms. Arm-induced mass inflows also make dust lanes stronger. Nuclear rings in slow-arm models are ~ 45% larger than in the no-arm counterparts. Star clusters that form in a nuclear ring exhibit an age gradient in the azimuthal direction only when the SFR is small, whereas no noticeable age gradient is found in the...

  2. Modelling of nuclear power plant decommissioning financing.

    Science.gov (United States)

    Bemš, J; Knápek, J; Králík, T; Hejhal, M; Kubančák, J; Vašíček, J

    2015-06-01

    Costs related to the decommissioning of nuclear power plants create a significant financial burden for nuclear power plant operators. This article discusses the various methodologies employed by selected European countries for financing of the liabilities related to the nuclear power plant decommissioning. The article also presents methodology of allocation of future decommissioning costs to the running costs of nuclear power plant in the form of fee imposed on each megawatt hour generated. The application of the methodology is presented in the form of a case study on a new nuclear power plant with installed capacity 1000 MW. PMID:25979740

  3. Nuclear Plant Integrated Outage Management

    International Nuclear Information System (INIS)

    This paper is a discussion of an emerging concept for improving nuclear plant outage performance - integrated outage management. The paper begins with an explanation of what the concept encompasses, including a scope definition of the service and descriptions of the organization structure, various team functions, and vendor/customer relationships. The evolvement of traditional base scope services to the integrated outage concept is addressed and includes discussions on changing customer needs, shared risks, and a partnership approach to outages. Experiences with concept implementation from a single service in 1984 to the current volume of integrated outage management presented in this paper. We at Westinghouse believe that the operators of nuclear power plants will continue to be aggressively challenged in the next decade to improve the operating and financial performance of their units. More and more customers in the U. S. are looking towards integrated outage as the way to meet these challenges of the 1990s, an arrangement that is best implemented through a long-term partnering with a single-source supplier of high quality nuclear and turbine generator outage services. This availability, and other important parameters

  4. Molecular Gas Dynamics in NGC 6946: a Bar-driven Nuclear Starburst "Caught in the Act"

    CERN Document Server

    Schinnerer, E; Emsellem, E; Lisenfeld, U

    2006-01-01

    We present high angular resolution ~1" and 0.6" mm-interferometric observations of the 12CO(1-0) and 12CO(2-1) line emission in the central 300pc of the late-type spiral galaxy NGC6946. The data, obtained with the IRAM Plateau de Bure Interferometer (PdBI), allow the first detection of a molecular gas spiral in the inner ~10" (270pc) with a large concentration of molecular gas (M(H_2) ~1.6x10^7M_sun) within the inner 60pc. This nuclear clump shows evidence for a ring-like geometry with a radius of ~10pc as inferred from the p-v diagrams. Both the distribution of the molecular gas as well as its kinematics can be well explained by the influence of an inner stellar bar of about 400pc length. A qualitative model of the expected gas flow shows that streaming motions along the leading sides of this bar are a plausible explanation for the high nuclear gas density. Thus, NGC6946 is a prime example of molecular gas kinematics being driven by a small-scale, secondary stellar bar.

  5. Design of nuclear power plants

    International Nuclear Information System (INIS)

    The criteria of design and safety, applied internationally to systems and components of PWR type reactors, are described. The main criteria of the design analysed are: thermohydraulic optimization; optimized arrangement of buildings and components; low costs of energy generation; high level of standardization; application of specific safety criteria for nuclear power plants. The safety criteria aim to: assure the safe reactor shutdown; remove the residual heat and; avoid the release of radioactive elements for environment. Some exemples of safety criteria are given for Angra-2 and Angra-3 reactors. (M.C.K.)

  6. Information technology for nuclear plant

    International Nuclear Information System (INIS)

    Sixteen papers are included. The first session covers the collection, storage and processing of relevant data (configuration management, the NEA reporting system and reliability data collection). The second group of papers is concerned with training and emergency control including simulation. The third session concerned plant control and maintenance including hardware and software problems. The final session is about artificial intelligence and expert systems applied to industrial management and control. An additional paper is about improved information exchange among nuclear operators. All papers are indexed separately. (UK)

  7. Multiprocessing in nuclear plant simulation

    International Nuclear Information System (INIS)

    This thesis describes the development of a multiprocessor for Nuclear Plant Simulation. A summary of the main features of continuous system simulation languages is presented. These languages simplify the development of simulation models by allowing the user to specify his program in a form closely related to its mathematical formulation. Existing computer architectures are studied for their suitability for the heavy computing requirements of simulation models. These are not well suited to the characteristics of simulation and hence do not yield the required performance. A novel computer architecture is described. This architecture is specially designed to match the characteristics of nuclear plant simulation. The author has developed a simulation language for the multiprocessor and has written a compiler for the language. The compiler has two special passes to analyse and partition the model so that the user can run programs on the multiprocessor transparently. Results from running real models on the multiprocessor have demonstrated the potential of the architecture and highlighted areas for future developments. (author)

  8. Testing Transgenic Aspen Plants with bar Gene for Herbicide Resistance under Semi-natural Conditions.

    Science.gov (United States)

    Lebedev, V G; Faskhiev, V N; Kovalenko, N P; Shestibratov, K A; Miroshnikov, A I

    2016-01-01

    Obtaining herbicide resistant plants is an important task in the genetic engineering of forest trees. Transgenic European aspen plants (Populus tremula L.) expressing the bar gene for phosphinothricin resistance have been produced using Agrobacterium tumefaciens-mediated transformation. Successful genetic transformation was confirmed by PCR analysis for thirteen lines derived from two elite genotypes. In 2014-2015, six lines were evaluated for resistance to herbicide treatment under semi-natural conditions. All selected transgenic lines were resistant to the herbicide Basta at doses equivalent to 10 l/ha (twofold normal field dosage) whereas the control plants died at 2.5 l/ha. Foliar NH4-N concentrations in transgenic plants did not change after treatment. Extremely low temperatures in the third ten-day period of October 2014 revealed differences in freeze tolerance between the lines obtained from Pt of f2 aspen genotypes. Stable expression of the bar gene after overwintering outdoors was confirmed by RT-PCR. On the basis of the tests, four transgenic aspen lines were selected. The bar gene could be used for retransformation of transgenic forest trees expressing valuable traits, such as increased productivity.

  9. Operation of Finnish nuclear power plants

    International Nuclear Information System (INIS)

    Quarterly reports on the operation of Finnish nuclear power plants describe events and observations, relating to nuclear and radiation safety, which the Finnish Centre for Radiation and Nuclear Safety considers significant. Also other events of general interest are reported. The reports also include a summary of the radiation safety of plant personnel and the environment, as well as tabulated data on the plants' production and load factors

  10. TOSHIBA CAE system for nuclear power plant

    International Nuclear Information System (INIS)

    TOSHIBA aims to secure safety, increase reliability and improve efficiency through the engineering for nuclear power plant using Computer Aided Engineering (CAE). TOSHIBA CAE system for nuclear power plant consists of numbers of sub-systems which had been integrated centering around the Nuclear Power Plant Engineering Data Base (PDBMS) and covers all stage of engineering for nuclear power plant from project management, design, manufacturing, construction to operating plant service and preventive maintenance as it were 'Plant Life-Cycle CAE System'. In recent years, TOSHIBA has been devoting to extend the system for integrated intelligent CAE system with state-of-the-art computer technologies such as computer graphics and artificial intelligence. This paper shows the outline of CAE system for nuclear power plant in TOSHIBA. (author)

  11. Nuclear Power Plant Lifetime Management Study (I)

    Energy Technology Data Exchange (ETDEWEB)

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

    1996-12-31

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

  12. Data retrieval techniques for nuclear power plants

    International Nuclear Information System (INIS)

    Data retrieval, processing retrieved data, and maintaining the plant documentation system to reflect the as-built condition of the plant are challenging tasks for most existing nuclear facilities. The information management systems available when these facilities were designed and constructed are archaic by today's standards. Today's plant documentation systems generally include hard copy drawings and text, drawings in various CAD formats, handwritten information, and incompatible databases. These existing plant documentation systems perpetuate inefficiency for the plant technical staff in the performance of their daily activities. This paper discusses data retrieval techniques and tools available to nuclear facilities to minimize the impacts of the existing plant documentation system on plant technical staff productivity

  13. Search for K(bar) nuclear clusters in proton induced reactions with FOPI at GSI

    International Nuclear Information System (INIS)

    Full text: Recently the existence of exotic nuclear states involving K(bar) was predicted. It was argued that the attractive I = 0 K(bar) N force acts as a mediator, which allows the formation of deeply bound kaonic states which are commonly referred to as kaonic nuclear clusters. The lightest of these systems, K-pp was predicted to exist with a mass of 2.32 GeV/c2, a width of 61 MeV and with an average density of 3 times the normal nuclear density. Independent calculations confirmed the possible existence of these states, however with varying properties. Different techniques to produce and measure kaonic nuclear clusters have been proposed and a few attempts have been made to experimentally prove their existence. However, the results so far are not conclusive. In 2005 we started a program at GSI with the goal to produce K-pp in p+d/C reactions and to verify its creation with the FOPI detector by means of an invariant mass and missing mass analysis. A first test experiment was carried out in Fall 2005. Based on this experience a new proposal was worked out to investigate the reaction p + p → K-pp + K+, which was approved by the Program Advisory Committee of GSI. In this talk we will report on the results from the test experiment and line out the concepts of the newly proposed experiment.With the limited statistics obtained during the test experiment it was not possible to verify or rule out the existence of kaonic nuclear clusters. However, the data was used to test data analysis concepts and allowed to identify possibilities for improvement of the experimental setup for the follow-up experiment. (author)

  14. Dukovany nuclear power plant safety

    International Nuclear Information System (INIS)

    Presentation covers recommended safety issues for the Dukovany NPP which have been solved with satisfactory conclusions. Safety issues concerned include: radiation safety; nuclear safety; security; emergency preparedness; health protection at work; fire protection; environmental protection; chemical safety; technical safety. Quality assurance programs at all stages on NPP life time is described. Report includes description of NPP staff training provision, training simulator, emergency operating procedures, emergency preparedness, Year 2000 problem, inspections and life time management. Description of Dukovany Plant Safety Analysis Projects including integrity of the equipment, modernisation, equipment innovation and safety upgrading program show that this approach corresponds to the actual practice applied in EU countries, and fulfilment of current IAEA requirements for safety enhancement of the WWER 440/213 units in the course of MORAWA Equipment Upgrading program

  15. Program increasing of nuclear power plant safeness

    International Nuclear Information System (INIS)

    The results achieved within the project of national task 'Program increasing of nuclear power plant safeness' are presented in the document. The project was aimed to extend and deepen activities relating to safety increase of nuclear power units WWER-440 which play significant part in electricity production in the Slovak Republic. The application of advanced foreign calculating programs and calculation of radionuclide spreading in environment and techniques will influence the increase of extent, quality and international acceptance of safety analysis of nuclear power plant blocks WWER-440 and the risk valuation from operating nuclear power plants. Methodic resources for coping in emergency situation in nuclear energetics will be used for support in decision making in real time during radiation emergency on nuclear plant, region and state level. A long-term strategy in dealing with burnt fuel and radioactive substance formatting during nuclear power plant liquidation particularly with waste which is un acceptable in regional dump, has developed into a theoretical and practical preparation of solvable group for operating the converting centre Bohunice and in inactivating the nuclear power plant A-1. The diagnostic activities in nuclear power plants in the Slovak Republic have been elaborated into a project of norm documents in accordance with international norms for diagnostic systems. Presentation of new technologies and materials for repairs and reconstructions of components and nuclear power plant knots qualify increase in their reliability, safety and life. New objective methods and criterions for valuation and monitoring of the residual life and safety of fixed nuclear power plants. Results of problem solving linked with connecting the blocks of nuclear power plants to frequency regulation in electric network in the Slovak Republic are also presented in the document

  16. Medical consequences of a nuclear plant accident

    International Nuclear Information System (INIS)

    The report gives background information concerning radiation and the biological medical effects and damages caused by radiation. The report also discusses nuclear power plant accidents and efforts from the medical service in the case of a nuclear power plant accident. (L.F.)

  17. Nuclear power plants for protecting the atmosphere

    International Nuclear Information System (INIS)

    Some figures are presented comparing date on the CO2 emission and oxygen consumption of nuclear, natural gas fired, advanced coal fired and oil fired power plants, for the same amounts of electricity generated. The data were deduced from the Paks Nuclear Power Plant, Hungary. (R.P.)

  18. Plant nuclear proteomics for unraveling physiological function.

    Science.gov (United States)

    Yin, Xiaojian; Komatsu, Setsuko

    2016-09-25

    The nucleus is the subcellular organelle that functions as the regulatory hub of the cell and is responsible for regulating several critical cellular functions, including cell proliferation, gene expression, and cell survival. Nuclear proteomics is a useful approach for investigating the mechanisms underlying plant responses to abiotic stresses, including protein-protein interactions, enzyme activities, and post-translational modifications. Among abiotic stresses, flooding is a major limiting factor for plant growth and yields, particularly for soybean. In this review, plant nuclei purification methods, modifications of plant nuclear proteins, and recent contributions to the field of plant nuclear proteomics are summarized. In addition, to reveal the upstream regulating mechanisms controlling soybean responses to flooding stress, the functions of flooding-responsive nuclear proteins are reviewed based on the results of nuclear proteomic analysis of soybean in the early stages of flooding stress. PMID:27004615

  19. Nuclear reactor kinetics and plant control

    CERN Document Server

    Oka, Yoshiaki

    2013-01-01

    Understanding time-dependent behaviors of nuclear reactors and the methods of their control is essential to the operation and safety of nuclear power plants. This book provides graduate students, researchers, and engineers in nuclear engineering comprehensive information on both the fundamental theory of nuclear reactor kinetics and control and the state-of-the-art practice in actual plants, as well as the idea of how to bridge the two. The first part focuses on understanding fundamental nuclear kinetics. It introduces delayed neutrons, fission chain reactions, point kinetics theory, reactivit

  20. Human factors in nuclear power plant operations

    International Nuclear Information System (INIS)

    This report describes some of the human factors problems in nuclear power plants and the technology that can be employed to reduce those problems. Many of the changes to improve the human factors in existing plants are inexpensive, and the expected gain in human reliability is substantial. The human factors technology is well-established and there are practitioners in most countries that have nuclear power plants

  1. Human factors in nuclear power plants

    International Nuclear Information System (INIS)

    This report describes some of the human factors problems in nuclear power plants and the technology that can be employed to reduce those problems. Many of the changes to improve the human factors in existing plants are inexpensive, and the expected gain in human reliability is substantial. The human factors technology is well-established and there are practitioners in most countries that have nuclear power plants. (orig.)

  2. Maintenance of nuclear power plant

    International Nuclear Information System (INIS)

    Maintenance action of nuclear power plant (NPP) was described. Maintenance of NPP aimed at assurance of required function of NPP's equipment so as to prevent release of radioactive materials into the environment as well as attainment of stable operation of NPP. Philosophy of NPP safety was based on defense-in-depth or multiple barriers requiring specified function for the equipment. Preventive maintenance was essential to NPP's equipment and the scope of maintenance was decided on priority with adequate method and frequency of inspection. Most inspection was conducted during periodic inspection at outage. Repair or improvement works were performed if needed. Periodic inspection period was very long and then capacity factor of NPP was low in Japan compared with foreign data although frequency of unscheduled shutdown was very low. Introduction of reability- centered maintenance was requested based on past experiences of overhaul inspection. Technical evaluation of aged NPP had been conducted on aging phenomena and promotion of advanced maintenance was more needed. (T. Tanaka)

  3. Citizens contra nuclear power plants

    International Nuclear Information System (INIS)

    Is Wyhl the beginning of a new citizens' movement against official policies concerning atomic energy or is it the end of citizens' initiatives of latter years. Did democracy pass its test in Wyhl, or was the state's authority undermined. The danger of atomic energy was not the only concern of the citizens of the Rhine valley who demonstrated against the planned nuclear power plant, but also the quality of industrial and energy planning in which the democratic foundations have to be safeguarded. In the meantime, the doubts increase that this source of energy is of a not dangerous nature, and the myth of supposedly cheap atomic energy has been scattered. The dangers in connection with waste transport and storage were made public beyond the boundaries of the places in question, in particular as a result of the demonstrations. The publication documents the course of the demonstration and the site occupation from the beginning of Febuary 1975 onwards. The occupation still continued when the booklet was published despite the decision of the Administrative Court in Freiburg at the end of March (prohibition of commencement of building until the verdict on the principal suit against the overall project has been reached, the final decision to be made by the Higher Administrative Court in Mannheim). The author aims at describing the new quality of citizens' commitments in this booklet. (orig./LN)

  4. Economic performance of nuclear plants: How competitive

    International Nuclear Information System (INIS)

    There is no uniquely correct cost for nuclear or other modes of electricity production, and there is little to be gained by seeking complete standardization of reference values used in making cost comparisons, for example, between nuclear and fossil-fuelled power plants. Even at the national level, such inter-fuel comparisons (nuclear versus fossil) have only limited ''generic'' value, due to the number of assumptions and operating conditions that are behind each example. Nevertheless, results from such studies can contribute to an improved understanding of the worldwide economic viability of nuclear power. Therefore, this article reviews some of the reported experience with nuclear power economic performance and estimates of future nuclear power costs, in comparison with fossil-fuel-fired plants. It is reemphasized, however, that the cost data presented should not be used as reference data for planning purposes, but are valid only to give an overall indication of the general economic competitiveness of nuclear power

  5. Nuclear power plant cable materials :

    Energy Technology Data Exchange (ETDEWEB)

    Celina, Mathias Christopher; Gillen, Kenneth T; Lindgren, Eric Richard

    2013-05-01

    A selective literature review was conducted to assess whether currently available accelerated aging and original qualification data could be used to establish operational margins for the continued use of cable insulation and jacketing materials in nuclear power plant environments. The materials are subject to chemical and physical degradation under extended radiationthermal- oxidative conditions. Of particular interest were the circumstances under which existing aging data could be used to predict whether aged materials should pass loss of coolant accident (LOCA) performance requirements. Original LOCA qualification testing usually involved accelerated aging simulations of the 40-year expected ambient aging conditions followed by a LOCA simulation. The accelerated aging simulations were conducted under rapid accelerated aging conditions that did not account for many of the known limitations in accelerated polymer aging and therefore did not correctly simulate actual aging conditions. These highly accelerated aging conditions resulted in insulation materials with mostly inert aging processes as well as jacket materials where oxidative damage dropped quickly away from the air-exposed outside jacket surface. Therefore, for most LOCA performance predictions, testing appears to have relied upon heterogeneous aging behavior with oxidation often limited to the exterior of the cable cross-section a situation which is not comparable with the nearly homogenous oxidative aging that will occur over decades under low dose rate and low temperature plant conditions. The historical aging conditions are therefore insufficient to determine with reasonable confidence the remaining operational margins for these materials. This does not necessarily imply that the existing 40-year-old materials would fail if LOCA conditions occurred, but rather that unambiguous statements about the current aging state and anticipated LOCA performance cannot be provided based on

  6. Development of SC structure modularization in Nuclear Power Plant

    International Nuclear Information System (INIS)

    New Focus on NPP are Rising Concerns on Global Warming, Potential energy crisis (geo-political), Improved reliability and safety of nuclear power plant, Advent of Generation 3+ NPP technology and Economical Energy Resource. New NPPs are 6 units in Korea and 23 in Asia being built, 32 units being planned in China by 2020 (150 by 2050), 10 units being planned in US by 2020 and IAEA expects $200 billions on NPP construction next 25 years (up to 30% of total world energy). □ SC(Steel Plate Concrete) structure · Steel Plate is used as a Structural Element instead of Reinforcing Bars in RC · SC structure consists of Steel Plate with Headed Studs. Connected by Tie-bars - The Primary Purpose of Tie-bars is to Stiffen and Hold Together the Plates during Construction Process - Headed Studs are Welded to the Inside of Steel Plate for composite action □ Benefits of SC Structure · Shorten Construction Duration for Re bar, Forming and Scaffolding Works · Minimize Site Labors · Improve the Construction Quality · Enable Construction Sites to be kept Clean □ SC Modularization · Fit for Modular Construction for Structural Features · Fit for Modular Construction for Structural Features · Inattentively Effective for Integrated Modules · Pre-fabrication, Pre-assembly and Modularization □ Project Overview · Project Name: Development of SC structure for Modularization in NPP · Project Type: Electric Power Industry R and D (Ministry of Knowledge Economy) · Duration: Sep. 2005 ∼ Aug. 2008 (36 Months) · Research Team and Scopes - Project Management: Korea Hydro and Nuclear Power Company (KHNP) - Development of Code and Standards for SC Structure: Korea Society of Steel Construction (KSSC) Korea Electric Power Research Institute (KEPRI) - Development of SC Structural Analysis and Design: Korea Power Engineering Company (KOPEC) - Development of Construction Techniques for SC Modularization: KHNP, Korea Institute of Nuclear Safety(KINS), KOPEC □ Performance

  7. 76 FR 1469 - Calvert Cliffs Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2...

    Science.gov (United States)

    2011-01-10

    ... COMMISSION Calvert Cliffs Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2... Cliffs Nuclear Power Plant, LLC, the licensee, for operation of the Calvert Cliffs Nuclear Power Plant... for light-water nuclear power reactors,'' which requires that the calculated emergency core...

  8. 77 FR 47121 - Calvert Cliffs Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Units 1 and 2...

    Science.gov (United States)

    2012-08-07

    ... COMMISSION Calvert Cliffs Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Units 1 and 2; Exemption 1.0 Background Calvert Cliffs Nuclear Power Plant, LLC (the licensee) is the holder of Renewed..., ``Fatigue Management for Nuclear Power Plant Personnel,'' endorses the Nuclear Energy Institute (NEI)...

  9. Industrial accidents in nuclear power plants

    International Nuclear Information System (INIS)

    In 12 nuclear power plants in the Federal Republic of Germany with a total of 3678 employees, 25 notifiable company personnel accidents and 46 notifiable outside personnel accidents were reported for an 18-month period. (orig./HP)

  10. Environmental hazards from nuclear power plants

    International Nuclear Information System (INIS)

    The article discusses the radiation exposure due to nuclear power stations in normal operation and after reactor incidents. Also mentioned is the radiation exposure to the emissions from fuel reprocessing plants and radioactive waste facilities. (RW/AK)

  11. Report concerning Zarnowiec nuclear power plant

    International Nuclear Information System (INIS)

    Report of the Team of the President of the National Atomic Energy Agency regarding Zarnowiec nuclear power plant contains the analysis of situation in Poland in June 1990, the assessment of public opinion, as well as the description of ecological, technical and economical problems. The team's conclusions are given together with the general conclusion to stop the construction of Zarnowiec nuclear power plant. 5 appendixes, 6 enclosures, 1 documents list, 1 tab. (A.S.)

  12. Quality assurance organization for nuclear power plants

    International Nuclear Information System (INIS)

    This Safety Guide provides requirements, recommendations and illustrative examples for structuring, staffing and documenting the organizations that perform activities affecting quality of a nuclear power plant. It also provides guidance on control of organization interfaces, and establishment of lines for direction, communication and co-ordination. The provisions of this Guide are applicable to all organizations participating in any of the constituent areas of activities affecting quality of a nuclear power plant, such as design, manufacture, construction, commissioning and operation

  13. Seismic instrumentation for nuclear power plants

    International Nuclear Information System (INIS)

    A seismic instrumentation system used in Nuclear Power Plants to monitor the design parameters of systems, structures and components, needed to provide safety to those plants, against the action of earth quarks is described. The instrumentation is based on the nuclear standards and other components used, as well as their general localization is indicated. The operation of the instrumentation system as a whole and the handling of the recovered data are dealt with accordingly. The accelerometer is described in detail. (Author)

  14. Does Brazil need new nuclear power plants?

    Energy Technology Data Exchange (ETDEWEB)

    Carvalho, Joaquim F. de [Graduate Program on Energy, University of Sao Paulo, SP (Brazil)], E-mail: jfdc35@uol.com.br; Sauer, Ildo L. [Graduate Program on Energy, University of Sao Paulo, SP (Brazil); Institute of Electrotechnics and Energy, University of Sao Paulo, SP (Brazil)], E-mail: illsauer@iee.usp.br

    2009-04-15

    In October 2008, the Brazilian Government announced plans to invest US$212 billion in the construction of nuclear power plants, totaling a joint capacity of 60,000 MW. Apart from this program, officials had already announced the completion of the construction of the nuclear plant Angra III; the construction of large-scale hydroelectric plans in the Amazon and the implantation of natural gas, biomass and coal thermoelectric plants in other regions throughout the country. Each of these projects has its proponents and its opponents, who bring forth concerns and create heated debates in the specialized forums. In this article, some of these concerns are explained, especially under the perspective of the comparative analysis of costs involved. Under such merit figures, the nuclear option, when compared to hydro plants, combined with conventional thermal and biomass-fueled plants, and even wind, to expand Brazilian power-generation capacity, does not appear as a priority.

  15. Does Brazil need new nuclear power plants?

    Energy Technology Data Exchange (ETDEWEB)

    De Carvalho, Joaquim F. [Graduate Program on Energy, University of Sao Paulo, SP (Brazil); Sauer, Ildo L. [Graduate Program on Energy, University of Sao Paulo, SP (Brazil)]|[Institute of Electrotechnics and Energy, University of Sao Paulo, SP (Brazil)

    2009-04-15

    In October 2008, the Brazilian Government announced plans to invest US$212 billion in the construction of nuclear power plants, totaling a joint capacity of 60,000 MW. Apart from this program, officials had already announced the completion of the construction of the nuclear plant Angra III; the construction of large-scale hydroelectric plans in the Amazon and the implantation of natural gas, biomass and coal thermoelectric plants in other regions throughout the country. Each of these projects has its proponents and its opponents, who bring forth concerns and create heated debates in the specialized forums. In this article, some of these concerns are explained, especially under the perspective of the comparative analysis of costs involved. Under such merit figures, the nuclear option, when compared to hydro plants, combined with conventional thermal and biomass-fueled plants, and even wind, to expand Brazilian power-generation capacity, does not appear as a priority. (author)

  16. Effort on Nuclear Power Plants safety

    International Nuclear Information System (INIS)

    Prospects of nuclear power plant on designing, building and operation covering natural safety, technical safety, and emergency safety are discussed. Several problems and their solutions and nuclear energy operation in developing countries especially control and permission are also discussed. (author tr.)

  17. Questions and Answers About Nuclear Power Plants.

    Science.gov (United States)

    Environmental Protection Agency, Washington, DC.

    This pamphlet is designed to answer many of the questions that have arisen about nuclear power plants and the environment. It is organized into a question and answer format, with the questions taken from those most often asked by the public. Topics include regulation of nuclear power sources, potential dangers to people's health, whether nuclear…

  18. Radiation protection in nuclear power plants

    International Nuclear Information System (INIS)

    The organization of workers' protection in a nuclear power plant is stated. Considering the nature and magnitude of potential risks and protection procedures, an inventory of occupational safety is made, taking account of accident statistics. It shows the credit to nuclear energy can be granted as to occupational safety

  19. Nuclear power plant safety in Brazil

    International Nuclear Information System (INIS)

    The Code of Practice for the Safe Operation of Nuclear Power Plants states that: 'In discharging its responsibility for public health and safety, the government should ensure that the operational safety of a nuclear reactor is subject to surveillance by a regulatory body independent of the operating organization'. In Brazil this task is being carried out by the Comissao Nacional de Energia Nuclear in accordance with the best international practice. (orig./RW)

  20. Psychological empowerment in French nuclear power plants

    OpenAIRE

    Fillol, Charlotte

    2011-01-01

    Since the eighties, nuclear safety has been discussed in organizational studies and constitutes nowadays a specific stream with several standpoints. Regarding the reliability of nuclear plants, the nuclear safety literature has emphasized on the crucial role of individuals and human factors. Especially, some researchers have noticed rule breaking behavior and the impact of individual self-confidence on thebehavior; but without deepening their analyses. As high self-esteem and confidence, i.e....

  1. Nuclear power plant construction activity, 1986

    International Nuclear Information System (INIS)

    Cost estimates, chronological data on construction progress, and the physical characteristics of nuclear units in commercial operation and units in the construction pipeline as of December 31, 1986, are presented. This report, which is updated annually, was prepared to provide an overview of the nuclear power plant construction industry. The report contains information on the status of nuclear generating units, average construction costs and lead-times, and construction milestones for individual reactors

  2. BAR-CODE BASED WEIGHT MEASUREMENT STATION FOR PHYSICAL INVENTORY TAKING OF PLUTONIUM OXIDE CONTAINERS AT THE MINING AND CHEMICAL COMBINE RADIOCHEMICAL REPROCESSING PLANT NEAR KRASNOYARSK, SIBERIA

    International Nuclear Information System (INIS)

    This paper describes the technical tasks being implemented to computerize the physical inventory taking (PIT) at the Mining and Chemical Combine (Gorno-Khimichesky Kombinat, GKhK) radiochemical plant under the US/Russian cooperative nuclear material protection, control, and accounting (MPC and A) program. Under the MPC and A program, Lab-to-Lab task agreements with GKhK were negotiated that involved computerized equipment for item verification and confirmatory measurement of the Pu containers. Tasks under Phase I cover the work for demonstrating the plan and procedures for carrying out the comparison of the Pu container identification on the container with the computerized inventory records. In addition to the records validation, the verification procedures include the application of bar codes and bar coded TIDs to the Pu containers. Phase II involves the verification of the Pu content. A plan and procedures are being written for carrying out confirmatory measurements on the Pu containers

  3. Nuclear power plant security assessment technical manual.

    Energy Technology Data Exchange (ETDEWEB)

    O' Connor, Sharon L.; Whitehead, Donnie Wayne; Potter, Claude S., III

    2007-09-01

    This report (Nuclear Power Plant Security Assessment Technical Manual) is a revision to NUREG/CR-1345 (Nuclear Power Plant Design Concepts for Sabotage Protection) that was published in January 1981. It provides conceptual and specific technical guidance for U.S. Nuclear Regulatory Commission nuclear power plant design certification and combined operating license applicants as they: (1) develop the layout of a facility (i.e., how buildings are arranged on the site property and how they are arranged internally) to enhance protection against sabotage and facilitate the use of physical security features; (2) design the physical protection system to be used at the facility; and (3) analyze the effectiveness of the PPS against the design basis threat. It should be used as a technical manual in conjunction with the 'Nuclear Power Plant Security Assessment Format and Content Guide'. The opportunity to optimize physical protection in the design of a nuclear power plant is obtained when an applicant utilizes both documents when performing a security assessment. This document provides a set of best practices that incorporates knowledge gained from more than 30 years of physical protection system design and evaluation activities at Sandia National Laboratories and insights derived from U.S. Nuclear Regulatory Commission technical staff into a manual that describes a development and analysis process of physical protection systems suitable for future nuclear power plants. In addition, selected security system technologies that may be used in a physical protection system are discussed. The scope of this document is limited to the identification of a set of best practices associated with the design and evaluation of physical security at future nuclear power plants in general. As such, it does not provide specific recommendations for the design and evaluation of physical security for any specific reactor design. These best practices should be applicable to the design and

  4. Drought prompts government to close nuclear plant

    CERN Multimedia

    2003-01-01

    "A nuclear power plant was shut down Sunday because a record drought left insufficient water to cool down the reactor. The plant supplies more than 10 percent of Romania's electricity and closure prompted fears of a price hike" (1/2 page).

  5. Operations quality assurance for nuclear power plants

    International Nuclear Information System (INIS)

    This standard covers the quality assurance of all activities concerned with the operation and maintenance of plant equipment and systems in CANDU-based nuclear power plants during the operations phase, the period between the completion of commissioning and the start of decommissioning

  6. 78 FR 38739 - Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants

    Science.gov (United States)

    2013-06-27

    ... COMMISSION Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants AGENCY: Nuclear... Accounting Systems for Nuclear Power Plants.'' This regulatory guide provides guidance on recordkeeping and... nuclear material control and accounting system requirements for nuclear power plants. This guide...

  7. 77 FR 28407 - Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants

    Science.gov (United States)

    2012-05-14

    ... COMMISSION Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants AGENCY: Nuclear...-5028, ``Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants.'' In DG-5028... Control and Accounting Systems for Nuclear Power Plants.'' DATES: Submit comments by July 16,...

  8. Natural Circulation Performance in Nuclear Power Plants

    International Nuclear Information System (INIS)

    The present paper deals with a study of natural circulation in PWR systems, The study consists of two parts: in the first one, natural circulation in experimental facilities simulating PWR plants was analyzed. This made it possible to gather a broad data base which was assumed as a reference for the subsequent part of the research. Seven Nuclear Power Plants nodalizations and additional experimental data from ''non-PWR'' facilities have been considered in the second part of the paper. Conclusions are drawn about natural circulation capabilities derived for the seven Nuclear Power Plants nodalizations and from data base pertinent to three ''non-PWR'' facilities. (author)

  9. Safety Assessment - Swedish Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Kjellstroem, B. [Luleaa Univ. of Technology (Sweden)

    1996-12-31

    After the reactor accident at Three Mile Island, the Swedish nuclear power plants were equipped with filtered venting of the containment. Several types of accidents can be identified where the filtered venting has no effect on the radioactive release. The probability for such accidents is hopefully very small. It is not possible however to estimate the probability accurately. Experiences gained in the last years, which have been documented in official reports from the Nuclear Power Inspectorate indicate that the probability for core melt accidents in Swedish reactors can be significantly larger than estimated earlier. A probability up to one in a thousand operating years can not be excluded. There are so far no indications that aging of the plants has contributed to an increased accident risk. Maintaining the safety level with aging nuclear power plants can however be expected to be increasingly difficult. It is concluded that the 12 Swedish plants remain a major threat for severe radioactive pollution of the Swedish environment despite measures taken since 1980 to improve their safety. Closing of the nuclear power plants is the only possibility to eliminate this threat. It is recommended that until this is done, quantitative safety goals, same for all Swedish plants, shall be defined and strictly enforced. It is also recommended that utilities distributing misleading information about nuclear power risks shall have their operating license withdrawn. 37 refs.

  10. Safety Assessment - Swedish Nuclear Power Plants

    International Nuclear Information System (INIS)

    After the reactor accident at Three Mile Island, the Swedish nuclear power plants were equipped with filtered venting of the containment. Several types of accidents can be identified where the filtered venting has no effect on the radioactive release. The probability for such accidents is hopefully very small. It is not possible however to estimate the probability accurately. Experiences gained in the last years, which have been documented in official reports from the Nuclear Power Inspectorate indicate that the probability for core melt accidents in Swedish reactors can be significantly larger than estimated earlier. A probability up to one in a thousand operating years can not be excluded. There are so far no indications that aging of the plants has contributed to an increased accident risk. Maintaining the safety level with aging nuclear power plants can however be expected to be increasingly difficult. It is concluded that the 12 Swedish plants remain a major threat for severe radioactive pollution of the Swedish environment despite measures taken since 1980 to improve their safety. Closing of the nuclear power plants is the only possibility to eliminate this threat. It is recommended that until this is done, quantitative safety goals, same for all Swedish plants, shall be defined and strictly enforced. It is also recommended that utilities distributing misleading information about nuclear power risks shall have their operating license withdrawn. 37 refs

  11. Construction and operation of nuclear power plants

    International Nuclear Information System (INIS)

    How does a nuclear power plant work. Which reactor types are in use. What safety measures are being taken. These questions and the like are frequently asked by those interested in nuclear power generation. The respective answers are to be found in the report ''Construction and Operation of Nuclear Power Plants''. Nuclear-physical fundamentals and the basic safety measures are explained, and four reactor types that are most common in the Federal Republic of Germany are described: PWR-, BWR-, HTR-type and faster breeder reactors. For each reactor type, the principle of operation, steam generator system, auxiliary and service buildings as well as the respective safety devices are indicated, and visualized by means of numerous illustrations. The report is meant to be instrumental to the purpose of getting objectiveness into the public discussion on the peaceful use of nuclear energy. (orig.)

  12. SWOT of nuclear power plant sustainable development

    International Nuclear Information System (INIS)

    SWOT Analysis is a Useful tool that can he applied to most projects or business ventures. In this article we are going to examine major strengths, weaknesses, opportunities and threats of nuclear power plants in view of sustainable development. Nuclear power plants have already attained widespread recognition for its benefits in fossil pollution abatement, near-zero green house gas emission, price stability and security of energy supply. The impressive new development is that these virtues are now a cost -free bonus, because, in long run, nuclear energy has become an inexpensive way to generate electricity. Nuclear energy's pre-eminence economically and environmentally has two implications for government policy. First, governments should ensure that nuclear licensing and safety oversight arc not only rigorous but also efficient in facilitating timely development of advanced power plants. Second, governments should be bold incentivizing the transformation to clean energy economics, recognizing that such short-term stimulus will, in the case of nuclear plants, simply accelerate desirable changes that now have their own long-term momentum. The increased competitiveness of nuclear power plant is the result of cost reductions in all aspects of nuclear economics: Construction, financing, operations, waste management and decommissioning. Among the cost-lowering factors are the evolution to standardized reactor designs, shorter construction periods, new financing techniques, more efficient generation technologies, higher rates of reactor utilization, and longer plant lifetimes. U.S World Nuclear Association report shows that total electricity costs for power plant construction and operation were calculated at two interest rates. At 10%, midrange generating costs per kilowatt-hour are nuclear at 4 cents, coal at 4.7 cents and natural gas at 5.1 cent. At a 5% interest rate, mid-range costs per KWh fall to nuclear at 2.6 cents, coal at 3.7 cents and natural gas at 4.3 cents

  13. Nuclear power plant transients: where are we

    International Nuclear Information System (INIS)

    This document is in part a postconference review and summary of the American Nuclear Society sponsored Anticipated and Abnormal Plant Transients in Light Water Reactors Conference held in Jackson, Wyoming, September 26-29, 1983, and in part a reflection upon the issues of plant transients and their impact on the viability of nuclear power. This document discusses state-of-the-art knowledge, deficiencies, and future directions in the plant transients area as seen through this conference. It describes briefly what was reported in this conference, emphasizes areas where it is felt there is confidence in the nuclear industry, and also discusses where the experts did not have a consensus. Areas covered in the document include major issues in operational transients, transient management, transient events experience base, the status of the analytical tools and their capabilities, probabilistic risk assessment applications in operational transients, and human factors impact on plant transients management

  14. Advanced nuclear power plants in Korea

    International Nuclear Information System (INIS)

    Full text: Korea Hydro and Nuclear Power Co., Ltd (KHNP) is the largest power company among the six subsidiaries that separated from Korea Electric Power Corporation (KEPCO) in 2001, accounting for approximately 25% of electricity producing facilities, hydro and nuclear combined. KHNP operates 20 nuclear power plants in Kori, Yonggwang, Ulchin and Wolsong site and several hydroelectric power generation facilities, providing approximately 36% of the national power supply. As a major source of electricity generation in Korea, nuclear energy contributes greatly to the stability of national electricity supply and energy security. KHNP's commercial nuclear power plant operation, which started with Kori Unit 1 in 1978, has achieved an average capacity factor more than 90% since 2000 and a high record of 93.4% in 2008. Following the introduction of nuclear power plants in the 1970's, Korea accumulated its nuclear technology in the 1980's, developed OPR 1000(Optimized Power Reactor) and demonstrated advanced level of its nuclear technology capabilities in the 2000's by developing an advanced type reactor, APR 1400(Advanced Power Reactor) which is being constructed at Shin-Kori Unit 3 and 4 for the first time. By 2022, KHNP will construct additional 12 nuclear power plants in order to ensure a stable power supply according to the Government Plan of Long-Term Electricity supply and Demand. 4 units of OPR 1000 reactor model will be commissioned by 2013 and 8 units of APR 1400 are under construction and planned. At the end of 2022, the nuclear capacity will reach 33% share of total generation capacity in Korea and account for 48% of national power generation. (author)

  15. 75 FR 66802 - Calvert Cliffs Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2...

    Science.gov (United States)

    2010-10-29

    ... COMMISSION Calvert Cliffs Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2... Regulatory Commission (the Commission) has granted the request of Calvert Cliffs Nuclear Power Plant, LLC... Operating License Nos. DPR-53 and DPR-69 for the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and...

  16. 76 FR 39908 - Calvert Cliffs Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2...

    Science.gov (United States)

    2011-07-07

    ... COMMISSION Calvert Cliffs Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2.... DPR-53 and DPR-69, for the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 (CCNPP), respectively... (ISFSI), currently held by Calvert Cliffs Nuclear Power Plant, LLC as owner and licensed...

  17. Risks of potential accidents of nuclear power plants in Europe

    OpenAIRE

    Slaper H; Eggink GJ; Blaauboer RO

    1993-01-01

    Over 200 nuclear power plants for commercial electricity production are presently operational in Europe. The 1986 accident with the nuclear power plant in Chernobyl has shown that severe accidents with a nuclear power plant can lead to a large scale contamination of Europe. This report is focussed on an integrated assessment of probabilistic cancer mortality risks due to possible accidental releases from the European nuclear power plants. For each of the European nuclear power plants the prob...

  18. Ground assessment methods for nuclear power plant

    International Nuclear Information System (INIS)

    It is needless to say that nuclear power plant must be constructed on the most stable and safe ground. Reliable assessment method is required for the purpose. The Ground Integrity Sub-committee of the Committee of Civil Engineering of Nuclear Power Plant started five working groups, the purpose of which is to systematize the assessment procedures including geological survey, ground examination and construction design. The works of working groups are to establishing assessment method of activities of faults, standardizing the rock classification method, standardizing assessment and indication method of ground properties, standardizing test methods and establishing the application standard for design and construction. Flow diagrams for the procedures of geological survey, for the investigation on fault activities and ground properties of area where nuclear reactor and important outdoor equipments are scheduled to construct, were established. And further, flow diagrams for applying investigated results to design and construction of plant, and for determining procedure of liquidification nature of ground etc. were also established. These systematized and standardized methods of investigation are expected to yield reliable data for assessment of construction site of nuclear power plant and lead to the safety of construction and operation in the future. In addition, the execution of these systematized and detailed preliminary investigation for determining the construction site of nuclear power plant will make much contribution for obtaining nation-wide understanding and faith for the project. (Ishimitsu, A.)

  19. The earthquake security of the Paks Nuclear Power Plant

    International Nuclear Information System (INIS)

    The seismic safety of Paks Nuclear Power Plant is analyzed. Assessment of earthquake risk has been done at the site of the plant, and seismic resistance of the nuclear power plant is analyzed together. (TRA)

  20. Thoughts on nuclear power plants

    International Nuclear Information System (INIS)

    In this article published before the Chernobyl accident (and the greenhouse effect issue), the author comments the evolution of the perception people have on nuclear energy: it was supposed to be the beginning of a golden age, and is finally perceived as a source of thermal and radioactive pollution and a major industrial risk. He outlines and criticizes the various and more or less violent reactions and debates about the fact that choosing nuclear energy means choosing a certain type of society. He considers that this point of view refuses reality. He states that the emerging new and renewable energies cannot be the solution. He comments the emergence of an energy crisis after the first oil crisis, and the associated questions about a possible reduction of consumption, the replacement of oil, the potential of renewable energies. He criticizes the excessive fear about nuclear materials and energy, discusses the actual risks associated with electronuclear production, and discusses the energy issue in the international context to outline the importance of nuclear energy. He finally addresses issues related to the definition and implementation of an energy policy, with EDF as a major actor

  1. Safety criteria for nuclear chemical plants

    International Nuclear Information System (INIS)

    Safety measures have always been required to limit the hazards due to accidental release of radioactive substances from nuclear power plants and chemical plants. The risk associated with the discharge of radioactive substances during normal operation has also to be kept acceptably low. BNFL (British Nuclear Fuels Ltd.) are developing risk criteria as targets for safe plant design and operation. The numerical values derived are compared with these criteria to see if plants are 'acceptably safe'. However, the criteria are not mandatory and may be exceeded if this can be justified. The risk assessments are subject to independent review and audit. The Nuclear Installations Inspectorate also has to pass the plants as safe. The assessment principles it uses are stated. The development of risk criteria for a multiplant site (nuclear chemical plants tend to be sited with many others which are related functionally) is discussed. This covers individual members of the general public, societal risks, risks to the workforce and external hazards. (U.K.)

  2. Nuclear power plant outage optimisation strategy

    International Nuclear Information System (INIS)

    Competitive environment for electricity generation has significant implications for nuclear power plant operations, including among others the need of efficient use of resources, effective management of plant activities such as on-line maintenance and outages. Nuclear power plant outage management is a key factor for good, safe and economic nuclear power plant performance which involves many aspects: plant policy, co-ordination of available resources, nuclear safety, regulatory and technical requirements and, all activities and work hazards, before and during the outage. This technical publication aims to communicate these practices in a way they can be used by operators and utilities in the Member States of the IAEA. It intends to give guidance to outage managers, operating staff and to the local industry on planning aspects, as well as examples and strategies experienced from current plants in operation on the optimization of outage period. This report discusses the plant outage strategy and how this strategy is actually implemented. The main areas identified as most important for outage optimization by the utilities and government organizations participating in this report are: organization and management; outage planning and preparation, outage execution, safety outage review, and counter measures to avoid extension of outages and to easier the work in forced outages. This report was based on discussions and findings by the authors of the annexes and the participants of an Advisory Group Meeting on Determinant Causes for Reducing Outage Duration held in June 1999 in Vienna. The report presents the consensus of these experts regarding best common or individual good practices that can be used at nuclear power plants with the aim to optimize

  3. Advanced nuclear plants meet the economic challenge

    International Nuclear Information System (INIS)

    Nuclear power plants operated in the baseload regime are economically competitive even when compared with plants burning fossil fuels. As they do not produce emissions when operated, they do not pollute the environment. This is clearly reflected also in the internalized costs. After 2000, many new power plants are expected to be constructed in the USA and worldwide. An important role in this phase will be played by advanced light water reactors of the ABWR and SBWR types representing the future state of the art in technology and safety as well as in cost and plant operations management. (orig.)

  4. Order and chaos in a galactic model with a strong nuclear bar

    Institute of Scientific and Technical Information of China (English)

    Euaggelos E. Zotos

    2012-01-01

    We use a composite gravitational galactic model consisting of a disk,a halo,a massive nucleus and a strong nuclear bar,in order to study the connections between global and local parameters in a realistic dynamical system.The local model is constructed from a two-dimensional perturbed harmonic oscillator and can be derived by expanding the global model in the vicinity of the central stable Lagrange equilibrium point.The frequencies of oscillations are not arbitrary,but they are connected with all the parameters involved with the global model.Moreover,the value of the local energy is also connected with the value of the global energy.Low and high energy stars in the global model display chaotic motion.Comparison with previous research reveals that the presence of the massive nucleus is responsible for the chaotic motion of the low energy stars.In the local motion,the low energy stars show interesting resonance phenomena,but the chaotic motion,if any,is negligible.On the contrary,the high energy stars do not show bounded motion in the local model.This is an indication of particular activity near the center of galaxies possessing massive nuclei.

  5. Ground acceleration in a nuclear power plant

    International Nuclear Information System (INIS)

    A methodology that adopts the recommendations of international organizations for determining the ground acceleration at a nuclear power plant is outlined. Systematic presented here emphasizes the type of geological, geophysical and geotechnical studies in different areas of influence, culminating in assessments of Design Basis earthquake and the earthquake Operating Base. The methodology indicates that in regional areas where the site of the nuclear power plant is located, failures are identified in geological structures, and seismic histories of the region are documented. In the area of detail geophysical tools to generate effects to determine subsurface propagation velocities and spectra of the induced seismic waves are used. The mechanical analysis of drill cores allows estimating the efforts that generate and earthquake postulate. Studies show that the magnitude of the Fukushima earthquake, did not affect the integrity of nuclear power plants due to the rocky settlement found. (Author)

  6. Wireless Technology Application to Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jeong Kweon; Jeong, See Chae; Jeong, Ki Hoon; Oh, Do Young; Kim, Jae Hack [KOPEC, Daejeon (Korea, Republic of)

    2009-10-15

    Wireless technologies are getting widely used in various industrial processes for equipment condition monitoring, process measurement and other applications. In case of Nuclear Power Plant (NPP), it is required to review applicability of the wireless technologies for maintaining plant reliability, preventing equipment failure, and reducing operation and maintenance costs. Remote sensors, mobile technology and two-way radio communication may satisfy these needs. The application of the state of the art wireless technologies in NPPs has been restricted because of the vulnerability for the Electromagnetic Interference and Radio Frequency Interference (EMI/RFI) and cyber security. It is expected that the wireless technologies can be applied to the nuclear industry after resolving these issues which most of the developers and vendors are aware of. This paper presents an overview and information on general wireless deployment in nuclear facilities for future application. It also introduces typical wireless plant monitoring system application in the existing NPPs.

  7. Nuclear plant cancellations: causes, costs, and consequences

    International Nuclear Information System (INIS)

    This study was commissioned in order to help quantify the effects of nuclear plant cancellations on the Nation's electricity prices. This report presents a historical overview of nuclear plant cancellations through 1982, the costs associated with those cancellations, and the reasons that the projects were terminated. A survey is presented of the precedents for regulatory treatment of the costs, the specific methods of cost recovery that were adopted, and the impacts of these decisions upon ratepayers, utility stockholders, and taxpayers. Finally, the report identifies a series of other nuclear plants that remain at risk of canellation in the future, principally as a result of similar demand, finance, or regulatory problems cited as causes of cancellation in the past. The costs associated with these potential cancellations are estimated, along with their regional distributions, and likely methods of cost recovery are suggested

  8. Nuclear plant cancellations: causes, costs, and consequences

    Energy Technology Data Exchange (ETDEWEB)

    1983-04-01

    This study was commissioned in order to help quantify the effects of nuclear plant cancellations on the Nation's electricity prices. This report presents a historical overview of nuclear plant cancellations through 1982, the costs associated with those cancellations, and the reasons that the projects were terminated. A survey is presented of the precedents for regulatory treatment of the costs, the specific methods of cost recovery that were adopted, and the impacts of these decisions upon ratepayers, utility stockholders, and taxpayers. Finally, the report identifies a series of other nuclear plants that remain at risk of canellation in the future, principally as a result of similar demand, finance, or regulatory problems cited as causes of cancellation in the past. The costs associated with these potential cancellations are estimated, along with their regional distributions, and likely methods of cost recovery are suggested.

  9. Construct ability Improvement for Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Dae Soo; Lee, Jong Rim; Kim, Jong Ku [Korea Electric Power Research Institute, Taejon (Korea, Republic of)

    1997-12-31

    The purpose of this study was to identify methods for improving the construct ability of nuclear power plants. This study reviewed several references of current construction practices of domestic and overseas nuclear plants in order to identify potential methods for improving construct ability. The identified methods for improving construct ability were then evaluated based on the applicability to domestic nuclear plant construction. The selected methods are expected to reduce the construction period, improve the quality of construction, cost, safety, and productivity. Selection of which methods should be implemented will require further evaluation of construction modifications, design changes, contract revisions. Among construction methods studied, platform construction methods can be applied through construction sequence modification without significant design changes, and Over the Top construction method of the NSSS, automatic welding of RCL pipes, CLP modularization, etc., are considered to be applied after design modification and adjustment of material lead time. (author). 49 refs., figs., tabs.

  10. Barsebaeck nuclear plant February-99

    International Nuclear Information System (INIS)

    Barsebaeck should, according to the government decision, have been closed before the 1st of July 1998, but the Supreme Administrative Court ruled on Stay of Execution, after Barsebaeck Kraft had applied for judicial review. The Threat of a Phase out of Barsebaeck 1 started in 1980, due to the accident at Three Mile Island. Swedish opinion Opinion polls (Nov 97, March 98 and May 98) shows that about 80 percent of the Swedish population want to use nuclear power until the existing reactors have to be stopped for safety or economical reasons. About 20 percent of these want to develop nuclear power. Average or high confidence in Barsebaeck has 94 percent on the Swedish side and 74 percent in Copenhagen 1998. From February 1997 till August 1998 Barsebaeck personnel have executed several information activities to stress our message that Barsebaeck is necessary for the environment, the jobs and the economy

  11. Investment issues in nuclear plant license renewal

    International Nuclear Information System (INIS)

    A method that determines the operating lives for existing nuclear power plants is discussed. These assumptions are the basis for projections of electricity supply through 2020 reported in the Energy Information Administration's (EIA's) Annual Energy Outlook 1999. To determine if plants will seek license renewal, one must first determine if they will be operating to the end of their current licenses. This determination is based on an economic test that assumes an investment of $150/kW will be required after 30 yr of operation for plants with older designs. This expenditure is intended to be equivalent to the cost that would be associated with any of several needs such as a one0time investment to replace aging equipment (steam generators), a series of investments to fix age-related degradation, increases in operating costs, or costs associated with decreased performance. This investment is compared with the cost of building and operating the lowest-cost new plant over the same 10-yr period. If a plant fails this test, it is assumed to be retired after 30 yr of service. All other plants are then considered candidates for license renewal. The method used to determine if it is economic to apply for license renewal and operate plants for an additional 20 yr is to assume that plants face an investment of $250 million after 40 yr of operation to refurbish aging components. This investment is compared with the lowest-cost new plant alternative evaluated over the same 20 yr that the nuclear plant would operate. If the nuclear plant is the lowest cost option, it is projected to continue to operate. EIA projects that it would be economic to extend the operating licenses for 3.7 GW of capacity (6 units)

  12. Special aspects of nuclear power plant construction

    International Nuclear Information System (INIS)

    The very strict safety and quality requirements as well as the necessity of strengthened schedule and investment control make good project management even more important to the construction of nuclear power plant than conventional projects. For developing countries, to increase the extent of local participation becomes an essential way to reduce the construction costs and improve the nuclear competitiveness. Modular construction approach and design for construct ability are discussed as viable means to further reduce construction time and costs

  13. Thermodynamics in nuclear power plant systems

    CERN Document Server

    Zohuri, Bahman

    2015-01-01

    This book covers the fundamentals of thermodynamics required to understand electrical power generation systems, honing in on the application of these principles to nuclear reactor powersystems. It includes all the necessary information regarding the fundamental laws to gain a complete understanding and apply them specifically to the challenges of operating nuclear plants. Beginning with definitions of thermodynamic variables such as temperature, pressure and specific volume, the book then explains the laws in detail, focusing on pivotal concepts such as enthalpy and entropy, irreversibilit

  14. Design concepts of nuclear desalination plants

    International Nuclear Information System (INIS)

    Interest in using nuclear energy for producing potable water has been growing worldwide in the past decade. This has been motivated by a variety of factors, including economic competitiveness of nuclear energy, the growing need for worldwide energy supply diversification, the need to conserve limited supplies of fossil fuels, protecting the environment from greenhouse gas emissions, and potentially advantageous spin-off effects of nuclear technology for industrial development. Various studies, and at least one demonstration project, have been considered by Member States with the aim of assessing the feasibility of using nuclear energy for desalination applications under specific conditions. In order to facilitate information exchange on the subject area, the IAEA has been active for a number of years in compiling related technical publications. In 1999, an inter regional technical co-operation project on Integrated Nuclear Power and desalination System Design was launched to facilitate international collaboration for the joint development by technology holders and potential end users of an integrated nuclear desalination system. This publication presents material on the current status of nuclear desalination activities and preliminary design concepts of nuclear desalination plants, as made available to the IAEA by various Member States. It is aimed at planners, designers and potential end-users in those Member States interested in further assessment of nuclear desalination. Interested readers are also referred to two related and recent IAEA publications, which contain useful information in this area: Introduction of Nuclear Desalination: A Guidebook, Technical Report Series No. 400 (2000) and Safety Aspects of Nuclear Plants Coupled with Seawater Desalination Units, IAEA-TECDOC-1235 (2001)

  15. The Advanced BWR Nuclear Plant: Safe, economic nuclear energy

    Energy Technology Data Exchange (ETDEWEB)

    Redding, J.R. [GE Nuclear Energy, San Jose, CA (United States)

    1994-12-31

    The safety and economics of Advanced BWR Nuclear Power Plants are outlined. The topics discussed include: ABWR Programs: status in US and Japan; ABWR competitiveness: safety and economics; SBWR status; combining ABWR and SBWR: the passive ABWR; and Korean/GE partnership.

  16. Commissioning of nuclear power plants

    International Nuclear Information System (INIS)

    The basic objective of commissioning programs is to demonstrate that systems will operate as designed. This involves testing under conditions which simulate normal, upset and accident conditions. Experience with commissioning of plants supports the current commissioning practices and suggests improvements that should be made

  17. Maintenance of nuclear power plants

    International Nuclear Information System (INIS)

    This Guide covers the organizational and procedural aspects of maintenance but does not give detailed technical advice on the maintenance of particular plant items. It gives guidance on preventive and remedial measures necessary to ensure that all structures, systems and components important to safety are capable of performing as intended. The Guide covers the organizational and administrative requirements for establishing and implementing preventive maintenance schedules, repairing defective plant items, providing maintenance facilities and equipment, procuring stores and spare parts, selecting and training maintenance personnel, reviewing and controlling plant modifications arising from maintenance, and for generating, collecting and retaining maintenance records. Maintenance shall be subject to quality assurance in all aspects important to safety. Because quality assurance has been dealt with in detail in other Safety Guides, it is only included here in specific instances where emphasis is required. Maintenance is considered to include functional and performance testing of plant, surveillance and in-service inspection, where these are necessary either to support other maintenance activities or to ensure continuing capability of structures, systems and components important to safety to perform their intended functions

  18. Plant life management and maintenance technologies for nuclear power plants

    International Nuclear Information System (INIS)

    Nuclear power generation occupying an important position for energy source in Japan and supplying about one third of total electric power usage is now required for further upgrading of its economics under regulation relaxation of electric power business. And, under execution retardation of its new planning plant, it becomes important to operate the already established plants for longer term and to secure their stability. Therefore, technical development in response to the plant life elongation is promoted under cooperation of the Ministry of Economics and Industries, electric power companies, literate, and plant manufacturers. Under such conditions, the Hitachi, Ltd. has progressed some technical developments on check inspection, repairs and maintenance for succession of the already established nuclear power plants for longer term under securing of their safety and reliability. And in future, by proposing the check inspection and maintenance program combined with these technologies, it is planned to exert promotion of maintenance program with minimum total cost from a viewpoint of its plant life. Here were described on technologies exerted in the Hitachi, Ltd. such as construction of plant maintenance program in response to plant life elongation agreeing with actual condition of each plant, yearly change mechanism grasping, life evaluation on instruments and materials necessary for maintenance, adequate check inspection, repairs and exchange, and so forth. (G.K.)

  19. Nuclear power plant siting: Hydrogeologic aspects

    International Nuclear Information System (INIS)

    This Safety Guide gives guidelines and methods for determining the ground water concentration of radionuclides that could result from postulated releases from nuclear power plants. The Guide gives recommendations on the data to be collected and the investigations to be performed at various stages of nuclear power plant siting in relation to the various aspects of the movement of accidentally released radioactive material through the ground water, the selection of an appropriate mathematical or physical model for the hydrodynamic dispersion even two-phase distribution of the radioactive material and an appropriate monitoring programme

  20. Virtual environments for nuclear power plant design

    International Nuclear Information System (INIS)

    In the design and operation of nuclear power plants, the visualization process inherent in virtual environments (VE) allows for abstract design concepts to be made concrete and simulated without using a physical mock-up. This helps reduce the time and effort required to design and understand the system, thus providing the design team with a less complicated arrangement. Also, the outcome of human interactions with the components and system can be minimized through various testing of scenarios in real-time without the threat of injury to the user or damage to the equipment. If implemented, this will lead to a minimal total design and construction effort for nuclear power plants (NPP)

  1. Integrated CAE system for nuclear power plant

    International Nuclear Information System (INIS)

    The design and engineering of nuclear power plant covers various technical fields. The information created in many fields is exchanged and utilized in many places at the same time. As CAE systems are applied to several plants, large and diverse information has been accumulated on the data base management system. Discrepancies in information and complicated data handling has come to light at routine work on large scale CAE systems. In view of the above, TOSHIBA has integrated CAE system to utilize information more efficiently. This paper describes that TOSHIBA has been improving user interface in an integrated environment and building intelligent applications specialized for nuclear engineering. (author)

  2. Seismic instrumentation for nuclear power plants

    International Nuclear Information System (INIS)

    A seismic instrumentation system used in Nuclear Power Plants to monitor the design parameters of systems, structures and components, needed to provide safety to those Plants, against the action of earthquakes is described. The instrumentation described is based on the nuclear standards in force. The minimum amount of sensors and other components used, as well as their general localization, is indicated. The operation of the instrumentation system as a whole and the handling of the recovered data are dealt with accordingly. The various devices used are not covered in detail, except for the accelerometer, which is the seismic instrumentation basic component. (Author)

  3. New technologies of information treatment in the ERP of the Almaraz and Trillo nuclear power plants

    International Nuclear Information System (INIS)

    The Almaraz and Trillo Nuclear Power Plants are equipped with an Integrated Operation Management System (SIGE), which covers practically all of their transactional and management needs in all areas, with the exception of some specific engineering and simulation tools. In recent years, applications based on new computer technologies have been developed and integrated into the SIGE, including a Maintenance Dashboard, an Admissions Office ant the use of bar code readers, all of which are described in this article. (Author)

  4. Economic justification of nuclear plant life extension

    International Nuclear Information System (INIS)

    The electric utility industry generally uses the revenue requirements method to compare alternative investment and financing decisions. Westinghouse has developed a present-worth generating cost model to assess the potential economic values of PLEX projects undertaken for nuclear power plants. This model evaluates all significant benefits and costs based on actual data provided by the utility and measured in discounted revenue requirement differentials between PLEX and a reference plan (nuclear plant replacement with a nuclear- or coal-fired plant of the same capacity). The ratio of the benefits of a PLEX program to its costs are calculated. The paper shows that a program that extends the life of the plant by 20 yr has a break-even cost of approximately $1100 per kW(electric) if the outage time to make the replacements (time in excess of normal planned outages) is 24 months. The allowed expense decreases rapidly if the PLEX program requires longer outage times, but is substantial at even 36 or 48 months. The results benefit-to-cost ratio for PLEX is at least 4.0. The ratio would be much higher if additional benefits from availability, efficiency improvements, and reduction in O and M costs were included. The results of the PLEX economic evaluations performed by Westinghouse clearly indicate that nuclear plant life extension is the most economical alternative to building new generating capacities

  5. Costs of Decommissioning Nuclear Power Plants

    International Nuclear Information System (INIS)

    While refurbishments for the long-term operation of nuclear power plants and for the lifetime extension of such plants have been widely pursued in recent years, the number of plants to be decommissioned is nonetheless expected to increase in future, particularly in the United States and Europe. It is thus important to understand the costs of decommissioning so as to develop coherent and cost-effective strategies, realistic cost estimates based on decommissioning plans from the outset of operations and mechanisms to ensure that future decommissioning expenses can be adequately covered. This study presents the results of an NEA review of the costs of decommissioning nuclear power plants and of overall funding practices adopted across NEA member countries. The study is based on the results of this NEA questionnaire, on actual decommissioning costs or estimates, and on plans for the establishment and management of decommissioning funds. Case studies are included to provide insight into decommissioning practices in a number of countries. (authors)

  6. Managing the first nuclear power plant project

    International Nuclear Information System (INIS)

    Energy is essential for national development. Nearly every aspect of development - from reducing poverty and raising living standards to improving health care, industrial and agricultural productivity - requires reliable access to modern energy resources. States may have different reasons for considering starting a nuclear power project to achieve their national energy needs, such as: lack of available indigenous energy resources, the desire to reduce dependence upon imported energy, the need to increase the diversity of energy resources and/or mitigation of carbon emission increases. The start of a nuclear power plant project involves several complex and interrelated activities with long duration. Experience shows that the time between the initial policy decision by a State to consider nuclear power up to the start of operation of its first nuclear power plant is about 10 to 15 years and that before specific project management can proceed, several key infrastructure issues have to be in place. The proper management of the wide scope of activities to be planned and implemented during this period represents a major challenge for the involved governmental, utility, regulatory, supplier and other supportive organizations. The main focus is to ensure that the project is implemented successfully from a commercial point of view while remaining in accordance with the appropriate engineering and quality requirements, safety standards and security guides. This publication is aimed at providing guidance on the practical management of a first nuclear power project in a country. There are many other issues, related to ensuring that the infrastructure in the country has been prepared adequately to ensure that the project will be able to be completed, that are only briefly addressed in this publication. The construction of the first nuclear power plant is a major undertaking for any country developing a nuclear power programme. Worldwide experience gained in the last 50 years

  7. Safer design for a nuclear power plant

    International Nuclear Information System (INIS)

    During the regulatory process for the issuing of the construction permit and the operating licence of the first Austrian nuclear power plant, more than 1200 injunctions have been issued for increasing its safety standard. In principle they belong to three groups: quality assurance and quality control; the improvement of the design; and probabilistic issues. Examples of all these three groups are given. When discussions with the parties in the regulatory process on the issuing of the operating licence were going on, work at the nuclear power plant was suddenly terminated following the negative outcome of a referendum. The main content of the discussions was that the nuclear inspectors keep permanent control over the plant and have a permanent record of occurrences there, that participation of the regulatory body is included in all issues which might influence the safety standard of the plant, and that the regulatory body may issue new injunctions on the operation of the plant if new standards arise from backfitting ensuing from lessons learned, from the treatment of generic issues, from new rules and regulations and from reactor safety research. Special attention is given to the process of mothballing the plant as was necessary after the referendum. The work on the plant was terminated in an orderly way; a final report was issued which stated what still would have to be done at the plant in order to go into operation. The mothballing began by demounting some systems, emptying others and shutting down a third group. Some ventilation systems are in operation. These activities are also recorded in reports; these, together with a final report of the status reached, could be the basis for revitalization work. Finally it is shown how Austria, with its limited means in terms of funds and personnel, is dealing with the problems of keeping the safety standard of the plant as high as at the plants in other countries with more funds and personnel available. (author)

  8. 76 FR 66089 - Access Authorization Program for Nuclear Power Plants

    Science.gov (United States)

    2011-10-25

    ... COMMISSION Access Authorization Program for Nuclear Power Plants AGENCY: Nuclear Regulatory Commission... revision to Regulatory Guide 5.66, ``Access Authorization Program for Nuclear Power Plants.'' This guide... Authorization Requirements for Nuclear Power Plants,'' and 10 CFR part 26, ``Fitness for Duty Programs.'' The...

  9. 78 FR 55118 - Seismic Instrumentation for Nuclear Power Plants

    Science.gov (United States)

    2013-09-09

    ... COMMISSION Seismic Instrumentation for Nuclear Power Plants AGENCY: Nuclear Regulatory Commission. ACTION..., ``Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition... Safety Analysis Reports for Nuclear Power Plants: LWR Edition'' (SRP, from the current Revision 2 to...

  10. Training of nuclear power plant operating personnel

    International Nuclear Information System (INIS)

    Proceedings are presented containing 13 papers on the training of nuclear power plant personnel, especially personnel of WWER type plants. The questions are discussed such as care of personnel, the position of operators and maintenance workers, factors affecting their reliable work, the human factor in reliability and safety of big power facilities, the assurance of a standard system of operators' training with associated social and sociological aspects, the development of psychodiagnostic methodologies for testing and selecting workers for individual jobs. (B.S.)

  11. Holdup measurement for nuclear fuel manufacturing plants

    Energy Technology Data Exchange (ETDEWEB)

    Zucker, M.S.; Degen, M.; Cohen, I.; Gody, A.; Summers, R.; Bisset, P.; Shaub, E.; Holody, D.

    1981-07-13

    The assay of nuclear material holdup in fuel manufacturing plants is a laborious but often necessary part of completing the material balance. A range of instruments, standards, and a methodology for assaying holdup has been developed. The objectives of holdup measurement are ascertaining the amount, distribution, and how firmly fixed the SNM is. The purposes are reconciliation of material unbalance during or after a manufacturing campaign or plant decommissioning, to decide security requirements, or whether further recovery efforts are justified.

  12. Th-100 Nuclear Power Plant

    International Nuclear Information System (INIS)

    Steenkampskraal Thorium Limited (STL) is a private company which is designing, marketing, licensing and commercializing a 100MWt thorium fueled pebble bed reactor. The concept plant design has been completed and work on the basic design has started. First site to determine the fuel cycle employed. Strong emphasis is placed on modular construction to reduce costs. STL hopes to start the licensing process within the next 6-8 months

  13. Quark fragmentation to $\\pi^{\\pm}$, $\\pi^{0}$, $K^{\\pm}$, $p$ and $\\bar{p}$ in the nuclear environment

    CERN Document Server

    Airapetian, A; Akopov, Z; Amarian, M; Ammosov, V V; Andrus, A; Aschenauer, E C; Augustyniak, W; Avakian, R; Avetisian, A; Avetissian, E; Bailey, P; Baturin, V; Baumgarten, C; Beckmann, M; Belostotskii, S; Bernreuther, S; Bianchi, N; Blok, H P; Böttcher, Helmut B; Borisov, A; Borysenko, A; Bouwhuis, M; Brack, J; Brüll, A; Bryzgalov, V V; Capitani, G P; Chiang, H C; Ciullo, G; Contalbrigo, M; Dalpiaz, P F; De Leo, R; De Nardo, L; De Sanctis, E; Devitsin, E G; Di Nezza, P; Düren, M; Ehrenfried, M; Elalaoui-Moulay, A; Elbakian, G M; Ellinghaus, F; Elschenbroich, U; Ely, J; Fabbri, R; Fantoni, A; Feshchenko, A; Felawka, L; Fox, B; Franz, J; Frullani, S; Gapienko, G; Gapienko, V; Garibaldi, F; Garrow, K; Garutti, E; Gaskell, D; Gavrilov, G E; Karibian, V; Graw, G; Grebenyuk, O; Greeniaus, L G; Gregor, I M; Hafidi, K; Hartig, M; Hasch, D; Heesbeen, D; Henoch, M; Hertenberger, R; Hesselink, W H A; Hillenbrand, A; Hoek, M; Holler, Y; Hommez, B; Iarygin, G; Ivanilov, A; Izotov, A; Jackson, H E; Jgoun, A; Kaiser, R; Kinney, E; Kiselev, A; Königsmann, K C; Kopytin, M; Korotkov, V; Kozlov, V; Krauss, B; Krivokhizhin, V G; Lagamba, L; Lapikas, L; Laziev, A; Lenisa, P; Liebing, P; Lindemann, T; Lipka, K; Lorenzon, W; Lü, J; Maiheu, B; Makins, N C R; Marianski, B; Marukyan, H O; Masoli, F; Mexner, V; Meyners, N; Miklukho, O; Miller, C A; Miyachi, Y; Muccifora, V; Nagaitsev, A; Nappi, E; Naryshkin, Yu; Nass, A; Negodaev, M A; Nowak, Wolf-Dieter; Oganessyan, K; Ohsuga, H; Pickert, N; Potashov, S Yu; Potterveld, D H; Raithel, M; Reggiani, D; Reimer, P E; Reischl, A; Reolon, A R; Riedl, C; Rith, K; Rosner, G; Rostomyan, A; Rubacek, L; Ryckbosch, D; Salomatin, Yu I; Sanjiev, I; Savin, I; Scarlett, C; Schäfer, A; Schill, C; Schnell, G; Schüler, K P; Schwind, A; Seele, J; Seidl, R; Seitz, B; Shanidze, R G; Shearer, C; Shibata, T A; Shutov, V B; Simani, M C; Sinram, K; Stancari, M D; Statera, M; Steffens, E; Steijger, J J M; Stenzel, H; Stewart, J; Stösslein, U; Tait, P; Tanaka, H; Taroian, S P; Tchuiko, B; Terkulov, A R; Tkabladze, A V; Trzcinski, A; Tytgat, M; Vandenbroucke, A; Van der Nat, P B; van der Steenhoven, G; Vetterli, Martin C; Vikhrov, V; Vincter, M G; Vogel, C; Vogt, M; Volmer, J; Weiskopf, C; Wendland, J; Wilbert, J; Ybeles-Smit, G V; Yen, S; Zihlmann, B; Zohrabyan, H G; Zupranski, P

    2003-01-01

    The influence of the nuclear medium on lepto-production of hadrons was studied in the HERMES experiment at DESY in semi-inclusive deep-inelastic scattering of 27.6 GeV positrons off deuterium, nitrogen and krypton targets. The differential multiplicity for krypton relative to that of deuterium has been measured for the first time for various identified hadrons ($\\pi^+$, $\\pi^-$, $\\pi^0$, $K^+$, $K^-$, $p$ and $\\bar{p}$) as a function of the virtual photon energy $\

  14. Communicating about advanced nuclear energy plants

    International Nuclear Information System (INIS)

    The success of advanced nuclear energy plants, as with any new product, will not depend on design alone. Success will require public support and good communications to achieve that support. In the past, communication weaknesses - including mixed and confusing messages - have sometimes created barriers between the technical community and the public. Several lessons learned from a decade of social science research in the United States of America have implications for communicating effectively about advanced design nuclear energy plants: (1) Most audiences are open-minded and receptive to communications on this topic. They view nuclear energy as a fuel of the future and want to be comfortable about the future. Most people in the USA (82%) expect future nuclear energy plants to be safer, so the improvements being made are simply consistent with public expectations. (2) Few people pay close attention to energy issues. (3) Communications must be simple and free of jargon. Because people do not pay close attention to the issues, their knowledge is limited. Some terms used by the industry to describe advanced design plants are misinterpreted. (4) Good communications focus on consumer wants and values, not industry needs or problems. People care about generational responsibility, planning for the future, environmental protection and security. (5) Benefits and safeguards should be shown instead of risk comparisons. Generic benefits of nuclear energy, such as clean air, are important to consumers. (6) Pictures and hand-on demonstrations help in communicating about nuclear energy plants, because many of the discussion concepts are abstract. (7) Trust is crucial and is established now for tomorrow through word and deed. (author)

  15. Nuclear Trafficking During Plant Innate Immunity

    Institute of Scientific and Technical Information of China (English)

    Jun Liu; Gitta Coaker

    2008-01-01

    Land plants possess innate immune systems that can control resistance against pathogen infection. Conceptually, there are two branches of the plant innate immune system. One branch recognizes conserved features of microbial pathogens, while a second branch specifically detects the presence of pathogen effector proteins by plant resistance (R) genes. Innate immunity controlled by plant R genes is called effector-triggered immunity. Although R genes can recognize all classes of plant pathogens, the majority can be grouped into one large family, encoding proteins with a nucleotide binding site and C-terminal leucine rich repeat domains. Despite the importance and number of R genes present in plants, we are just beginning to decipher the signaling events required to initiate defense responses. Recent exciting discoveries have implicated dynamic nuclear trafficking of plant R proteins to achieve effector-triggered immunity. Furthermore, there are several additional lines of evidence implicating nucleo-cyctoplasmic trafficking in plant disease resistance, as mutations in nucleoporins and importins can compromise resistance signaling. Taken together, these data illustrate the importance of nuclear trafficking in the manifestation of disease resistance mediated by R genes.

  16. New nuclear power plants for Ontario

    International Nuclear Information System (INIS)

    Towards the end of this year the Ontario government will select the technology for its future nuclear power plants. To clarify the differences between the contending reactors I have put together the following quick overview. Ontario's requirement is for a stand-alone two-unit nuclear power plant to provide around 2,000 to 3,500 MWe of baseload generating capacity at a site to he specified with an option for one or two additional units. It is likely that the first units will be located at either the Darlington site near Bowmanville or the Bruce site near Kincardine. However the output from the Bruce site is presently transmission constrained. All nuclear-electric generation in Ontario comes from Atomic Energy of Canada Limited's (AECL) CANDU reactors at Pickering, Darlington and Bruce. The contenders are, AECL's 1085 MWe (net) ACR-1000 (Advanced CANDU Reactor), Westinghouse Electric Company's 1117 MWe (net) AP1000 (Advanced Passive), AREVA NP's 1600 MWe (net) U.S. EPR (United States Evolutionary Pressurized Reactor) and the 1550 MWe (net) GE Hitachi Nuclear Energy's ESBWR (Economic and Simplified Boiling Water Reactor). Westinghouse has Toshiba as a majority shareholder, AREVA has the government of France as a majority shareholder and GE-Hitachi has GE as the major shareholder. AECL is a federal crown corporation and is part of Team CANDU consisting of Babcock and Wilcox Canada, GE-Hitachi Nuclear Energy Canada Inc., Hitachi Canada Limited and SNC-Lavalin Nuclear Inc. Generally the engineering split in Team CANDU would be, AECL, Mississauga, Ontario, responsible for the design of the nuclear steam plant including reactor and safety systems; Babcock and Wilcox Canada, Cambridge, Ontario, responsible for supply of the steam generators and other pressure retaining components; GE-Hitachi Nuclear Energy Canada Inc., Peterborough, Ontario for the fuel handling equipment; Hitachi Canada Limited, Mississauga, for the balance of plant steam to electricity conversion

  17. The challenge of financing nuclear power plants

    International Nuclear Information System (INIS)

    To date, more then 500 nuclear power reactors have been successfully financed and built. Experience in recent nuclear projects confirms that nuclear power will not cease to be a viable option due to a worldwide financing constraint. For financing nuclear plants there are special considerations: large investment; long lead and construction times; complex technology; regulatory risk and political risk. The principal preconditions to financing are a national policy supporting nuclear power; creditworthiness; economic competitiveness; project feasibility; assurance of adequate revenues; acceptability of risks; and no open-ended liabilities. Generally, nuclear power plants are financed conventionally through multi-sources, where a package covers the entire cost. The first source, the investor/owner/operator responsible for building and operating the plant, should cover a sizable portion of the overall investment. In addition, bond issues, domestic bank credits etc. and, in case of State-owned or controlled enterprises, donations and credits from public entities or the governmental budget, should complete the financing. A financially sound utility should be able to meet this challenge. For importing technology, bids are invited. Export credits should form the basis of foreign financing, because these have favorable terms and conditions. Suppliers from several countries may join in a consortium subdividing the scope of supply and involve several Export Credit Agencies (ECAs). There are also innovative financing approaches that could be applied to nuclear projects. Evolutionary Reactors with smaller overall investment, shorter construction times, reliance on proven technology, together with predictable regulatory regimes and reliable long-term national policies favorable to nuclear power, should make it easier to meet the future challenges of financing. (author)

  18. A PIP chart for nuclear plant safety

    International Nuclear Information System (INIS)

    While it is known that social and political aspects of nuclear safety issues are important, little study has been done on identifying the breadth of stakeholders whose policies have important influences over nuclear plant safety in a comprehensive way. The objectives of this study are to develop a chart that visually identifies important stakeholders and their policies and illustrates these influences in a hierarchical representation so that the relationship between stakeholders and nuclear safety will be better understood. This study is based on a series of extensive interviews with major stakeholders, such as nuclear plant managers, corporate planning vice presidents, state regulators, news media, and public interest groups, and focuses on one US nuclear power plant. Based on the interview results, the authors developed a conceptual policy influence paths (PIP) chart. The PIP chart illustrates the hierarchy of influence among stakeholders. The PIP chart is also useful in identifying possible stakeholders who can be easily overlooked without the PIP chart. In addition, it shows that influence flow is circular rather than linear in one direction

  19. Regional economic impacts of nuclear power plants

    International Nuclear Information System (INIS)

    This study of economic and social impacts of nuclear power facilities compares a nuclear energy center (NEC) consisting of three surrogate sites in Ocean County, New Jersey with nuclear facilities dispersed in the Pennsylvania - New Jersey - Maryland area. The NEC studied in this report is assumed to contain 20 reactors of 1200 MW(e) each, for a total NEC capacity of 24,000 MW(e). Following the Introductory chapter, Chapter II discusses briefly the methodological basis for estimating impacts. This part of the analysis only considers impacts of wages and salaries and not purchase of construction materials within the region. Chapters III and IV, respectively, set forth the scenarios of an NEC at each of three sites in Ocean County, N.J. and of a pattern of dispersed nuclear power plants of total equivalent generating capacity. In each case, the economic impacts (employment and income) are calculated, emphasizing the regional effects. In Chapter V these impacts are compared and some more general conclusions are reported. A more detailed analysis of the consequences of the construction of a nuclear power plant is given in Chapter VI. An interindustry (input-output) study, which uses rather finely disaggregated data to estimate the impacts of a prototype plant that might be constructed either as a component of the dispersed scenario or as part of an NEC, is given. Some concluding remarks are given in Chapter VII, and policy questions are emphasized

  20. Fire protection in nuclear power plants

    International Nuclear Information System (INIS)

    The Safety Guide gives design and some operational guidance for protection from fire and fire-related explosions in nuclear power plants (NPP). It confines itself to fire protection of items important to safety, leaving the aspects of fire protection not related to safety in NPP to be decided upon the basis of the national practices and regulations

  1. Programmed system for nuclear power plant protection

    International Nuclear Information System (INIS)

    The progress in the field of microprocessors and large scale integration circuits, have incited to introduce this new technologies into nuclear power plant protection system. The hardware and software design principles are briefly listed; then, a quad-redundant protection system for 1300 MWe PWR, developed in France is described

  2. NUCLEAR POWER PLANT WASTE HEAT HORTICULTURE

    Science.gov (United States)

    The report gives results of a study of the feasibility of using low grade (70 degrees F) waste heat from the condenser cooling water of the Vermont Yaknee nuclear plant for commercial food enhancement. The study addressed the possible impact of laws on the use of waste heat from ...

  3. Geodesy problems in nuclear power plant construction

    International Nuclear Information System (INIS)

    The special geodetic problems encountered during the construction of the Paks nuclear power plants are treated. The main building with its hermetically connected components including the reactor, the steam generators, the circulation pumps etc. impose special requirements on the control net of datum points. The geodesy tasks solved during the construction of the main building are presented in details. (R.P.)

  4. Safety analysis of nuclear power plants

    International Nuclear Information System (INIS)

    A study about the safety analysis of nuclear power plant, giving emphasis to how and why to do is presented. The utilization of the safety analysis aiming to perform the licensing requirements is discussed, and an example of the Angra 2 and 3 safety analysis is shown. Some presented tendency of the safety analysis are presented and examples are shown.(E.G.)

  5. Alpha-nuclides in nuclear power plants

    International Nuclear Information System (INIS)

    The behaviour of alpha-nuclides in nuclear power plants is subject of the investigations presented. The source of alpha-nuclides is a contamination with fissile material (so called tramp uranium or tramp fuel) which deposits on fuel rod surfaces and leads to the build-up of transuranium nuclides. The determination of a defect situation with fuel release as well as the quantification of the fissile material contamination background is given for BWR and PWR plants. The quantification of the fuel release and the tramp uranium background can be calculated with different, measurable nuclides in BWR and PWR plants. (orig.)

  6. Evaluating nuclear power plant crew performance during emergency response drills

    International Nuclear Information System (INIS)

    The Atomic Energy Control Board (AECB) is responsible for the regulation of the health, safety and environmental consequences of nuclear activities in Canada. Recently, the Human Factors Specialists of the AECB have become involved in the assessment of emergency preparedness and emergency response at nuclear facilities. One key contribution to existing AECB methodology is the introduction of Behaviourally Anchored Rating Scales (BARS) to measure crew interaction skills during emergency response drills. This report presents results of an on-going pilot study to determine if the BARS provide a reliable and valid means of rating the key dimensions of communications, openness, task coordination and adaptability under simulated emergency circumstances. To date, the objectivity of the BARS is supported by good inter-rater reliability while the validity of the BARS is supported by the agreement between ratings of crew interaction and qualitative and quantitative observations of crew performance. (author)

  7. Constitutional determinants of nuclear power plant upgrading

    International Nuclear Information System (INIS)

    Around half a year ago the European stress test for nuclear power plants, a precautionary measure initiated by the European Council in March 2011 in response to the Fukushima disaster, revealed that while German nuclear power plants show a high degree of robustness compared with those in other European countries, they nevertheless required upgrading in one or the other respect (earthquake warning systems, protection against crashing civil passenger airplanes). The present article investigates whether this upgrading requirement can justify an injunction to carry out structural retrofitting measures or whether obligations to this end can be excluded on grounds of reasonability in view of the recent decision taken by the German parliament to phase out nuclear energy.

  8. Artificial intelligence in nuclear power plants

    International Nuclear Information System (INIS)

    The IAEA Specialists' Meeting on Artificial Intelligence in Nuclear Power Plants was arranged in Helsink/Vantaa, Finland, on October 10-12, 1989, under auspices of the International Working Group of Nuclear Power Plant Control and Instrumentation of the International Atomic Energy Agency (IAEA/IWG NPPCI). Technical Research Centre of Finland together with Imatran Voima Oy and Teollisuuden Voima Oy answered for the practical arrangements of the meeting. 105 participants from 17 countries and 2 international organizations took part in the meeting and 58 papers were submitted for presentation. These papers gave a comprehensive picture of the recent status and further trends in applying the rapidly developing techniques of artificial intelligence and expert systems to improve the quality and safety in designing and using of nuclear power worldwide

  9. Recent Advances in Ocean Nuclear Power Plants

    Directory of Open Access Journals (Sweden)

    Kang-Heon Lee

    2015-10-01

    Full Text Available In this paper, recent advances in Ocean Nuclear Power Plants (ONPPs are reviewed, including their general arrangement, design parameters, and safety features. The development of ONPP concepts have continued due to initiatives taking place in France, Russia, South Korea, and the United States. Russia’s first floating nuclear power stations utilizing the PWR technology (KLT-40S and the spar-type offshore floating nuclear power plant designed by a research group in United States are considered herein. The APR1400 and SMART mounted Gravity Based Structure (GBS-type ONPPs proposed by a research group in South Korea are also considered. In addition, a submerged-type ONPP designed by DCNS of France is taken into account. Last, issues and challenges related to ONPPs are discussed and summarized.

  10. Intelligent distributed control for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Klevans, E.H.; Edwards, R.M.; Ray, A.; Lee, K.Y.; Garcia, H.E.: Chavez, C.M.; Turso, J.A.; BenAbdennour, A.

    1991-01-01

    In September of 1989 work began on the DOE University Program grant DE-FG07-89ER12889. The grant provides support for a three year project to develop and demonstrate Intelligent Distributed Control (IDC) for Nuclear Power Plants. The body of this Second Annual Technical Progress report covers the period from September 1990 to September 1991. It summarizes the second year accomplishments while the appendices provide detailed information presented at conference meetings. These are two primary goals of this research. The first is to combine diagnostics and control to achieve a highly automated power plant as described by M.A. Schultz, a project consultant during the first year of the project. This philosophy, as presented in the first annual technical progress report, is to improve public perception of the safety of nuclear power plants by incorporating a high degree automation where greatly simplified operator control console minimizes the possibility of human error in power plant operations. A hierarchically distributed control system with automated responses to plant upset conditions is the focus of our research to achieve this goal. The second goal is to apply this research to develop a prototype demonstration on an actual power plant system, the EBR-II steam plant.

  11. Safety culture in nuclear power plants. Proceedings

    International Nuclear Information System (INIS)

    As a consequence of the INSAG-4 report on 'safety culture', published by the IAEA in 1991, the Federal Commission for the Safety of Nuclear Power Plants (KSA) decided to hold a one-day seminar as a first step in this field. The KSA is an advisory body of the Federal Government and the Federal Department of Transport and Energy (EVED). It comments on applications for licenses, observes the operation of nuclear power plants, assists with the preparation of regulations, monitors the progress of research in the field of nuclear safety, and makes proposals for research tasks. The objective of this seminar was to familiarise the participants with the principles of 'safety culture', with the experiences made in Switzerland and abroad with existing concepts, as well as to eliminate existing prejudices. The main points dealt with at this seminar were: - safety culture from the point of view of operators, - safety culture from the point of view of the authorities, - safety culture: collaboration between power plants, the authorities and research organisations, - trends and developments in the field of safety culture. Invitations to attend this seminar were extended to the management boards of companies operating Swiss nuclear power plants, and to representatives of the Swiss authorities responsible for the safety of nuclear power plants. All these organisations were represented by a large number of executive and specialist staff. We would like to express our sincerest thanks to the Head of the Federal Department of Transport and Energy for his kind patronage of this seminar. (author) figs., tabs., refs

  12. Design of a nuclear steam reforming plant

    International Nuclear Information System (INIS)

    The design of a plant for the steam reforming of methane using a High Temperature Reactor has been studied by CEA in connection with the G.E.G.N. This group of companies (CEA, GAZ DE FRANCE, CHARBONNAGES DE FRANCE, CREUSOT-LOIRE, NOVATOME) is in charge of studying the feasibility of the coal gasification process by using a nuclear reactor. The process is based on the hydrogenation of the coal in liquid phase with hydrogen produced by a methane steam reformer. The reformer plant is fed by a pipe of natural gas or SNG. The produced hydrogen feeds the gasification plant which could not be located on the same site. An intermediate hydrogen storage between the two plants could make the coupling more flexible. The gasification plant does not need a great deal of heat and this heat can be satisfied mostly by internal heat exchanges

  13. Training of nuclear power plant operating personnel

    International Nuclear Information System (INIS)

    A collection is presented containing 11 papers submitted at a conference on the selection and education of specialists for operation and maintenance of nuclear power plants. The conference was attended by specialists from universities and colleges, research institutes and production plants. It debated the methods and aims of both general and specialized theoretical and practical personnel education, the proposals for teaching centre equipment, the use of simulators, computers and other aids in the teaching process; training on school reactors was included. A proposal was put forward of the system of education, the teaching process itself, the content of the basic theoretical subjects, and the method of testing pupils' knowledge. The importance was stressed of establishing a national coordination centre to safeguard the syllabus, methodology, teaching aids, and also the training proper. The system of personnel education in the Paks nuclear power plant, Hungary, is presented as an example. (M.S.)

  14. Nuclear power plants in the world - 2010 edition

    International Nuclear Information System (INIS)

    This small booklet summarizes in tables all data relative to the nuclear power plants worldwide. These data come from the IAEA's PRIS and AREVA-CEA's GAIA databases. The following aspects are reviewed: 2009 highlights, Main characteristics of reactor types, Map of the French nuclear power plants on 2010/01/01, Worldwide status of nuclear power plants (12/31/2009), Units distributed by countries, Nuclear power plants connected to the Grid- by reactor type groups, Nuclear power plants under construction on 2009, Evolution of nuclear power plants capacities connected to the grid, First electric generations supplied by a nuclear unit in each country, Electrical generation from nuclear power plants by country at the end 2009, Performance indicator of french PWR units, Evolution of the generation indicators worldwide by type, Nuclear operator ranking according to their installed capacity, Units connected to the grid by countries at 12/31/2009, Status of licence renewal applications in USA, Nuclear power plants under construction at 12/31/2009, Shutdown reactors, Exported nuclear capacity in net MWe, Exported and national nuclear capacity connected to the grid, Exported nuclear power plants under construction, Exported and national nuclear capacity under construction, Nuclear power plants ordered at 12/31/2009, Long term shutdown units at 12/31/2009, COL applications in the USA, Recycling of Plutonium in reactors and experiences, Mox licence plants projects, Appendix - historical development, Meaning of the used acronyms, Glossary

  15. Elecnuc - Nuclear power plants in the world - 2009 edition

    International Nuclear Information System (INIS)

    This small booklet summarizes in tables all data relative to the nuclear power plants worldwide. These data come from the IAEA's PRIS and AREVA-CEA's GAIA databases. The following aspects are reviewed: 2008 highlights, Main characteristics of reactor types, Map of the French nuclear power plants on 2008/01/01, Worldwide status of nuclear power plants (12/31/2008), Units distributed by countries, Nuclear power plants connected to the Grid- by reactor type groups, Nuclear power plants under construction on 2008, Evolution of nuclear power plants capacities connected to the grid, First electric generations supplied by a nuclear unit in each country, Electrical generation from nuclear powe plants by country at the end 2008, Performance indicator of french PWR units, Evolution of the generation indicators worldwide by type, Nuclear operator ranking according to their installed capacity, Units connected to the grid by countries at 12/31/2008, Status of licence renewal applications in USA, Nuclear power plants under construction at 12/31/2008, Shutdown reactors, Exported nuclear capacity in net MWe, Exported and national nuclear capacity connected to the grid, Exported nuclear power plants under construction, Exported and national nuclear capacity under construction, Nuclear power plants ordered at 12/31/2008, Long term shutdown units at 12/31/2008, COL applications in the USA, Recycling of Plutonium in reactors and experiences, Mox licence plants projects, Appendix - historical development, Meaning of the used acronyms, Glossary

  16. ELECNUC Nuclear power plants in the world - 2013 edition

    International Nuclear Information System (INIS)

    This small booklet summarizes in a series of tables the figures relative to the nuclear power plants worldwide. Data come from the IAEA's PRIS database and from specific I-tese studies. The following aspects are reviewed: 2012 highlights; Main characteristics of reactor types; Map of the French nuclear power plants on 2012/01/01; Worldwide status of nuclear power plants (12/31/2012); Units distributed by countries; Nuclear power plants connected to the Grid- by reactor type groups; Nuclear power plants under construction on 2012; Evolution of nuclear power plants capacities connected to the grid; First electric generations supplied by a nuclear unit in each country; Electrical generation from nuclear power plants by country at the end 2012; Performance indicator of french PWR units; Evolution of the generation indicators worldwide by type; Nuclear operator ranking according to their installed capacity; Units connected to the grid by countries at 12/31/2012; Status of licence renewal applications in USA; Nuclear power plants under construction at 12/31/2012; Shutdown reactors; Exported nuclear capacity in net MWe; Exported and national nuclear capacity connected to the grid; Exported nuclear power plants under construction; Exported and national nuclear capacity under construction; Nuclear power plants ordered at 12/31/2012; Long term shutdown units at 12/31/2012; COL (Combined Licence) applications in the USA; Recycling of Plutonium in reactors and experiences; Mox licence plants projects; Appendix - historical development; Meaning of the used acronyms; Glossary

  17. Using modular neural networks to monitor accident conditions in nuclear power plants

    International Nuclear Information System (INIS)

    Nuclear power plants are very complex systems. The diagnoses of transients or accident conditions is very difficult because a large amount of information, which is often noisy, or intermittent, or even incomplete, need to be processed in real time. To demonstrate their potential application to nuclear power plants, neural networks axe used to monitor the accident scenarios simulated by the training simulator of TVA's Watts Bar Nuclear Power Plant. A self-organization network is used to compress original data to reduce the total number of training patterns. Different accident scenarios are closely related to different key parameters which distinguish one accident scenario from another. Therefore, the accident scenarios can be monitored by a set of small size neural networks, called modular networks, each one of which monitors only one assigned accident scenario, to obtain fast training and recall. Sensitivity analysis is applied to select proper input variables for modular networks

  18. Operational monitoring in German nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Seibold, A. [Technischer Ueberwachungs-Verein Suedwest e.V., Filderstadt (Germany); Bartonicek, J. [GKN Neckarwestheim, Im Steinbruch, Neckarwestheim, D-74382 (Germany); Kockelmann, H. [Staatliche Materialpruefungsanstalt (MPA), University of Stuttgart, Stuttgart (Germany)

    1995-10-01

    The Atomic Energy Act requires that measures made feasible by state of the art technology be adopted to avoid damage that could be caused as the result of the construction and operation of a nuclear plant. This stipulation constitutes the basis for deriving requirements for planning, design, construction, operation and decommissioning. Ensuring the function and integrity of those components and systems that are relevant to plant safety is of major significance with regard to operation of a nuclear power plant. The basis for ensuring these features is laid in planning, design and construction. Important as these foundations may be, it is absolutely essential to monitor the quality originally planned and achieved in an object as undeniably complex as a nuclear power plant. The RSK-Leitlinien fuer Druckwasserreaktoren (Reactor Safety Commission Guidelines for Pressurized Water Reactors) incorporate fundamental requirements for design, mechanical design, materials, manufacturing, testing and examination, and operation. Meeting these requirements makes it possible to exclude a catastrophic rupture of the components in the reactor cooling system pressure boundary (primary system), as has been demonstrated in detailed research and development work. The term basic safety was defined for this concept. Basic safety coupled with multiple redundancy suffices to exclude the possibility of large ruptures (rupture preclusion). The principle of plant monitoring and documentation (operational monitoring) implements redundancy in a significant manner within this concept. The monitoring techniques used in Germany have reached an advanced state of development and are still being optimized. Thus, operational monitoring is a major contributory factor in the safety and high availability of nuclear power plants. It also provides a means of expanding our knowledge of life time expectation. (orig.).

  19. Management of delayed nuclear power plant projects

    International Nuclear Information System (INIS)

    According to the available information at the IAEA PRIS (Power Reactor Information System) at the end of 1998 there were more than 40 nuclear power plant projects with delays of five or more years with respect to the originally scheduled commercial operation. The degree of conformance with original construction schedules showed large variations due to several issues, including financial, economic and public opinion factors. Taking into account the number of projects with several years delay in their original schedules, it was considered useful to identify the subject areas where exchange of experience among Member States would be mutually beneficial in identification of problems and development of guidance for successful management of the completion of these delayed projects. A joint programme of the IAEA Departments of Nuclear Energy (Nuclear Power Engineering Section) and Technical Co-operation (Europe Section, with additional support from the Latin America and West Asia Sections) was set up during the period 1997-1998. The specific aim of the programme was to provide assistance in the management of delayed nuclear power plants regarding measures to maintain readiness for resuming the project implementation schedule when the conditions permit. The integration of IAEA interdepartmental resources enabled the participation of 53 experts from 14 Member States resulting in a wider exchange of experience and dissemination of guidance. Under the framework of the joint programme, senior managers directly responsible for delayed nuclear power plant projects identified several issues or problem areas that needed to be addressed and guidance on management be provided. A work plan for the development of several working documents, addressing the different issues, was established. Subsequently these documents were merged into a single one to produce the present publication. This publication provides information and practical examples on necessary management actions to preserve

  20. BAR expressolog identification: expression profile similarity ranking of homologous genes in plant species.

    Science.gov (United States)

    Patel, Rohan V; Nahal, Hardeep K; Breit, Robert; Provart, Nicholas J

    2012-09-01

    Large numbers of sequences are now readily available for many plant species, allowing easy identification of homologous genes. However, orthologous gene identification across multiple species is made difficult by evolutionary events such as whole-genome or segmental duplications. Several developmental atlases of gene expression have been produced in the past couple of years, and it may be possible to use these transcript abundance data to refine ortholog predictions. In this study, clusters of homologous genes between seven plant species - Arabidopsis, soybean, Medicago truncatula, poplar, barley, maize and rice - were identified. Following this, a pipeline to rank homologs within gene clusters by both sequence and expression profile similarity was devised by determining equivalent tissues between species, with the best expression profile match being termed the 'expressolog'. Five electronic fluorescent pictograph (eFP) browsers were produced as part of this effort, to aid in visualization of gene expression data and to complement existing eFP browsers at the Bio-Array Resource (BAR). Within the eFP browser framework, these expression profile similarity rankings were incorporated into an Expressolog Tree Viewer to allow cross-species homolog browsing by both sequence and expression pattern similarity. Global analyses showed that orthologs with the highest sequence similarity do not necessarily exhibit the highest expression pattern similarity. Other orthologs may show different expression patterns, indicating that such genes may require re-annotation or more specific annotation. Ultimately, it is envisaged that this pipeline will aid in improvement of the functional annotation of genes and translational plant research.

  1. Safety goals for nuclear power plant operation

    International Nuclear Information System (INIS)

    This report presents and discusses the Nuclear Regulatory Commission's, Policy Statement on Safety Goals for the Operation of Nuclear Power Plants. The safety goals have been formulated in terms of qualitative goals and quantitative design objectives. The qualitative goals state that the risk to any individual member of the public from nuclear power plant operation should not be a significant contributor to that individual's risk of accidental death or injury and that the societal risks should be comparable to or less than those of viable competing technologies. The quantitative design objectives state that the average risks to individual and the societal risks of nuclear power plant operation should not exceed 0.1% of certain other risks to which members of the US population are exposed. A subsidiary quantitative design objective is established for the frequency of large-scale core melt. The significance of the goals and objectives, their bases and rationale, and the plan to evaluate the goals are provided. In addition, public comments on the 1982 proposed policy statement and responses to a series of questions that accompanied the 1982 statement are summarized

  2. Psychological empowerment in French nuclear power plants

    International Nuclear Information System (INIS)

    Since the eighties, nuclear safety has been discussed in organizational studies and constitutes nowadays a specific stream with several standpoints. Regarding the reliability of nuclear plants, the nuclear safety literature has emphasized on the crucial role of individuals and human factors. Especially, some researchers have noticed rule breaking behavior and the impact of individual self-confidence on the behavior; but without deepening their analyses. As high self-esteem and confidence, i.e. psychological empowerment, naturally lead to innovation and rule breaking, the behavior can be analyzed, in such a regulated industry, as opposite to safety. Thus, this article aims at explaining the roots and discernable features of the observed psychological empowerment. Methods include an in-depth qualitative study in 4 nuclear power plants owned by Electricite de France (EDF), the French national nuclear power operator. Focused on the leading team of the plant, the set of data is composed of 35 interviews, 6 weeks of non-participant observation and internal documents. The content analysis has revealed two main pillars of psychological empowerment. On the first hand, the strong professional identity developed at the opening of the plants is based on initiative and risk-taking. In some ways, this professional identify fostered by commitment to a demanding job and the team, influences behavior more than do professional rules. On the second hand, the management discourse is perceived as ambiguous towards the strict application of the rules and tacitly legitimizes rule breaking behavior. This article details and exemplifies these phenomena and discusses the implications. (author)

  3. Economic performance indicators for nuclear power plants

    International Nuclear Information System (INIS)

    From a global perspective, it is clear that there is no single group of key economic and financial measures that are applicable and useful for all countries and regions. The extent to which deregulation and privatization is occurring varies considerably throughout the world, with some countries continuing to foster regulated monopolies or government subsidies for power generation, while in others retail and wholesale electricity is sold in truly open market, competitive situations. Consequently, the requirement for key measures of financial and economic success for the nuclear power industry will continue to be diverse from one region or country to another. This report has been prepared for the benefit of nuclear plant managers and operators. Its primary purpose is to identify and define a number of economic performance measures for use at nuclear power plants operating in deregulated, competitive electricity markets. In addressing the value of economic measures, the report presents and discusses a general definition and classifications of nuclear economic indicators within the context of regulation, competition and the economic requirements for constructing, operating and decommissioning nuclear plants. Categories of economic measures, traditionally used in competitive enterprises, that have potential application in the operation of nuclear plants are also presented. A number of industry observations are discussed and presented as critical factors leading to a series of improvement strategies for the continued development and implementation of economic indicators, beyond those provided in this report, as well as for other related IAEA activities on the implementation and further development of the Nuclear Economic Performance Information System. On the basis of the collective opinions and judgements of the representatives of the participating countries, the report provides a 'preliminary' set of nuclear economic performance indicators, presented in standard Excel

  4. U.S. Nuclear Power Reactor Plant Status

    Data.gov (United States)

    Nuclear Regulatory Commission — Demographic data on U.S. commercial nuclear power reactors, including: plant name/unit number, docket number, location, licensee, reactor/containment type, nuclear...

  5. 75 FR 16869 - Entergy Nuclear Operations, LLC; Palisades Nuclear Plant; Exemption

    Science.gov (United States)

    2010-04-02

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Entergy Nuclear Operations, LLC; Palisades Nuclear Plant; Exemption 1.0 Background Entergy Nuclear... operation of Palisades Nuclear Plant (PNP). The license provides, among other things, that the facility...

  6. Reviewing computer capabilities in nuclear power plants

    International Nuclear Information System (INIS)

    The OSART programme of the IAEA has become an effective vehicle for promoting international co-operation for the enhancement of plant operational safety. In order to maintain consistency in the OSART reviews, OSART Guidelines have been developed which are intended to ensure that the reviewing process is comprehensive. Computer technology is an area in which rapid development is taking place and new applications may be computerized to further enhance safety and the effectiveness of the plant. Supplementary guidance and reference material is needed to help attain comprehensiveness and consistency in OSART reviews. This document is devoted to the utilization of on-site and off-site computers in such a way that the safe operation of the plant is supported. In addition to the main text, there are several annexes illustrating adequate practices as found at various operating nuclear power plants. Refs, figs and tabs

  7. Configuration management in nuclear power plants

    CERN Document Server

    2003-01-01

    Configuration management (CM) is the process of identifying and documenting the characteristics of a facility's structures, systems and components of a facility, and of ensuring that changes to these characteristics are properly developed, assessed, approved, issued, implemented, verified, recorded and incorporated into the facility documentation. The need for a CM system is a result of the long term operation of any nuclear power plant. The main challenges are caused particularly by ageing plant technology, plant modifications, the application of new safety and operational requirements, and in general by human factors arising from migration of plant personnel and possible human failures. The IAEA Incident Reporting System (IRS) shows that on average 25% of recorded events could be caused by configuration errors or deficiencies. CM processes correctly applied ensure that the construction, operation, maintenance and testing of a physical facility are in accordance with design requirements as expressed in the d...

  8. Cooling water requirements and nuclear power plants

    International Nuclear Information System (INIS)

    Indian nuclear power programme is poised to scuttle the energy crisis of our time by proposing joint ventures for large power plants. Large fossil/nuclear power plants (NPPs) rely upon water for cooling and are therefore located near coastal areas. The amount of water a power station uses and consumes depends on the cooling technology used. Depending on the cooling technology utilized, per megawatt existing NPPs use and consume more water (by a factor of 1.25) than power stations using other fuel sources. In this context the distinction between 'use' and 'consume' of water is important. All power stations do consume some of the water they use; this is generally lost as evaporation. Cooling systems are basically of two types; Closed cycle and Once-through, of the two systems, the closed cycle uses about 2-3% of the water volumes used by the once-through system. Generally, water used for power plant cooling is chemically altered for purposes of extending the useful life of equipment and to ensure efficient operation. The used chemicals effluent will be added to the cooling water discharge. Thus water quality impacts on power plants vary significantly, from one electricity generating technology to another. In light of massive expansion of nuclear power programme there is a need to develop new ecofriendly cooling water technologies. Seawater cooling towers (SCT) could be a viable option for power plants. SCTs can be utilized with the proper selection of materials, coatings and can achieve long service life. Among the concerns raised about the development of a nuclear power industry, the amount of water consumed by nuclear power plants compared with other power stations is of relevance in light of the warming surface seawater temperatures. A 1000 MW power plant uses per day ∼800 ML/MW in once through cooling system; while SCT use 27 ML/MW. With the advent of new marine materials and concrete compositions SCT can be constructed for efficient operation. However, the

  9. Desalination demonstration plant using nuclear heat

    International Nuclear Information System (INIS)

    Most of the desalination plants which are operating throughout the world utilize the energy from thermal power station which has the main disadvantage of polluting the environment due to combustion of fossil fuel and with the inevitable rise in prices of fossil fuel, nuclear driven desalination plants will become more economical. So it is proposed to set up nuclear desalination demonstration plant at the location of Madras Atomic Power Station (MAPS), Kalpakkam. The desalination plant will be of a capacity 6300 m3/day and based on both Multi Stage Flash (MSF) and Sea Water Reverse Osmosis (SWRO) processes. The MSF plant with performance ratio of 9 will produce water total dissolved solids (TDS-25 ppm) at a rate of 4500 m3/day from seawater of 35000 ppm. A part of this water namely 1000 m3/day will be used as Demineralised (DM) water after passing it through a mixed bed polishing unit. The remaining 3500 m3/day water will be mixed with 1800 m3/day water produced from the SWRO plant of TDS of 400 ppm and the same be supplied to industrial/municipal use. The sea water required for MSF and SWRO plants will be drawn from the intake/outfall system of MAPS which will also supply the required electric power pumping. There will be net 4 MW loss of power of MAPS namely 3 MW for MSF and 1 MW for SWRO desalination plants. The salient features of the project as well as the technical details of the both MSF and SWRO processes and its present status are given in this paper. It also contains comparative cost parameters of water produced by both processes. (author)

  10. Safety aspects of nuclear power plant ageing

    International Nuclear Information System (INIS)

    The nuclear community is facing new challenges as commercial nuclear power plants (NPPs) of the first generation get older. At present, some of the plants are approaching or have even exceeded the end of their nominal design life. Experience with fossil fired power plants and in other industries shows that reliability of NPP components, and consequently general plant safety and reliability, may decline in the middle and later years of plant life. Thus, the task of maintaining operational safety and reliability during the entire plant life and especially, in its later years, is of growing importance. Recognizing the potential impact of ageing on plant safety, the IAEA convened a Working Group in 1985 to draft a report to stimulate relevant activities in the Member States. This report provided the basis for the preparation of the present document, which included a review in 1986 by a Technical Committee and the incorporation of relevant results presented at the 1987 IAEA Symposium on the Safety Aspects of the Ageing and Maintenance of NPPs and in available literature. The purpose of the present document is to increase awareness and understanding of the potential impact of ageing on plant safety; of ageing processes; and of the approach and actions needed to manage the ageing of NPP components effectively. Despite the continuing growth in knowledge on the subject during the preparation of this report it nevertheless contains much that will be of interest to a wide technical and managerial audience. Furthermore, more specific technical publications on the evaluation and management of NPP ageing and service life are being developed under the Agency's programme, which is based on the recommendations of its 1988 Advisory Group on NPP ageing. Refs, figs and tabs

  11. 75 FR 16520 - James A. Fitzpatrick Nuclear Power Plant; Exemption

    Science.gov (United States)

    2010-04-01

    ... COMMISSION James A. Fitzpatrick Nuclear Power Plant; Exemption 1.0 Background Entergy Nuclear Operations, Inc... the James A. FitzPatrick Nuclear Power Plant (JAFNPP). The license provides, among other things, that... physical protection of licensed activities in nuclear power reactors against radiological...

  12. Risks of potential accidents of nuclear power plants in Europe

    NARCIS (Netherlands)

    Slaper H; Eggink GJ; Blaauboer RO

    1993-01-01

    Over 200 nuclear power plants for commercial electricity production are presently operational in Europe. The 1986 accident with the nuclear power plant in Chernobyl has shown that severe accidents with a nuclear power plant can lead to a large scale contamination of Europe. This report is focussed

  13. Risks of potential accidents of nuclear power plants in Europe

    NARCIS (Netherlands)

    Slaper H; Eggink GJ; Blaauboer RO

    1993-01-01

    Over 200 nuclear power plants for commercial electricity production are presently operational in Europe. The 1986 accident with the nuclear power plant in Chernobyl has shown that severe accidents with a nuclear power plant can lead to a large scale contamination of Europe. This report is focussed o

  14. Safety in nuclear power plants in India

    Directory of Open Access Journals (Sweden)

    Deolalikar R

    2008-01-01

    Full Text Available Safety in nuclear power plants (NPPs in India is a very important topic and it is necessary to dissipate correct information to all the readers and the public at large. In this article, I have briefly described how the safety in our NPPs is maintained. Safety is accorded overriding priority in all the activities. NPPs in India are not only safe but are also well regulated, have proper radiological protection of workers and the public, regular surveillance, dosimetry, approved standard operating and maintenance procedures, a well-defined waste management methodology, proper well documented and periodically rehearsed emergency preparedness and disaster management plans. The NPPs have occupational health policies covering periodic medical examinations, dosimetry and bioassay and are backed-up by fully equipped Personnel Decontamination Centers manned by doctors qualified in Occupational and Industrial Health. All the operating plants are ISO 14001 and IS 18001 certified plants. The Nuclear Power Corporation of India Limited today has 17 operating plants and five plants under construction, and our scientists and engineers are fully geared to take up many more in order to meet the national requirements.

  15. Taxonomy of the nuclear plant operator's role

    International Nuclear Information System (INIS)

    A program is presently under way at the Oak Ridge National Laboratory (ORNL) to define the functional design requirements of operational aids for nuclear power plant operators. A first and important step in defining these requirements is to develop an understanding of the operator's role or function. This paper describes a taxonomy of operator functions that applies during all operational modes and conditions of the plant. Other topics such as the influence of automation, role acceptance, and the operator's role during emergencies are also discussed. This systematic approach has revealed several areas which have potential for improving the operator's ability to perform his role

  16. Simulators for training nuclear power plant personnel

    International Nuclear Information System (INIS)

    Simulator training and retraining of operations personnel is essential for their acquiring the necessary knowledge, skills and qualification for operating a nuclear power plant, and for effective feedback of experience including human based operating errors. Simulator training is the most effective way by far of training operations personnel in co-operation and communication in a team, which also involves instilling attitudes and approaches for achieving excellence and individual responsibility and alertness. This technical document provides guidance to Member States on the procurement, setting up and utilization of a simulator training centre; it will also be useful for organizations with previous experience in the use of simulators for training. The document is the result of a series of advisory and consultants meetings held in the framework of the International Working Group on Nuclear Power Plant Control and Instrumentation in 1989-1992. 17 refs, 2 tabs

  17. The Dukovany nuclear power plant in 1992

    International Nuclear Information System (INIS)

    In 1992, the Dukovany nuclear power plant generated 12,250,230 MWh and supplied 11,475,241 MWh of electricity to the grid, which was 100.8% with respect to the plan of supplies. The profit was 177.5 million CZK (Czechoslovak crowns). The power plant had 2475 people on staff. Major repairs were made on all the 4 units. Inspectors of the State Surveillance over Nuclear Safety recorded 115 failures, 4 of which were evaluated as level 1 on the INES scale, the other were level 0. Data on gaseous and liquid effluents are given in tables. No health physics limit was surpassed in 1992. (M.D.). 10 figs., 3 tabs

  18. Global nuclear plant network and its characteristics

    International Nuclear Information System (INIS)

    Based on the realistic data, the priority queue network model was proposed and a global nuclear plant network (GNPN) was constructed by means of the theories of network science. The topological properties of the network such as the degree distribution and the clustering coefficients were numerically simulated, and the community structure of the network was discussed by a software named CFinder. The results reveal that the distribution of GNPN is of hyperdispersion and nonequilibrium distribution. From the structure of the network, we can also deduce the fact that the common reactor types are widely used in developed countries(node degree is large). However, developing countries (node degree is small)purchase them from the developed countries. All characteristics of GNPN can reflect the status and evolution of nuclear plants in different countries and they may be valuable for the concerned research in China. (authors)

  19. Operating experience with nuclear power plants 2015. Pt. 1

    International Nuclear Information System (INIS)

    The VGB Technical Committee ''Nuclear Plant Operation'' has been exchanging operating experience about nuclear power plants for more than 30 years. Plant operators from several European countries are participating in the exchange. A report is given on the operating results achieved in 2015, events important to plant safety, special and relevant repair, and retrofit measures from Germany. The second part of this report will focus on nuclear power plant in Belgium, Finland, the Netherlands, Switzerland, and Spain.

  20. Operating experience with nuclear power plants 2015. Pt. 1

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    2016-07-01

    The VGB Technical Committee ''Nuclear Plant Operation'' has been exchanging operating experience about nuclear power plants for more than 30 years. Plant operators from several European countries are participating in the exchange. A report is given on the operating results achieved in 2015, events important to plant safety, special and relevant repair, and retrofit measures from Germany. The second part of this report will focus on nuclear power plant in Belgium, Finland, the Netherlands, Switzerland, and Spain.

  1. Nuclear Plant Aging Research (NPAR) program plan

    International Nuclear Information System (INIS)

    A comprehensive Nuclear Plant Aging Research (NPAR) Program was implemented by the US NRC office of Nuclear Regulatory Research in 1985 to identify and resolve technical safety issues related to the aging of systems, structures, and components in operating nuclear power plants. This is Revision 2 to the Nuclear Plant Aging Research Program Plant. This planes defines the goals of the program the current status of research, and summarizes utilization of the research results in the regulatory process. The plan also describes major milestones and schedules for coordinating research within the agency and with organizations and institutions outside the agency, both domestic and foreign. Currently the NPAR Program comprises seven major areas: (1) hardware-oriented engineering research involving components and structures; (2) system-oriented aging interaction studies; (3) development of technical bases for license renewal rulemaking; (4) determining risk significance of aging phenomena; (5) development of technical bases for resolving generic safety issues; (6) recommendations for field inspection and maintenance addressing aging concerns; (7) and residual lifetime evaluations of major LWR components and structures. The NPAR technical database comprises approximately 100 NUREG/CR reports by June 1991, plus numerous published papers and proceedings that offer regulators and industry important insights to aging characteristics and aging management of safety-related equipment. Regulatory applications include revisions to and development of regulatory guides and technical specifications; support to resolve generic safety issues; development of codes and standards; evaluation of diagnostic techniques; (e.g., for cables and valves); and technical support for development of the license renewal rule. 80 refs., 25 figs., 10 tabs

  2. New nuclear plant design and licensing process

    International Nuclear Information System (INIS)

    This paper describes latest developments in the nuclear power reactor technology with emphasis on three areas: (1) the US technology of advanced passive light water reactors (AP600 and S BWR), (2) regulatory processes that certify their safety, and (3) current engineering concerns. The goal is to provide and insight of how the government's regulatory agency guarantees public safety by looking into how new passive safety features were designed and tested by vendors and how they were re-evaluated and retested by the US NRC. The paper then discusses the US 1989 nuclear licensing reform (10 CFR Part 52) whose objectives are to promote the standardization of nuclear power plants and provide for the early and definitive resolution of site and design issues before plants are built. The new licensing process avoids the unpredictability nd escalated construction cost under the old licensing process. Finally, the paper summarizes engineering concerns found in current light water reactors that may not go away in the new design. The concerns are related the material and water chemistry technology in dealing with corrosion problems in water-cooled nuclear reactor systems (PWRs and BWRs). These engineering concerns include core shroud cracking (BWRs), jet pump hold-down beam cracking (BWRs), steam generator tube stress corrosion cracking (PWR)

  3. Environmental monitoring around nuclear power plant sites

    International Nuclear Information System (INIS)

    The environmental monitoring around nuclear power plant sites is presented. The basic policy that no part of the ecosystem should be subjected to excessive (above natural) radiation exposure is realized by predictive methodology of environmental and dosimetric models. The validation of these models is achieved through environmental monitoring around nuclear power plant sites right from the pre-operational period through operational phase. The 'potential contaminated media' are monitored in pre-operational phase. The measurements carried out in the environmental matrices for assessment of the impact on the population demonstrate that the objectives of the Department of Atomic Energy are fully realized. These activities are carried out at each nuclear power plant site by establishing an Environmental Survey Laboratory, which operates under the administrative and technical control of the Health Physics Division of BARC. This arrangement ensures independence from the operating organisation and better public acceptance of data generated. The results of environmental monitoring indicate that the radiation dose received by members of the public is well below the regulatory limits. (author)

  4. Improved economics of nuclear plant life management

    International Nuclear Information System (INIS)

    The adoption of new on-line monitoring, diagnostic and eventually prognostics technologies has the potential to impact the economics of the existing nuclear power plant fleet, new plants and future advanced designs. To move from periodic inspection to on-line monitoring for condition-based maintenance and eventually prognostics will require advances in sensors, better understanding of what and how to measure within the plant; enhanced data interrogation, communication and integration; new predictive models for damage/aging evolution; system integration for real-world deployments; quantification of uncertainties in what are inherently ill-posed problems and the integration of enhanced condition-based maintenance/prognostics philosophies into new plant designs, operation and O and M approaches. The move to digital systems in petrochemical process and fossil fuel power plants is enabling major advances to occur in the instrumentation, controls and monitoring systems and approaches employed. The adoption within the nuclear power community of advanced on-line monitoring and advanced diagnostics has the potential for the reduction in costly periodic surveillance that requires plant shut-down, more accurate cost-benefit analysis, 'just-in-time' maintenance, pre-staging of maintenance tasks, movement towards true 'operation without failures' and a jump start on advanced technologies for new plant concepts, such as those proposed under the International Gen IV Program. There are significant opportunities to adopt condition-based maintenance when upgrades are implemented at existing facilities. The economic benefit from a predictive maintenance program based on advanced on-line monitoring and advanced diagnostics can be demonstrated from a cost/benefit analysis. An analysis of the 104 U.S. legacy systems has indicated potential savings at over $1B per year when applied to all key equipment; a summary of the supporting analysis is provided in this paper. (author)

  5. Diagnosis of Thermal Efficiency of Nuclear Power Plants Using Optical Torque Sensors

    International Nuclear Information System (INIS)

    A new optical torque measuring method was applied to diagnosis of thermal efficiency of nuclear power plants. The sensor allows torque deformation of the rotor caused by power transmission to be measured without contact. Semiconductor laser beams and small pieces of stainless reflector that have bar-code patterns are employed. The intensity of the reflected laser beam is measured and then input into a computer through an APD and an A/D converter having high frequency sampling rates. The correlation analysis technique can translate these data into the torque deformation angle. This angle allows us to obtain the turbine output along with the torsional rigidity and the rotating speed of the rotor. The sensor was applied to a nuclear plant of Tokyo Electric Power Company, TEPCO, following its application success to the early combined cycle plants and the advanced combined cycle plants of TEPCO. As the turbine rotor of the nuclear power plant is less exposed than that of the combined cycle plants, the measurement position is confined to a narrow gap. In order to overcome the difficulty in installation, the shape of the sensor is modified to be long and thin. Sensor performance of the nuclear power plant was inspected over a year. The value of the torsional rigidity was analyzed by the finite element method at first. Accuracy was improved by correcting the torsional rigidity so that the value was consistent with the generator output. As a result, it is considered that the sensor performance has reached a practical use level. (authors)

  6. Selecting safety standards for nuclear power plants

    International Nuclear Information System (INIS)

    Today, many thousands of documents are available describing the requirements, guidelines, and industrial standards which can be used as bases for a nuclear power plant programme. Many of these documents relate to nuclear safety which is currently the focus of world-wide attention. The multitude of documents available on the subject, and their varying status and emphasis, make the processes of selection and implementation very important. Because nuclear power plants are technically intricate and advanced, particularly in relation to the technological status of many developing countries, these processes are also complicated. These matters were the subject of a seminar held at the Agency's headquarters in Vienna last December. The IAEA Nuclear Safety Standards (NUSS) programme was outlined and explained at the Seminar. The five areas of the NUSS programme for nuclear power plants cover, governmental organization, siting, design; operation; quality assurance. In each area the Agency has issued Codes of Practice and is developing Safety Guides. These provide regulatory agencies with a framework for safety. The Seminar recognized that the NUSS programme should enable developing countries to identify priorities in their work, particularly the implementation of safety standards. The ISO activities in the nuclear field are carried out in the framework of its Technical Committee 85 (ISO/TC85). The work is distributed in sub-committees. Seminar on selection and implementation of safety standards for nuclear power plants, jointly organized by the IAEA and the International Organization for Standardization (ISO), and held in Vienna from 15 to 18 December 1980 concerned with: terminology, definitions, units and symbols (SC-1), radiation protection (SC-2), power reactor technology (SC-3), nuclear fuel technology (SC-5). There was general agreement that the ISO standards are complementary to the NUSS codes and guides. ISO has had close relations with the IAEA for several years

  7. China’s Nuclear Power Plants in Operation

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

    Qinshan Plant Phase I Located in Haiyan,Zhejiang Province,Qinshan Nuclear Power Plant Phase I is t he first 300-megawatt pressurized water reactor (PWR) nuclear power plant independently designed,constructed,operated and managed by China.The plant came into commercial operation in April 1994.

  8. Energy expenditure involved in building and operating nuclear power plants

    International Nuclear Information System (INIS)

    In the public discussion about the economic benefits of nuclear power it was argued recently that more energy was required to build and operate nuclear power plants than would be generated by those plants. Three authors, one of them working at a nuclear research center (KFA Juelich), one with a utility (RWE), and one with a reactor manufacturer (KWU), have studied this question. It is seen that the energy expenditure is roughly the same for a coal fired power plant and a nuclear power plant and that all the energy needed to build a nuclear power plant can be 'recovered' in one month of full power operation. (orig.)

  9. Thermal and nuclear power plant design

    International Nuclear Information System (INIS)

    Research on heat transfer processes makes use of the concept of exergy or usable energy. The design of thermal power plants, which produce energy, make use of this fundamental entity, that conditions the final balance of work production. The different types of thermal power plant of the steam and gas type, together with nuclear power plants are reviewed. Heat losses, equal to more than half of the heat input, are the consequence of irreversible transformations of the energy of the fuel employed. It is important to implement resuperheating, so as to reduce the energy loss at high temperature. This is also enhanced by the use of a high steam pressure. The major parameters inherent in the design of the firebox associated with the gas turbine, are identified. The use of combined gas/steam cycles, allowing low exergy losses, has been spreading in recent years. The different systems used for nuclear power plants, for which the heat transfer aspect is crucial are examined. Future developments will depend on the high temperature behaviour of materials, because of the vital importance of thermal fatigue

  10. 78 FR 50458 - Entergy Nuclear Operations, Inc., James A. Fitzpatrick Nuclear Power Plant, Vermont Yankee...

    Science.gov (United States)

    2013-08-19

    ... COMMISSION Entergy Nuclear Operations, Inc., James A. Fitzpatrick Nuclear Power Plant, Vermont Yankee Nuclear Power Station, Pilgrim Nuclear Power Station, Request for Action AGENCY: Nuclear Regulatory Commission... petitioners'') has requested that the NRC take action with regard to James A. Fitzpatrick Nuclear Power......

  11. Fatigue monitoring in Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Ware, A.G.; Shah, V.N. [Idaho National Engineering Laboratory, Idaho Falls, ID (United States)

    1995-04-01

    This paper summarizes fatigue monitoring methods and surveys their application in the nuclear power industry. The paper is based on a review of the technical literature. Two main reasons for fatigue monitoring are more frequent occurrence of some transients than that assumed in the fatigue design analysis and the discovery of stressors that were not included in the fatigue design analysis but may cause significant fatigue damage at some locations. One fatigue monitoring method involves use of plant operating data and procedures to update the fatigue usage. Another method involves monitoring of plant operating parameters using existing, or if needed, supplementary plant instrumentation for online computation of fatigue usage. Use of fatigue monitoring has better defined the operational transients. Most operational transients have been found less severe and fewer in numbers than anticipated in the design fatigue analysis. Use of fatigue monitoring has assisted in quantifying newly discovered stressors and has helped in detecting the presence of thermal stratification of unsuspected locations.

  12. Nuclear power plant safety and reliability assurance

    International Nuclear Information System (INIS)

    The philosophy of nuclear power plant safety is that design should follow established and conservative engineering practices, there should be safety margins in all modes of plant operations, special systems should be provided for response to accidents, and safety systems should have redundant components. This philosophy provides ''defense in depth.'' In recent years, with the accumulation of operating experience and the unexpected complexity of the present generation of light water reactors, the defense in depth philosophy has been supplemented by risk and reliability assessments. Reliability assurance programs based on these probabilistic engineering assessments provide a means of integrating design review, maintenance, testing, replacement of parts, failure reporting, and corrective action, so that the protection of the plant and the public can be systematically ensured

  13. Commissioning procedures for nuclear power plants

    International Nuclear Information System (INIS)

    This Safety Guide was prepared as part of the Agency's programme, referred to as the NUSS programme, for establishing Codes of Practice and Safety Guides relating to nuclear power plants. It deals with the commissioning of all types of land-based stationary thermal neutron power plants. Its purpose is to give guidance on the good practices currently adopted, the implementation of which will enable commissioning to proceed safely. It will also enable the necessary assurances to be provided that the plant has been constructed and can operate in accordance with the design intent. The Guide covers commissioning programme requirements, organization and management, test and review procedures, and the interfaces with construction and with operating activities. It also covers the control of changes and the documentation required during commissioning

  14. Intelligent distributed control for nuclear power plants

    International Nuclear Information System (INIS)

    This project was initiated in September 1989 as a three year project to develop and demonstrate Intelligent Distributed Control (IDC) for Nuclear Power Plants. There were two primary goals of this research project. The first goal was to combine diagnostics and control to achieve a highly automated power plant as described by M.A. Schultz. The second goal was to apply this research to develop a prototype demonstration on an actual power plant system, the EBR-2 steam plant. Described in this Final (Third Annual) Technical Progress Report is the accomplishment of the project's final milestone, an in-plant intelligent control experiment conducted on April 1, 1993. The development of the experiment included: simulation validation, experiment formulation and final programming, procedure development and approval, and experimental results. Other third year developments summarized in this report are: (1) a theoretical foundation for Reconfigurable Hybrid Supervisory Control, (2) a steam plant diagnostic system, (3) control console design tools and (4) other advanced and intelligent control

  15. Alien and invasive species in plant communities of the Vistula and Brennica rivers gravel bars (Western Carpathians, Poland

    Directory of Open Access Journals (Sweden)

    Wilczek Zbigniew

    2015-06-01

    Full Text Available Gravel bars are the initial habitats, inseparably connected to the mountain streams. On the one hand, they are an unstable substrate, influenced by the overflows and high waters; however, they are also exposed to strong sunlight and heat. This situation determines specific vegetation which, due to dynamic changes in the habitat, has a pioneer character. What is more, gravel bars are areas where many river migratory species and many random species appear. Among them, there are also synanthropic species. In years 2011-2012, floristic and phytosociological studies were conducted in the Silesian Beskids. The goal of these studies was to recognize the vegetation of the gravel bars of the Vistula and the Brennica rivers - from their springs in the Silesian Beskids to the point where the Brennica River flows into the Vistula River in the Silesian Foothills. The studied section of the two rivers is regulated. Particular attention was paid to the synanthropic species that pose a threat to the native flora. In 9 recognized types of plant communities, 293 vascular plant species were recognized. More than 15% of the flora were alien species (45 and 22 of them were considered to be invasive. The most common invasive species that were spotted included: Impatiens glandulifera, Heracleum mantegazzianum and Reynoutria japonica. Plant communities with the biggest number and share of alien species were Plantago major-Barbarea vulgaris community and Phalaridetum arundinaceae.

  16. Exergoeconomic analysis of a nuclear power plant

    Science.gov (United States)

    Moreno, Roman Miguel

    Exergoeconomic analysis of a nuclear power plant is a focus of this dissertation. Specifically, the performance of the Palo Verde Nuclear Power Plant in Arizona is examined. The analysis combines thermodynamic second law exergy analysis with economics in order to assign costs to the loss and destruction of exergy. This work was done entirely with an interacting spreadsheets notebook. The procedures are to first determine conventional energy flow, where the thermodynamic stream state points are calculated automatically. Exergy flow is then evaluated along with destruction and losses. The capital cost and fixed investment rate used for the economics do not apply specifically to the Palo Verde Plant. Exergy costing is done next involving the solution of about 90 equations by matrix inversion. Finally, the analysis assigns cost to the exergy destruction and losses in each component. In this work, the cost of electricity (exergy), including capital cost, leaving the generator came to 38,400 /hr. The major exergy destruction occurs in the reactor where fission energy transfer is limited by the maxiμm permissible clad temperature. Exergy destruction costs were: reactor--18,207 hr, the low pressure turbine-2,000 /hr, the condenser--1,700 hr, the steam generator-1,200 $/hr. The inclusion of capital cost and O&M are important in new system design assessments. When investigating operational performance, however, these are sunk costs; only fuel cost needs to be considered. The application of a case study is included based on a real modification instituted at Palo Verde to reduce corrosion steam generator problems; the pressure in the steam generator was reduced from 1072 to 980 psi. Exergy destruction costs increased in the low pressure turbine and in the steam generator, but decreased in the reactor vessel and the condenser. The dissertation demonstrates the procedures and tools required for exergoeconomic analysis whether in the evaluation of a new nuclear reactor system

  17. Seed retention by pioneer trees enhances plant diversity resilience on gravel bars: Observations from the river Allier, France

    Science.gov (United States)

    Corenblit, Dov; Vidal, Vincent; Cabanis, Manon; Steiger, Johannes; Garófano-Gómez, Virginia; Garreau, Alexandre; Hortobágyi, Borbála; Otto, Thierry; Roussel, Erwan; Voldoire, Olivier

    2016-07-01

    Pioneer riparian trees which establish in river active tracts on gravel bars enhance fine sediment retention during high flows within their stands and in their lee side, forming obstacle marks. Fine sediment retention can be accompanied by deposition of seeds transported by water dispersal, i.e. by hydrochory. We tested the hypothesis that pioneer riparian trees significantly control seed deposition on gravel bars by forming sediment obstacle marks. We described the seed bank structure and compared samples collected from obstacle marks and bare coarse-grained bar surfaces. At the surface (at 2 cm depth), seed abundance (N) and richness (S) (expressed as mean ± sd) were significantly higher in areas directly affected by riparian trees, i.e. obstacle marks, (N: 693 ± 391; S: 17 ± 3) than in bare surfaces (N: 334 ± 371; S: 13 ± 5). Surface and sub-surface (at 20 cm depth) samples were also significantly different, with the sub-surface samples almost devoid of seeds (respectively N: 514 ± 413; S: 15 ± 5 and N: 3 ± 6; S: 1 ± 2). These results suggest a biogeomorphic feedback between sediment and associated seed retention mediated by hydrochory, vegetation growth and local seed dispersal mediated by barochory. Such feedback may improve plant diversity resilience on gravel alluvial bars of high-energy rivers.

  18. Regulatory control of nuclear power plants

    International Nuclear Information System (INIS)

    The purpose of this book is to support IAEA training courses and workshops in the field of regulatory control of nuclear power plants as well as to support the regulatory bodies of Member States in their own training activities. The target group is the professional staff members of nuclear safety regulatory bodies supervising nuclear power plants and having duties and responsibilities in the following regulatory fields: regulatory framework; regulatory organization; regulatory guidance; licensing and licensing documents; assessment of safety; and regulatory inspection and enforcement. Important topics such as regulatory competence and quality of regulatory work as well as emergency preparedness and public communication are also covered. The book also presents the key issues of nuclear safety such as 'defence-in-depth' and safety culture and explains how these should be taken into account in regulatory work, e.g. during safety assessment and regulatory inspection. The book also reflects how nuclear safety has been developed during the years on the basis of operating experience feedback and results of safety research by giving topical examples. The examples cover development of operating procedures and accident management to cope with complicated incidents and severe accidents to stress the importance of regulatory role in nuclear safety research. The main target group is new staff members of regulatory bodies, but the book also offers good examples for more experienced inspectors to be used as comparison and discussion basis in internal workshops organized by the regulatory bodies for refreshing and continuing training. The book was originally compiled on the basis of presentations provided during the two regulatory control training courses in 1997 and 1998. The textbook was reviewed at the beginning of the years 2000 and 2002 by IAEA staff members and consistency with the latest revisions of safety standards have been ensured. The textbook was completed in the

  19. Maintenance technologies on nuclear power plants

    International Nuclear Information System (INIS)

    As nuclear power plants in Japan are proud of their operation results with high reliability at a viewpoint of the world, one of main factors supporting on this high reliability is 'maintenance'. On the other hand, U.S.A. has not carried out thorough preventive maintenance like Japan but systematically progressed adequacy of maintenance at a center of condition based maintenance (CBM) under its success. In Japan, reduction of periodical inspection time and introduction of the CBM are begun to wrestle with adequacy of maintenance. Here was introduced on efforts on maintenance, inspection and technical development carried out at the nuclear power plants, and also on actions on 'maintenance' in Japan. Here were described on present state of maintenance and inspection in the nuclear power stations, efforts to reduce periodical inspection time, efforts on countermeasure for high aging, conditions on technical development of maintenance and inspection, working results on renewal engineering of large scale apparatuses, and efforts on upgrading of technology on maintenance and inspection. (G.K.)

  20. Recent advances in nuclear power plant simulation

    International Nuclear Information System (INIS)

    The field of industrial simulation has experienced very significant progress in recent years, and power plant simulation in particular has been an extremely active area. Improvements may be recorded in practically all simulator subsystems. In Europe, the construction of new full- or optimized-scope nuclear power plant simulators during the middle 1990's has been remarkable intense. In fact, it is possible to identify a distinct simulator generation, which constitutes a new de facto simulation standard. Thomson Training and Simulation has taken part in these developments by designing, building, and validation several of these new simulators for Dutch, German and French nuclear power plants. Their characteristics are discussed in this paper. The following main trends may be identified: Process modeling is clearly evolving towards obtaining engineering-grade performance, even under the added constraints of real-time operation and a very wide range of operating conditions to be covered; Massive use of modern graphic user interfaces (GUI) ensures an unprecedented flexibility and user-friendliness for the Instructor Station; The massive use of GUIs also allows the development of Trainee Stations (TS), which significantly enhance the in-depth training value of the simulators; The development of powerful Software Development Environments (SDE) enables the simulator maintenance teams to keep abreast of modifications carried out in the reference plants; Finally, simulator maintenance and its compliance with simulator fidelity requirements are greatly enhanced by integrated Configuration Management Systems (CMS). In conclusion, the power plant simulation field has attained a strong level of maturity, which benefits its approximately forty years of service to the power generation industry. (author)

  1. Radiation emergency preparedness in nuclear power plants

    International Nuclear Information System (INIS)

    The purpose of planning for radiation emergency response is to ensure adequate preparedness for protection of the plant personnel and members of the public from significant radiation exposures in the unlikely event of an accident. With a number of safety features in the reactor design and sound operating procedures, the probability of a major accident resulting in the releases of large quantities of radioactivity is extremely small. However, as an abundant cautious approach a comprehensive radiation emergency response preparedness is in place in all the nuclear power plants (NPPs). Radiation Emergency in NPPs is broadly categorized into three types; plant emergency, site emergency and off-site emergency. During off site emergency conditions, based on levels of radiation in the environment, Civil Authorities may impose several counter measures such as sheltering, administering prophylaxis (stable iodine for thyroid blocking) and evacuation of people from the affected area. Environmental Survey Laboratory (ESL) carries out environmental survey extensively in the affected sector identified by the meteorological survey laboratory. To handle emergency situations, Emergency Control Centre with all communication facility and Emergency Equipment Centre having radiation measuring instruments and protective equipment are functional at all NPPs. AERB stipulates certain periodicity for conducting the exercises on plant, site and off site emergency. These exercises are conducted and deficiencies corrected for strengthening the emergency preparedness system. In the case of off site emergency exercise, observers are invited from AERB and Crisis Management Group of Department of Atomic Energy (DAE). The emergency exercises conducted by Nuclear Power Plant Sites have been very satisfactory. (author)

  2. 75 FR 16524 - FirstEnergy Nuclear Operating Company, Perry Nuclear Power Plant; Exemption

    Science.gov (United States)

    2010-04-01

    ... COMMISSION FirstEnergy Nuclear Operating Company, Perry Nuclear Power Plant; Exemption 1.0 Background First.... NFP-58, which authorizes operation of the Perry Nuclear Power Plant, Unit 1 (PNPP). The license..., ``Requirements for physical protection of licensed activities in nuclear power reactors against...

  3. Decontamination of operational nuclear power plants

    International Nuclear Information System (INIS)

    In order to reduce the radiation fields around nuclear power plants, and, consequently, to limit the radiation exposure of and dose commitments to the operating and maintenance personnel, the contamination build-up should be kept to a minimum. The most fruitful approach, from the point of view of economics and efficiency, is to tackle the problems of contamination and decontamination in the design and construction phases of the reactor. To do this, knowledge gained from the operation of existing power reactors should be used to make improvements in new designs. New structural materials with low corrosion rates or whose constituents are not activated by neutrons should also be used. For older reactors, in most cases it is already too late to incorporate design changes without extensive and expensive modifications. For these plants, decontamination remains the most efficient way to reduce radiation fields. The aim of this report is to deal with the different decontamination methods that may be applied to nuclear power plant circuits and equipment during operation. The factors that have to be considered in determining the type and the extent of the methods used are the engineering and the planning of the decontamination operation and the treatment of the resulting waste generated during the process are also discussed

  4. Analysis of nuclear power plant construction costs

    International Nuclear Information System (INIS)

    The objective of this report is to present the results of a statistical analysis of nuclear power plant construction costs and lead-times (where lead-time is defined as the duration of the construction period), using a sample of units that entered construction during the 1966-1977 period. For more than a decade, analysts have been attempting to understand the reasons for the divergence between predicted and actual construction costs and lead-times. More importantly, it is rapidly being recognized that the future of the nuclear power industry rests precariously on an improvement in the cost and lead-time situation. Thus, it is important to study the historical information on completed plants, not only to understand what has occurred to also to improve the ability to evaluate the economics of future plants. This requires an examination of the factors that have affected both the realized costs and lead-times and the expectations about these factors that have been formed during the construction process. 5 figs., 22 tabs

  5. Nuclear Power Plant Control and Instrumentation 1989

    International Nuclear Information System (INIS)

    The meeting of the International Working Group on Nuclear Power Plant Control and Instrumentation (IWG-NPPCI) was organized in order to summarize operating experience of nuclear power plant control systems, gain a general overview of activities in development of modern control systems and receive recommendations on the further directions and particular measures within the Agency's programme. The meeting was held at the IAEA Headquarters in Vienna and was attended by 21 national delegates and observers from 18 countries. The present volume contains: (1) report on the meeting of the IWG-NPPCI, Vienna, 8-10 May 1989, (2) report of the scientific secretary on the major activities of IAEA during 1987-89 in the NPPCI area, (3) terms of reference International Working Group on NPPCI and (4) reports of the national representatives to the International Working Group on NPPCI. The paper and discussions with practical experience and described actual problems encountered. Emphasis was placed on the technical, industrial and economical aspects of the introduction of modern control systems and on the improvement of plant availability and safety. A separate abstract was prepared for each of the 19 papers presented by members of the International Working Group. Refs, figs and tabs

  6. Strategies for competitive nuclear power plants

    International Nuclear Information System (INIS)

    This technical publication on competitive strategies for nuclear power plants (NPPs) is part of an ongoing project on management of NPP operations in a competitive environment. The overall objective of this project is to assist the management of operating organizations and NPPs in identifying and implementing appropriate measures to remain competitive in a rapidly changing business environment. Other documents that have been written on this topic have focused on how the environment in which NPPs operate is changing. This report instead focuses on strategies and techniques that operating organization and NPP managers can use to succeed in this environment. Of particular note is ongoing OECD/NEA work to describe the environment for nuclear power in competitive electricity markets. The main objective of the OECD/NEA study is to review the impacts of increasing market competition on the nuclear power sectors in OECD Member countries. The OECD/NEA study is identifying various nuclear aspects which have to be considered in relation to the regulatory reform of the electricity sector in OECD Member States. The OECD/NEA work was co-ordinated with the development of this IAEA report; staff members from the two organizations participated in the development and review of the associated documents. Thus, the strategies and techniques identified in this report are consistent with the impacts of increasing market competition identified in the OECD/NEA study

  7. Risk perception among nuclear power plant employees

    International Nuclear Information System (INIS)

    Radiation protection training and general employee training within the nuclear industry are designed to reduce workers' concerns about radiation and to develop skills that will protect against unwarranted exposures. Inaccurate perceptions about radiation by workers can cause a lack of adequate concern or exaggerated fears, which in turn can result in unnecessary radiation exposure to the worker or co-workers. The purpose of the study is threefold: (a) to identify health and safety concerns among nuclear power plant employees, (b) to discover variables that influence the perception of risk among employees, and (c) to ascertain if attitudes of the family, community, and the media affect workers' perception of risk. Workers identified five areas of concern: shift work, radiation, industrial safety, stress, and sabotage

  8. Analysis of failed nuclear plant components

    Science.gov (United States)

    Diercks, D. R.

    1993-12-01

    Argonne National Laboratory has conducted analyses of failed components from nuclear power- gener-ating stations since 1974. The considerations involved in working with and analyzing radioactive compo-nents are reviewed here, and the decontamination of these components is discussed. Analyses of four failed components from nuclear plants are then described to illustrate the kinds of failures seen in serv-ice. The failures discussed are (1) intergranular stress- corrosion cracking of core spray injection piping in a boiling water reactor, (2) failure of canopy seal welds in adapter tube assemblies in the control rod drive head of a pressurized water reactor, (3) thermal fatigue of a recirculation pump shaft in a boiling water reactor, and (4) failure of pump seal wear rings by nickel leaching in a boiling water reactor.

  9. Safety and environmental impact of nuclear power plants

    International Nuclear Information System (INIS)

    The proceedings contains the full texts of 12 papers which all fall under the INIS scope. The papers deal with the general aspects of nuclear safety, such as the physical and technical principles of nuclear reactors and the socio-legal aspects of the preparation of the construction and operation of nuclear power plants. Also discussed are questions of quality assurance of equipment and questions of operating safety, the disposal of radioactive wastes and nuclear power plant accidents and the environmental impacts of nuclear power plants, including a comparison of their impact with that of conventional power plants. (Z.M.)

  10. Pile foundation of nuclear power plant structures

    International Nuclear Information System (INIS)

    The subject of pile foundation used for nuclear power plant structures, considering the experience gained by the designers of the Angra Nuclear Power Plant, Units 2 and 3 in Brazil is dealt with. The general concept of the pile foundations, including types and execution of the piles, is described briefly. Then the two basic models, i.e. the static model and the dynamic one, used in the design are shown, and the pertinent design assumptions as related to the Angra project are mentioned. The criteria which established the loading capacity of the piles are discussed and the geological conditions of the Angra site are also explained briefly, justifying the reasons why pile foundations are necessary in this project. After that, the design procedures and particularly the tools - i.e. the computer programs - are described. It is noted that the relatively simple but always time consuming job of loading determination calculations can be computerized too, as it was done on this project through the computer program SEASA. The interesting aspects of soil/structure interaction, applicable to static models, are covered in detail, showing the theoretical base wich was used in the program PILMAT. Then the advantage resulting from computerizing of the job of pile reinforcement design are mentioned, describing briefly the jobs done by the two special programs PILDES and PILTAB. The point is stressed that the effort computerizing the structural design of this project was not so much due to the required accuracy of the calculations, but mainly due to the need to save on the design time, as to allow to perform the design task within the relatively tight time schedule. A conclusion can be drawn that design of pile foundations for nuclear power plant structures is a more complex task than the design of bearing type of foundation for the same structures, but that the task can be always made easier when the design process can be computerized. (Author)

  11. Nuclear power plants. Safe and efficient decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Huger, Helmut [TUEV SUED Energietechnik GmbH, Filderstadt (Germany). Div. of Radiation Protection, Waste Management and Decommissioning; Woodcock, Richard [TUEV SUED Nuclear Technologies, Warrington, Cheshire (United Kingdom). Environment and Radioactive Waste Management

    2016-02-15

    The process of dismantling a nuclear power plant consists of several phases that involve significant challenges along the way for authorities, operators, and suppliers. It is necessary to ensure safety at all times and to achieve certainty in respect of key project parameters, especially time and cost. Therefore, careful planning as well as detailed knowledge of local standards and regulations, best available techniques and practical implementation strategies are crucial. Independent expertise and knowledge service can be utilised for demanding projects worldwide. This guarantees safety for people and the environment in every phase of decommissioning. The article gives an overview on different decommissioning options and their challenges.

  12. The Daya Bay nuclear power plant

    International Nuclear Information System (INIS)

    The Daya Bay plant is nearing completion for the Guangdong Nuclear Power Joint Venture Company (GNPJVC), formed by the Chinese Government (75%) in conjunction with China Light Power, the Hong Kong utility (25%). 70% of generated power from two French-design 900 MWe class PWRs will be supplied to Hong Kong (the reference units: France's Gravelines-5 and -6). The Advanced Fuel Assembly designed by Framatome is used. The turbines are British-built (GEC) and designed differently from those installed in French units. 1 fig

  13. Knowledge management in nuclear power plants

    International Nuclear Information System (INIS)

    This article aims to show the importance of knowledge management from different perspectives. In this first part part of the article, the overall approach that performs CNAT of knowledge management is described. In the second part, a specific aspect of knowledge management in ANAV, tacit knowledge transfer is showed. finally, the third part discusses the strategies and actions that are followed in CNCO for knowledge management. All this aims to show an overview of knowledge management held in the Spanish Nuclear Power Plants. (Author)

  14. Dynamic analysis of Leningrad nuclear power plant

    International Nuclear Information System (INIS)

    Within the scope of this study a preliminary dynamic analysis for the detonation explosion and earthquake load cases was carried out for the Leningrad Nuclear Power Plant. A soil model was added to the three-dimensional shell model which was taken over from IVO (Finland). During this Research Program the model was translated into the STARDYNE program and was investigated by means of time history modal analysis. Since the status quo of the documentation available at that time had to be completed through useful technical assumptions this report only considers exemplary selected results

  15. Organizational processes and nuclear power plant safety

    International Nuclear Information System (INIS)

    The paper describes the effects organizational factors have on the risk associated with the operation of nuclear power plants. The described research project addresses three methods for identifying the organizational factors that impact safety. The first method consists of an elaborate theory-based protocol dealing with decision making procedures, interdepartmental coordination of activities, and communications. The second, known as goals/means/measures protocol, deals with identifying safey related goals. The third method is known as behaviorally anchored rating scale development. The paper discusses the importance of the convergence of these three methods to identify organizational factors essential to reactor safety

  16. Modernization of electric power systems of the Laguna Verde Nuclear Power Plant; Modernizacion de los sistemas electricos de potencia de la Central Nuclear de Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Gabaldon, M. A.; Gonzalez, J. J.; Prieto, I.

    2011-07-01

    The Power Increase Project of Laguna Verde Nuclear Plant has entailed the replacement, in one unique outage, of the main power electrical systems of the Plant (Isolated Phase Bars, Generator Circuit Breaker and Main Transformer) as well as the replacement of the Turbo-group. The simultaneous substitution of these entire system has never been done by any other Plant in the world, representing an engineering challenge that embraced the design of the new equipment up to the planning, coordination and management of the construction and commissioning works, which were successfully carried out by Iberdrola within the established outage period /47 days) for both units. (Author)

  17. Earthquake protection of nuclear power plant equipment

    Energy Technology Data Exchange (ETDEWEB)

    Nawrotzki, Peter [GERB Vibration Control Systems, Berlin (Germany)

    2010-05-15

    Power plant machinery can be dynamically decoupled from the substructure by the effective use of helical steel springs and viscous dampers. Turbine foundations, boiler feed pumps and other machine foundations benefit from this type of elastic support systems to mitigate the transmission of operational vibration. The application of these devices may also be used to protect against earthquakes and other catastrophic events, i.e. airplane crash, of particular importance in nuclear facilities. This article illustrates basic principles of elastic support systems and applications on power plant buildings in medium and high seismic areas. Spring-damper combinations with special stiffness properties are used to reduce seismic acceleration levels of turbine components and other safety or non-safety related structures. For turbine buildings, the integration of the turbine substructure into the machine building can further reduce stress levels in all structural members. (orig.)

  18. Quality assurance auditing for nuclear power plants

    International Nuclear Information System (INIS)

    This Safety Guide provides requirements and recommendations for establishing and implementing a system of internal and external audits during the design, manufacture, construction, commissioning and operation of nuclear power plants. It provides for the planning, performance, reporting and follow-up of the quality assurance audit activity. It defines in general terms the responsibilities of the auditing and audited organizations. The Guide also covers auditing in the context of supplier evaluation; it does not include inspection for the sole purpose of process control or product acceptance. Like the Code, the present Guide was prepared as part of the IAEA's programme, referred to as the NUSS programme, for establishing Codes of Practice and Safety Guides relating to land-based stationary thermal neutron power plants

  19. Nuclear Plants in the Vicinity of Borders

    International Nuclear Information System (INIS)

    The siting of nuclear power plants in border areas is decided according to 'national criteria' which are governed by the cost/benefit principle, i.e. a comparison between investment and profit; human values are taken into consideration by transforming them into financial values according to the 'quantification' procedure. However ecology cannot be quantified as it is linked to the great complexity of the natural system. To harmonize technical criteria and ecological requirements, the jurist suggests a legal system of indemnity which takes into account both damage which has already occurred and the degree of probability of its occurrence. Thus a new criterion would be introduced in the decision-making process on plant siting: compensation costs for the national population and for the neighbouring countries would then be a factor in cost/benefit calculations. (NEA)

  20. Nuclear security - New challenge to the safety of nuclear power plants

    International Nuclear Information System (INIS)

    The safety of nuclear power plants involves two aspects: one is to prevent nuclear accidents resulted from systems and equipments failure or human errors; the other is to refrain nuclear accidents from external intended attack. From this point of view, nuclear security is an organic part of the nuclear safety of power plants since they have basically the same goals and concrete measures with each other. In order to prevent malicious attacks; the concept of physical protection of nuclear facilities has been put forward. In many years, a series of codes and regulations as well as technical standard systems on physical protection had been developed at international level. The United Nations passed No. 1540 resolution as well as 'Convention on the Suppression of Acts of Nuclear terrorism', and revised 'Convention on Physical Protection of Nuclear Materials', which has enhanced a higher level capacity of preparedness by international community to deal with security issues of nuclear facilities. In China, in order to improve the capability of nuclear power plants on preventing and suppressing the external attacks, the Chinese government consecutively developed the related codes and standards as well as technical documents based on the existing laws and regulations, including 'Guide for the Nuclear Security of Nuclear Power Plants' and 'Guide for the Physical Protection of Nuclear Materials', so as to upgrade the legislative requirements for nuclear security in power plants. The government also made greater efforts to support the scientific research and staff training on physical protection, and satisfying the physical protection standards for newly-built nuclear facilities such as large scale nuclear power plants to meet requirement at international level. At the same time old facilities were renovated and the Chinese government established a nuclear emergency preparedness coordination mechanism, developed corresponding emergency preparedness plans, intensified the

  1. Localization of nuclear power plant technology

    International Nuclear Information System (INIS)

    -effective localization of nuclear power in Asia. Nuclear power is more capital intensive than most other power generation options. This results in the electricity cost to the end user being more influenced by the initial cost than fuel, and other operations and maintenance expenses. Because developing nations typically have lower wages, it's a natural conclusion to maximize local capabilities to drive the capital cost as low as possible. To facilitate localization, new approaches to expediting the formation of a credible nuclear technology infrastructure in these emerging commercial nuclear power nations is discussed. This paper will examine localization of nuclear technology as one of the most promising methods to make nuclear power more affordable to the emerging markets in Asia. Localization will allow for the utilization of lower cost, local labor in the design, manufacture and construction of new nuclear power plants. ABB's practical localization philosophy is discussed with reference to previous experience and future expectations. (author)

  2. A potent effect of strong $\\bar{\\mbox{p}}-$p nuclear forces on the rate of the low-energy three-body protonium formation reaction: $\\bar{\\mbox{p}} + (\\mbox{p}\\mu^-)_{1s} \\rightarrow (\\bar{\\mbox{p}} \\mbox{p})_{\\alpha} + \\mu^-$

    CERN Document Server

    Sultanov, Renat A; Adhikari, Sadhan K

    2016-01-01

    The effect of the strong $\\bar{\\rm p}-$p nuclear interaction in a three-charge-particle system with arbitrary masses is investigated. Specifically, the ($\\bar{\\rm p},\\ \\mu^-$,\\ p) system is considered. A numerical computation in the framework of a detailed few-body approach is carried out for the following protonium (antiprotonic hydrogen) production three-body reaction: $\\bar{\\mbox{p}} +(\\mbox{p}\\mu^-)_{1s} \\rightarrow (\\bar{\\mbox{p}}\\rm{p})_{1s} + \\mu^-$. Here, p is a proton, $\\bar{\\mbox{p}}$ is an antiproton, $\\mu^-$ is a muon, and a bound state of $\\mbox{p}^+$ and its counterpart $\\bar{\\mbox{p}}$ is protonium: $Pn = (\\bar{\\mbox{p}}\\mbox{p})$. The low-energy cross sections and rates of the $Pn$ formation reaction are computed in the framework of a Faddeev-like equation formalism. The strong $\\bar{\\mbox{p}}-$p interaction is included in these calculations within a first order approximation. It was found, that the inclusion of this strong interaction results in a quite significant correction to the output of...

  3. Reliability-centered maintenance improves operations at TMI nuclear plant

    International Nuclear Information System (INIS)

    This article describes one of the first comprehensive power plant demonstrations of reliability-centered maintenance which has been successfully implemented at the Three Mile Island nuclear plant. The equipment failure trend is down significantly. This program implemented at the TMI nuclear plant is, to date, one of the most comprehensive applications of RCM methodology to a US power generation plant. Top corporate management and plant staff consider the program to be an outstanding success

  4. General digitalized system on nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Akagi, Katsumi; Kadohara, Hozumi; Taniguchi, Manabu [Mitsubishi Electric Corp., Tokyo (Japan)

    2000-08-01

    Hitherto, instrumentation control system in a PWR nuclear power plant has stepwisely adopted digital technology such as application of digital instrumentation control device to ordinary use (primary/secondary system control device, and so on), application of CRT display system to monitoring function, and so forth, to realize load reduction of an operator due to expansion of operation automation range, upgrading of reliability and maintenance due to self-diagnosis function, reduction of mass in cables due to multiple transfer, and upgrading of visual recognition due to information integration. In next term PWR plant instrumentation control system, under consideration of application practice of conventional digital technology, application of general digitalisation system to adopt digitalisation of overall instrumentation control system containing safety protection system, and central instrumentation system (new type of instrumentation system) and to intend to further upgrade economics, maintenance, operability/monitoring under security of reliability/safety is planned. And, together with embodiment of construction program of the next-term plant, verification at the general digitalisation proto-system aiming at establishment of basic technology on the system is carried out. Then, here was described on abstract of the general digitalisation system and characteristics of a digital type safety protection apparatus to be adopted in the next-term plant. (G.K.)

  5. General digitalized system on nuclear power plants

    International Nuclear Information System (INIS)

    Hitherto, instrumentation control system in a PWR nuclear power plant has stepwisely adopted digital technology such as application of digital instrumentation control device to ordinary use (primary/secondary system control device, and so on), application of CRT display system to monitoring function, and so forth, to realize load reduction of an operator due to expansion of operation automation range, upgrading of reliability and maintenance due to self-diagnosis function, reduction of mass in cables due to multiple transfer, and upgrading of visual recognition due to information integration. In next term PWR plant instrumentation control system, under consideration of application practice of conventional digital technology, application of general digitalisation system to adopt digitalisation of overall instrumentation control system containing safety protection system, and central instrumentation system (new type of instrumentation system) and to intend to further upgrade economics, maintenance, operability/monitoring under security of reliability/safety is planned. And, together with embodiment of construction program of the next-term plant, verification at the general digitalisation proto-system aiming at establishment of basic technology on the system is carried out. Then, here was described on abstract of the general digitalisation system and characteristics of a digital type safety protection apparatus to be adopted in the next-term plant. (G.K.)

  6. Applications of RFID into Nuclear Power Plant Maintenance System

    International Nuclear Information System (INIS)

    RFID (Radio Frequency Identification) system, one of the most anticipated ubiquitous technologies is an automatic identification method using devices called RFID tags. RFID antenna detects each approach of RFID tags and recognizes the tags' ID and transfer to reader to do information processing. Since first introduced in the logistics industry, production management and maintenance organization in various fields of domestic and foreign enterprises introduce the RFID. Nuclear power plants are also using RFID to manage materials lately. However, the current status on the use of RFID is just a little more advanced on the use of bar code. Therefore, it seems that the important characteristic of RFID is not enough actualized to keep seeing. In point of Maintenance Information Field based on ubiquitous technology, the most important concept is real-time information processing. And RFID is quite proper to develop this information field system because it satisfies for the matter of that concept. The leading content in ubiquitous maintenance system is that maintenance personnel can get information what he needs and he can also transfer information what he gets whenever and wherever he is. In this paper, some examples of applying RFID in development of ubiquitous maintenance system are suggested

  7. Operating results 2015. Nuclear power plants. Pt. 1

    International Nuclear Information System (INIS)

    A report is given on the opening results achieved in 2015, events important to plant safety, special and relevant repair, and retrofit measures from nuclear power plants in Germany. Reports about nuclear power plants in Belgium, Finland, the Netherlands, Switzerland, and Spain will be published in further issue.

  8. Operating results 2015. Nuclear power plants. Pt. 1

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    2016-05-15

    A report is given on the opening results achieved in 2015, events important to plant safety, special and relevant repair, and retrofit measures from nuclear power plants in Germany. Reports about nuclear power plants in Belgium, Finland, the Netherlands, Switzerland, and Spain will be published in further issue.

  9. Construction Technologies for Nuclear Power Plants

    International Nuclear Information System (INIS)

    One of the IAEA's statutory objectives is to 'seek to accelerate and enlarge the contribution of atomic energy to peace, health and prosperity throughout the world'. One way this objective is achieved is through the publication of a range of technical series. Two of these are the IAEA Nuclear Energy Series and the IAEA Safety Standards Series. According to Statute Article III, A.6, the IAEA safety standards establish 'standards of safety for protection of health and minimization of danger to life and property.' The safety standards include the Safety Fundamentals, Safety Requirements and Safety Guides. These standards are written primarily in a regulatory style, and are binding on the IAEA for its own programmes. The principal users are the regulatory bodies in Member States and other national authorities. The IAEA Nuclear Energy Series comprises reports designed to encourage and assist R and D on and practical application of, nuclear energy for peaceful uses. This includes practical examples to be used by owners and operators of utilities in Member States, implementing organizations, academia, and government officials, among others. This information is presented in guides, reports on technology status and advances, and best practices for peaceful uses of nuclear energy based on inputs from international experts. The IAEA Nuclear Energy Series complements the IAEA Safety Standards Series. There are three distinct significant phases in a nuclear power plant (NPP) project after the signing of a contract; engineering, procurement, and construction and commissioning. Experience gained over the last forty years has shown that the construction phase is one of the most critical phases for the success of a project. Success is defined as completing the project with the specified quality, and within budget and schedule. The key to a successful construction project is to have an established programme that integrates the critical attributes into the overall project. Some of

  10. Reviewing industrial safety in nuclear power plants

    International Nuclear Information System (INIS)

    This document contains guidance and reference materials for Operational Safety Review Team (OSART) experts, in addition to the OSART Guidelines (TECDOC-449), for use in the review of industrial safety activities at nuclear power plants. It sets out objectives for an excellent industrial safety programme, and suggests investigations which should be made in evaluating industrial safety programmes. The attributes of an excellent industrial safety programme are listed as examples for comparison. Practical hints for reviewing industrial safety are discussed, so that the necessary information can be obtained effectively through a review of documents and records, discussions with counterparts, and field observations. There are several annexes. These deal with major features of industrial safety programmes such as safety committees, reporting and investigation systems and first aid and medical facilities. They include some examples which are considered commendable. The document should be taken into account not only when reviewing management, organization and administration but also in the review of related areas, such as maintenance and operations, so that all aspects of industrial safety in an operating nuclear power plant are covered

  11. Alarm-Processing in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Information overload due to the activation of a great number of alarms in a short time is a common problem for the operator in the control room of a industrial plant, mainly in complex process like the nuclear power plants.The problem is the conventional conception of the alarm system, that defines each alarm like a separated and independent entity of the global situation of the plant.A direct consequence is the generation of multiple alarms during a significative disturbance in the process, being most of them redundant and irrelevant to the actual process state wich involves an extra load to the operator, who wastes time in acting selecting the important alarms of the group that appears or lead to a an erroneous action.The present work first describes the techniques developed in the last years to attack the avalanche of alarms problem.Later we present our approach to alarm-processing: an expert system as alarm-filter.Our objective is collect in the system the state of the art in the development of advanced alarm systems, offering an improvement of the information flow to the operators through the suppression of nonsignificant alarms and a structured visualization of the process state.Such support is important during a disturbance for the identification of plant state, diagnosis, consequence prediction and corrective actions.The system is arranged in three stages: alarm-generation, alarm-filter and alarm-presentation.The alarm-generation uses conventional techniques or receives them from an external system.The alarm-filter uses suppression techniques based on: irrelevance analysis with the operation mode and the state of components, causal reasoning and static importance analysis.The alarm presentation is made through a structured way using a priority scheme with three level.The knowledge representation of each alarm is based on frames and a graph of alarms for global knowledge, where the connections between nodes represent causal and irrelevance relations

  12. Team interaction skills evaluation criteria for nuclear power plant control room operators

    International Nuclear Information System (INIS)

    Previous research has shown the value of good team interaction skills to group performance, yet little progress has been made on in terms of how such skills can be measured. In this study rating scales developed previously (Montgomery, et al., 1990) were extensively revised and cast into a Behaviorally Anchored Rating Scale (BARS) and a Behavioral Frequency format. Rating data were collected using 13 training instructors at the Diablo Canyon Nuclear Plant, who rated three videotapes of simulator scenario performance during a day-long training session and later evaluated control room crews during requalification training. High levels of interrater agreement on both rating scales were found. However, the factor structure of the ratings was generally inconsistent with that hypothesized. Analysis of training ratings using Cronbach's components of accuracy (Cronbach, 1955) indicated that BARS ratings generally exhibited less error than did the Behavioral Frequency ratings. The results are discussed in terms of both field and research implications

  13. Design and construction of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Meiswinkel, Ruediger [MBI Bautechnik GmbH, Enkenbach-Alsenborn (Germany); Meyer, Julian [Hochtief Solutions AG Consult IKS Energy, Frankfurt (Germany); Schnell, Juergen [Technical Univ. Kaiserslautern (Germany). Inst. of Concrete Structures and Structural Engineering

    2013-07-01

    Despite all the efforts being put into expanding renewable energy sources, large-scale power stations will be essential as part of a reliable energy supply strategy for a longer period. Given that they are low on CO2 emissions, many countries are moving into or expanding nuclear energy to cover their baseload supply. Building structures required for nuclear installations whose protective function means they are classified as safety-related, have to meet particular construction requirements more stringent than those involved in conventional construction. This book gives a comprehensive overview from approval aspects given by nuclear and construction law, with special attention to the interface between plant and construction engineering, to a building structure classification. All life cycle phases are considered, with the primary focus on execution. Accidental actions on structures, the safety concept and design and fastening systems are exposed to a particular treatment. Selected chapters of the German concrete yearbook ''Beton-Kalender'' are now available in English. The new English BetonKalender Series delivers internationally useful engineering expertise and industrial know-how from Germany.

  14. Electromagnetic Compatibility in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Electromagnetic compatibility (EMC) has long been a key element of qualification for mission critical instrumentation and control (I ampersand C) systems used by the U.S. military. The potential for disruption of safety-related I ampersand C systems by electromagnetic interference (EMI), radio-frequency interference (RFI), or power surges is also an issue of concern for the nuclear industry. Experimental investigations of the potential vulnerability of advanced safety systems to EMI/RFI, coupled with studies of reported events at nuclear power plants (NPPs) that are attributed to EMI/RFI, confirm the safety significance of EMC for both analog and digital technology. As a result, Oak Ridge National Laboratory has been engaged in the development of the technical basis for guidance that addresses EMC for safety-related I ampersand C systems in NPPs. This research has involved the identification of engineering practices to minimize the potential impact of EMI/RFI and power surges and an evaluation of the ambient electromagnetic environment at NPPs to tailor those practices for use by the nuclear industry. Recommendations for EMC guidance have been derived from these research findings and are summarized in this paper

  15. Monitoring of occupational exposure at nuclear power plants

    International Nuclear Information System (INIS)

    The regulations concerning the monitoring of radiation doses of nuclear power plant workers and the reporting of radiation doses to the Finnish Centre for Radiation and Nuclear Safety (STUK) are specified in the guide. (10 refs.)

  16. Nuclear power plant reliability database management

    International Nuclear Information System (INIS)

    In the framework of the development of a probabilistic safety project on site (notion of living PSA), Saint Laurent des Eaux NPP implements a specific EDF reliability database. The main goals of this project at Saint Laurent des Eaux are: to expand risk analysis and to constitute an effective local basis of thinking about operating safety by requiring the participation of all departments of a power plant: analysis of all potential operating transients, unavailability consequences... that means to go further than a simple culture of applying operating rules; to involve nuclear power plant operators in experience feedback and its analysis, especially by following up behaviour of components and of safety functions; to allow plant safety managers to outline their decisions facing safety authorities for notwithstanding, preventive maintenance programme, operating incident evaluation. To hit these goals requires feedback data, tools, techniques and development of skills. The first step is to obtain specific reliability data on the site. Raw data come from plant maintenance management system which processes all maintenance activities and keeps in memory all the records of component failures and maintenance activities. Plant specific reliability data are estimated with a Bayesian model which combines these validated raw data with corporate generic data. This approach allow to provide reliability data for main components modelled in PSA, to check the consistency of the maintenance program (RCM), to verify hypothesis made at the design about component reliability. A number of studies, related to components reliability as well as decision making process of specific incident risk evaluation have been carried out. This paper provides also an overview of the process management set up on site from raw database to specific reliability database in compliance with established corporate objectives. (authors). 4 figs

  17. Knowledge management for the decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    This paper describes background, objectives and select conceptual components of knowledge management for the decommissioning of nuclear power plants. The concept focuses on the transfer of personal practice experience within and between nuclear power plants. The conceptual insights embrace aspects of knowledge content, structure, KM processes, organization, cooperation, culture, persuasion, leadership, technology, infrastructure, business impact and resilience. Key challenges are discussed, and related advice is provided for KM practitioners with similar endeavours in the field of nuclear power plant decommissioning. (author)

  18. Human resource management in the nuclear power plant

    OpenAIRE

    BAZGIEROVÁ, Barbora

    2016-01-01

    This Bachelor thesis investigates particularities in human resource management in the nuclear power plant. The goal of this work is to describe basic models of human resource management and their use in practise including models of human resource management that are used in the monitored nuclear power plant. This work contains options how to manage people, recruitment and education or remuneration of employees. The paper deals with human resource management in the specific nuclear power plant...

  19. Nuclear fuel procurement management at nuclear power plant

    International Nuclear Information System (INIS)

    The market situation of nuclear fuel cycles is highlighted. It also summarises the possible contract models and the elements of effective management for nuclear fuel procurement at nuclear power station based upon the nuclear fuel procurement practice of Guangdong Daya Bay Nuclear Power Station (GNPS)

  20. Development of materials for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Haenninen, H. (Aalto Univ. School of Science and Technology, Eng. Materials, Espoo (Finland))

    2010-05-15

    Concerns to material failures of nuclear power plant components have been changing during the years. Corrosion related failures of stainless steel components have been the major concern, especially pipe cracking due to weld sensitization has caused outages and repairs in BWRs. IGSCC of locally cold-worked stainless steel components without sensitization is an emerging problem in aging plants. The major issue concerning failures of stainless steel components has also been environment-assisted cracking (IGSCC and IASCC) of reactor core internal components, where handling of highly active stainless steel materials in repairs is causing also a major concern. In PWRs the long-time concern has been the steam generator tube corrosion damage both on the primary and secondary side as well as the irradiation embrittlement of the reactor pressure vessel steel and its weldments. The new big issue is the Ni-alloy weld metal cracking in reactor pressure vessel safe-end welds and in reactor head and bottom penetrations. Many of these failure modes are time-dependent and, are expected to become more prevalent when the plants are aging. (orig.)

  1. Nuclear power plant Severe Accident Research Plan

    International Nuclear Information System (INIS)

    The Severe Accident Research Plan (SARP) will provide technical information necessary to support regulatory decisions in the severe accident area for existing or planned nuclear power plants, and covers research for the time period of January 1982 through January 1986. SARP will develop generic bases to determine how safe the plants are and where and how their level of safety ought to be improved. The analysis to address these issues will be performed using improved probabilistic risk assessment methodology, as benchmarked to more exact data and analysis. There are thirteen program elements in the plan and the work is phased in two parts, with the first phase being completed in early 1984, at which time an assessment will be made whether or not any major changes will be recommended to the Commission for operating plants to handle severe accidents. Additionally at this time, all of the thirteen program elements in Chapter 5 will be reviewed and assessed in terms of how much additional work is necessary and where major impacts in probabilistic risk assessment might be achieved. Confirmatory research will be carried out in phase II to provide additional assurance on the appropriateness of phase I decisions. Most of this work will be concluded by early 1986

  2. Nuclear Plant Aging Research (NPAR) program plan

    International Nuclear Information System (INIS)

    The nuclear plant aging research described in this plan is intended to resolve issues related to the aging and service wear of equipment and systems at commercial reactor facilities and their possible impact on plant safety. Emphasis has been placed on identification and characterization of the mechansims of material and component degradation during service and evaluation of methods of inspection, surveillance, condition monitoring and maintenance as means of mitigating such effects. Specifically the goals of the program are as follows: (1) to identify and characterize aging and service wear effects which, if unchecked, could cause degradation of structures, components, and systems and thereby impair plant safety; (2) to identify methods of inspection, surveillance and monitoring, or of evaluating residual life of structures, components, and systems, which will assure timely detection of significant aging effects prior to loss of safety function; and (3) to evaluate the effectiveness of storage, maintenance, repair and replacement practices in mitigating the rate and extent of degradation caused by aging and service wear

  3. Forecast of environment influence of the Ukrainian nuclear fuel plant

    International Nuclear Information System (INIS)

    Problem of site selection for the Ukrainian nuclear fuel plant is considered. Ecological influence of the site and possible contamination levels are calculated for normal and emergency situations in plant operation

  4. Seismic evaluation of existing nuclear power plants

    International Nuclear Information System (INIS)

    The IAEA nuclear safety standards publications address the site evaluation and the design of new nuclear power plants (NPPs), including seismic hazard assessment and safe seismic design, at the level of the Safety Requirements as well as at the level of dedicated Safety Guides. It rapidly became apparent that the existing nuclear safety standards documents were not adequate for handling specific issues in the seismic evaluation of existing NPPs, and that a dedicated document was necessary. This is the purpose of this Safety Report, which is written in the spirit of the nuclear safety standards and can be regarded as guidance for the interpretation of their intent. Worldwide experience shows that an assessment of the seismic capacity of an existing operating facility can be prompted for the following: (a) Evidence of a greater seismic hazard at the site than expected before, owing to new or additional data and/or to new methods; (b) Regulatory requirements, such as periodic safety reviews, to ensure that the plant has adequate margins for seismic loads; (c) Lack of anti-seismic design or poor anti-seismic design; (d) New technical finding such as vulnerability of some structures (masonry walls) or equipment (relays), other feedback and new experience from real earthquakes. Post-construction evaluation programmes evaluate the current capability of the plant to withstand the seismic concern and identify any necessary upgrades or changes in operating procedures. Seismic qualification is distinguished from seismic evaluation primarily in that seismic qualification is intended to be performed at the design stage of a plant, whereas seismic evaluation is intended to be applied after a plant has been constructed. Although some guidelines do exist for the evaluation of existing NPPs, these are not established at the level of a regulatory guide or its equivalent. Nevertheless, a number of existing NPPs throughout the world have been and are being subjected to review of their

  5. Detecting Cyber Attacks On Nuclear Power Plants

    Science.gov (United States)

    Rrushi, Julian; Campbell, Roy

    This paper proposes an unconventional anomaly detection approach that provides digital instrumentation and control (I&C) systems in a nuclear power plant (NPP) with the capability to probabilistically discern between legitimate protocol frames and attack frames. The stochastic activity network (SAN) formalism is used to model the fusion of protocol activity in each digital I&C system and the operation of physical components of an NPP. SAN models are employed to analyze links between protocol frames as streams of bytes, their semantics in terms of NPP operations, control data as stored in the memory of I&C systems, the operations of I&C systems on NPP components, and NPP processes. Reward rates and impulse rewards are defined in the SAN models based on the activity-marking reward structure to estimate NPP operation profiles. These profiles are then used to probabilistically estimate the legitimacy of the semantics and payloads of protocol frames received by I&C systems.

  6. Materials qualification for nuclear power plants

    International Nuclear Information System (INIS)

    The supply of materials to be used in the fabrication of components submitted to pressure destined to Atucha II nuclear power plant must fulfill the quality assurance requirements in accordance with the international standards. With the aim of promoting the national participation in CNA II, ENACE had the need to adapt these requirements to the national industry conditions and to the availability of official entities' qualification and inspection. As a uniform and normalized assessment for the qualification of materials did not exist in the country, ENACE had to develop a materials suppliers qualification system. This paper presents a suppliers qualification procedure, its application limits and the alternative procedures for the acceptance of individual stock and for the stock materials purchase. (Author)

  7. Severe accidents in Nuclear Power Plants

    International Nuclear Information System (INIS)

    For the assessment of the safety of nuclear power plants it is of great importance the analyses of severe accidents since they allow to estimate the possible failure models of the containment, and also permit knowing the magnitude and composition of the radioactive material that would be released to the environment in case of an accident upon population and the environment. This paper presents in general terms the basic principles for conducting the analysis of severe accidents, the fundamental sources in the generation of radionuclides and aerosols, the transportation and deposition processes, and also makes reference to de main codes used in the modulation of severe accidents. The final part of the paper contents information on how severe accidents are dialed with the regulatory point view in different countries

  8. Corrosion protection system for nuclear power plant

    International Nuclear Information System (INIS)

    A cathodic corrosion protection system for a nuclear power plant which employs an ion tank adjacent the main fresh water feed pipe leading to the steam generator to treat water from the main feed pipe and then return the treated water to the main feed pipe to form a corrosion protecting alkaline layer on surfaces of the main feed pipe and the secondary side of the steam generator. The ion tank receives measured amounts of hydrazine to render the water therein substantially conductive and contains ionizable metal anodes which release free metal ions as electric current flows between the anodes and a cathode connection on an ion tank outlet pipe near the main feed water pipe

  9. Advanced nuclear power plant solidification system

    Energy Technology Data Exchange (ETDEWEB)

    Kikuchi, M. [Hitachi Ltd., Tokyo (Japan); Hirayama, S.; Nishi, T. [Hitachi Ltd., Ibaraki (Japan); Huang, C. T. [Institute of Nuclear Energy Research, Lungtan (Taiwan)

    2003-07-01

    'Slim-Rad' is an advanced radioactive waste treatment system reflecting Hitachi's long experience as a supplier of nuclear plants. The system utilizes new technologies such as a hollow fiber filter, high-performance cement solidification and laundry and shower drain treatment. By adopting this Slim-Rad system, not only the final waste volume but also the number of radwaste tanks can be reduced 1/8 and 1/2, respectively, compared with previous Hitachi radwaste treatment systems. Moreover, release of radioactivity into the environment from the treated waste is reduced effectively. This paper outlines the system and describes its features, as well as the features of the key technology such as volume reduction and solidification technology.

  10. The role of nuclear power plant designers

    International Nuclear Information System (INIS)

    When design of a nuclear power plant begins its designers, owners, and regulators make a safety judgement based on their knowledge and collective experience. As time goes on safety criteria change, methods improve, new scientific understanding is gained, and the cost of safety increases in relation to the benefits gained. In spite of that, the fundamental safety of CANDU remains and will continue high. However, the designer's job has become more difficult. The process of designing a product to satisfy a customer using a perceived view of that benefits society is no longer simple. Is the customer the utility or an amalgam of government departments and various factions of the public? How is the designer to make judgements on social acceptability when society speaks with so many voices and so little leadership

  11. Emotional consequences of nuclear power plant disasters.

    Science.gov (United States)

    Bromet, Evelyn J

    2014-02-01

    The emotional consequences of nuclear power plant disasters include depression, anxiety, post-traumatic stress disorder, and medically unexplained somatic symptoms. These effects are often long term and associated with fears about developing cancer. Research on disasters involving radiation, particularly evidence from Chernobyl, indicates that mothers of young children and cleanup workers are the highest risk groups. The emotional consequences occur independently of the actual exposure received. In contrast, studies of children raised in the shadows of the Three Mile Island (TMI) and Chernobyl accidents suggest that although their self-rated health is less satisfactory than that of their peers, their emotional, academic, and psychosocial development is comparable. The importance of the psychological impact is underscored by its chronicity and by several studies showing that poor mental health is associated with physical health conditions, early mortality, disability, and overuse of medical services. Given the established increase in mental health problems following TMI and Chernobyl, it is likely that the same pattern will occur in residents and evacuees affected by the Fukushima meltdowns. Preliminary data from Fukushima indeed suggest that workers and mothers of young children are at risk of depression, anxiety, psychosomatic, and post-traumatic symptoms both as a direct result of their fears about radiation exposure and an indirect result of societal stigma. Thus, it is important that non-mental health providers learn to recognize and manage psychological symptoms and that medical programs be designed to reduce stigma and alleviate psychological suffering by integrating psychiatric and medical treatment within the walls of their clinics.Introduction of Emotional Consequences of Nuclear Power Plant Disasters (Video 2:15, http://links.lww.com/HP/A34).

  12. Impact the nuclear power plant on electrical grid

    International Nuclear Information System (INIS)

    Due to the limited fossil fuel energy resources and the almost fully utilized hydro energy, Egypt has been considering for sometime the various options for satisfying the increasing demand for electricity, including nuclear energy. This thesis emphasizes decisions concerning the impact of nuclear power plant on Egyptian Electrical Grid.This work presents the dynamic modeling and simulation of load flow and transient stability analysis to evaluate the Egyptian Electrical grid. The complex power system is modeled and simulated using Power System Simulator for Engineer (PSS/E). The building blocks of the dynamic model of a power system are presented. A detail of modeling for Egyptian Electrical power network is discussed. It presents an introduction of the load forecasting, and proposal on Egyptian Electrical grid in year 2018. This work presents definitions of nuclear power plant (NPP) and the most widespread power plant reactor types. A detailed representation, analysis, mathematical model, simulation of nuclear power plant and simulation results is also given.This thesis explains the characteristics of the electric grid, its relationship with the NPP, the interaction of electrical grid and nuclear power plant, and the reasons why a reliable grid is so important to the NPP.This thesis proposes a new design of power plant reactor controller for the nuclear power plant. A detailed representation, analysis, mathematical model, simulation of nuclear power plant control and simulation for different disturbance of nuclear power plant on the Egyptian Electrical Grid results is also presented.

  13. Instrumentation control system in nuclear power plant

    International Nuclear Information System (INIS)

    Purpose: To improve the reliability of instrumentation control system in a nuclear power plant by using an optical fiber cable as a transmission path between a multiplexer and a central control room to thereby eliminate noises resulted from electromagnetic inductions or the likes. Constitution: Signals from neutron detectors are sent by way of ceramic-insulated cables to pre-amplifiers disposed outside of the pressure vessel of a nuclear reactor, converted into voltage pulse signals and then sent by way of coaxial cables to a multiplexer. The multiplexer receives a plurality of voltage pulse signals corresponding to the neutron detectors respectively, converts them into a time-shared electric signal train and sends it to an optical pulse transmitter. The transmitter converts the supplied signals into an optical pulse signal train corresponding to the electric signal train from the multiplexer and sends it by way of an optical fiber cable to an optical pulse receiver disposed in a central control room. (Kawakami, Y.)

  14. Total generating costs: coal and nuclear plants

    International Nuclear Information System (INIS)

    The study was confined to single and multi-unit coal- and nuclear-fueled electric-generating stations. The stations are composed of 1200-MWe PWRs; 1200-MWe BWRs; 800-and 1200-MWe High-Sulfur Coal units, and 800- and 1200-MWe Low-Sulfur Coal units. The total generating cost estimates were developed for commercial operation dates of 1985 and 1990; for 5 and 8% escalation rates, for 10 and 12% discount rates; and, for capacity factors of 50, 60, 70, and 80%. The report describes the methodology for obtaining annualized capital costs, levelized coal and nuclear fuel costs, levelized operation and maintenance costs, and the resulting total generating costs for each type of station. The costs are applicable to a hypothetical Middletwon site in the Northeastern United States. Plant descriptions with general design parameters are included. The report also reprints for convenience, summaries of capital cost by account type developed in the previous commercial electric-power cost studies. Appropriate references are given for additional detailed information. Sufficient detail is given to allow the reader to develop total generating costs for other cases or conditions

  15. Total quality drives nuclear plant improvements

    International Nuclear Information System (INIS)

    Total quality (TQ) at Carolina Power and Light (CP and L) is fulfilling a 1985 vision of Sherwood H. Smith, Jr., CP and L's chairman, president, and chief executive officer. The TQ concept has provided a way for employees to align their creative energies toward meeting the business needs of the company. Throughout CP and L, TQ has been recognized as the vehicle for reducing operating costs and improving customer satisfaction. Within the nuclear organization, application of the TQ process has helped to improve communications, resolve challenges, and provide more consistent work practices among CP and L's three nuclear plants. Total quality was introduced from the top down, with initial benefits coming from team interactions. Senior management at CP and L defined the corporate expectations and outlined the training requirements for implementing TQ. Management staffs at each organizational level became steering committees for TQ team activities within their departments. Teams of employees most knowledgeable about a given work area were empowered to solve problems or overcome obstacles related to that work area. Employees learned to become better team players and to appreciate the quality of decisions reached through group consensus. Now, formalized methods that started TQ are becoming part of the day-to-day work ethic

  16. Quality management of nuclear power plants

    International Nuclear Information System (INIS)

    The paper discusses the various approaches to quality management and the progressive development from traditional quality assurance (QA) concepts through integrated and performance based quality management systems to total quality management. Experience has shown that in many cases the traditional implementation of QA in nuclear power plant life-cycle activities has resulted in limited benefits. The paper outlines the advantages of developing an integrated quality management system, which, besides satisfying the QA standards, focuses on the performance of an organization. This reflects the approach implicit in the proposed revisions of the IAEA QA standards (code and guides). Such a quality management system provides the framework within which processes are controlled to meet the business objectives and is capable of accommodating easily new requirements, such as environmental management. An integrated quality management system should not be focused specifically on regulatory (and hence nuclear safety) issues, but should constitute the whole management system of the organization, of which safety and the environment are of course important elements. The paper gives a practical example of this approach implemented company wide. This approach is similar to other approaches in place or being developed by many Foratom members. The paper also lists the components of total quality management, which is considered to constitute the future direction for the nuclear power industry. The quality management system is the primary vehicle to meet the fundamental objectives, but total quality can only be realized by developing the full potential of people through team work in order to continuously improve the system and the performance of the organization by focusing on internal as well as external customers. (author). 6 refs, 3 figs, 2 tab

  17. Government support for the export of nuclear power plants after Fukushima Daiichi nuclear power accident

    International Nuclear Information System (INIS)

    Depending on the surge of a global evaluation for the nuclear power generation, our country strengthened government support for the export of nuclear power plants. However, under the influence of a Fukushima Daiichi Nuclear Power Plant accident, the internal and external situation surrounding nuclear power has been changing. Should our country continue government support for the nuclear power plant export according to this? This report outlined the world trend around nuclear power before the Fukushima accident, surveyed merits and problems of the nuclear power plant export, and introduced what kind of export aid package the government took. And then, it showed the situation change after the Fukushima accident and the point at issue on thinking about the way of the government support. The Fukushima accident raised concern for the safety of the nuclear power plant and might have a big influence on the construction trend of the world nuclear power plant in the future. The criticism to conventional government support for the nuclear power plant export has risen, too. However, the role of government support for the nuclear power plant export was not the problem that should be discussed only by the side of safety and the economy. The nuclear power plant export carried an international contribution, reinforcement of the thickness of a technique and the talented person of the nuclear power industry, and a role such as the contribution to economic growth in medium-and-long term energy policy and nuclear energy policy until now. It may be said that we were asked how was placed nuclear power plant export again while these policies were reviewed after the Fukushima accident. (T. Tanaka)

  18. Nuclear Power Plant Fire Protection Research Program

    International Nuclear Information System (INIS)

    The goal is to develop test data and analytical capabilities to support the evaluation of: (1) the contribution of fires to the risk from nuclear power plants; (2) the effects of fires on control room equipment and operations; and (3) the effects of actuation of fire suppression systems on safety equipment. A range of fire sources will be characterized with respect to their energy and mass evolution, including smoke, corrosion products, and electrically conductive products of combustion. An analytical method for determining the environment resulting from fire will be developed. This method will account for the source characteristics, the suppression action following detection of the fire, and certain parameters specific to the plant enclosure in which the fire originates, such as the geometry of the enclosure and the ventilation rate. The developing local environment in the vicinity of safety-related equipment will be expressed in terms of temperatures, temperature rise rates, heat fluxes, and moisture and certain species content. The response of certain safe shutdown equipment and components to the environmental conditions will be studied. The objective will be to determine the limits of environmental conditions that a component may be exposed to without impairment of its ability to function

  19. Human factors in nuclear power plants

    International Nuclear Information System (INIS)

    This report describes the results of a study on the functions of operating and maintenance personnel in nuclear power plants. Since an effective power plant design must take into systematic account the possibilities and limitations of the human element, the basic aim of the study was to identify what the human operators are required to do and how they achieve it. Information was acquired by direct observation and by interviews as well as by evaluation of written documents (e.g. incident reports, procedures manuals, work regulations) and of working conditions (e.g. equipment and workplace design). A literature search and evaluation carried out within the scope of this study has been published as a separate document. The main part of the report is devoted to discussions and conclusions on selected areas of potential improvements. The topics include control room design, factors of the physical environment including radiation, problems of maintainability, design of written documents, problems in communicating information, design and control of tasks, placement and training. A separate section deals with problems of recording human errors. (orig.)

  20. Comprehensive signal validation for nuclear power plants

    International Nuclear Information System (INIS)

    Signal validation is the detection, isolation and characterization of faulty signals. A signal validation technique utilizing a process hypercube comparison (PHC) was originated during the research and other methods were extended. The hypercube is merely a multi-dimensional joint histogram of the process conditions. The hypercube is created off-line during a learning phase. In the event that a newly observed plant state does not match with those in the learned hypercube, the PHC algorithm performs signal validation by progressively hypothesizing that one or more signals is in error. This assumption is then either substantiated or denied. In the case where many signals are found to be in error, a conclusion that the process conditions are abnormal is reached. A comprehensive signal validation software system has been developed for application to nuclear power plants. This system combines some previously established fault detection methodologies as well as some newly developed ones. The techniques have been implemented in a modular architecture which allows the addition or removal of signal validation modules as deemed necessary. Intra-module confidence factors describing the validity of a given signal are derived using fuzzy membership functions. A final evaluation of signal status is made by the System Executive (SE) based on results from each signal validation module. In order to make reliable decisions in this parallel system a positive decision maker (PDM) was developed

  1. Next Generation Nuclear Plant GAP Analysis Report

    Energy Technology Data Exchange (ETDEWEB)

    Ball, Sydney J [ORNL; Burchell, Timothy D [ORNL; Corwin, William R [ORNL; Fisher, Stephen Eugene [ORNL; Forsberg, Charles W. [Massachusetts Institute of Technology (MIT); Morris, Robert Noel [ORNL; Moses, David Lewis [ORNL

    2008-12-01

    As a follow-up to the phenomena identification and ranking table (PIRT) studies conducted recently by NRC on next generation nuclear plant (NGNP) safety, a study was conducted to identify the significant 'gaps' between what is needed and what is already available to adequately assess NGNP safety characteristics. The PIRT studies focused on identifying important phenomena affecting NGNP plant behavior, while the gap study gives more attention to off-normal behavior, uncertainties, and event probabilities under both normal operation and postulated accident conditions. Hence, this process also involved incorporating more detailed evaluations of accident sequences and risk assessments. This study considers thermal-fluid and neutronic behavior under both normal and postulated accident conditions, fission product transport (FPT), high-temperature metals, and graphite behavior and their effects on safety. In addition, safety issues related to coupling process heat (hydrogen production) systems to the reactor are addressed, given the limited design information currently available. Recommendations for further study, including analytical methods development and experimental needs, are presented as appropriate in each of these areas.

  2. Alpha nuclides in nuclear power plants

    International Nuclear Information System (INIS)

    In a joint research project of VGB and AREVA NP GmbH the behavior of alpha nuclides in nuclear power plants has been investigated since 2005. The main source of alpha nuclides is core contamination with fissile material (so called tramp uranium or tramp fuel) which deposits on fuel rod surfaces and leads to the build-up of transuranium nuclides. Such alpha-nuclides are of special interest for health physics due to their high biological effectiveness. Having very high dose factors they lead to high dose weighting in case of incorporation. At NPC 2008 first results of the joint research project were presented concerning tramp fuel and its impact to alpha nuclides. The present publication will cover the ongoing results of this research project. A special focus is taken to deduce recommendations which allow plant operation personal to recognize situations in advance which can lead to enhanced appearance of alpha nuclides. Depending on the fuel conditions in the core and the activity level of fission products of the reactor coolant a better prediction of the alpha situation at the following outage and maintenance can be deduced. (author)

  3. Training diagnostic skills for nuclear power plants

    International Nuclear Information System (INIS)

    Operators of large-scale industrial process plants such as nuclear power stations and chemical plants are faced with a critical and complex task when confronted with disturbances in normal operation caused by technical failures or mainte- nances errors. Great care must be taken to prepare and support the operators during such situations. Procedural systems are provided, trained on full-scale highfidelity simulators is often a prerequisite and decision-support systems are starting to be incorporated, especially in modern control rooms. During recent years, it has become increasingly clear from ''real-life'' studies in complex production and transport industries that professional highly skilled troubleshooters can develop effective general purpose search strategies for locating and dealing with faults and, most importantly, with new and not previously experienced faults. This research has indicated that means for training of these general diagnostic abilities can be developed. In addition, other work has dealt with the problem of observing and analyzing operator behaviour in coping with disturbances. The NKA/LIT-4 project has continued these efforts in studying methods for training diagnostic skills as well as for observing and testing operator behaviour on training simulators. (author)

  4. Bar-HRM for Authentication of Plant-Based Medicines: Evaluation of Three Medicinal Products Derived from Acanthaceae Species.

    Directory of Open Access Journals (Sweden)

    Maslin Osathanunkul

    Full Text Available Medicinal plants are used as a popular alternative to synthetic drugs, both in developed and developing countries. The economic importance of the herbal and natural supplement industry is increasing every year. As the herbal industry grows, consumer safety is one issue that cannot be overlooked. Herbal products in Thai local markets are commonly sold without packaging or labels. Plant powders are stored in large bags or boxes, and therefore buying local herbal products poses a high risk of acquiring counterfeited, substituted and/or adulterated products. Due to these issues, a reliable method to authenticate products is needed. Here DNA barcoding was used in combination with High Resolution Melting analysis (Bar-HRM to authenticate three medicinal Acanthaceae species (Acanthus ebracteatus, Andrographis paniculata and Rhinacanthus nasutus commonly used in Thailand. The rbcL barcode was selected for use in primers design for HRM analysis to produce standard melting profiles of the selected species. Melting data from the HRM assay using the designed rbcL primers showed that the three chosen species could be distinguished from each other. HRM curves of all fifteen test samples indicated that three of tested products did not contain the indicated species. Two closely related species (A. paniculata and R. nasutus, which have a high level of morphological similarity, were interchanged with one another in three tested products. Incorrect information on packaging and labels of the tested herbal products was the cause of the results shown here. Morphological similarity among the species of interest also hindered the collection process. The Bar-HRM method developed here proved useful in aiding in the identification and authentication of herbal species in processed samples. In the future, species authentication through Bar-HRM could be used to promote consumer trust, as well as raising the quality of herbal products.

  5. Upgrading the safety, reliability and economy of nuclear power plants

    International Nuclear Information System (INIS)

    The main task of the Nuclear Power Plant Research Institute (VUJE) in Trnava (CS) is systems research of nuclear power plant operation as a whole, with the objective of increasing the efficiency and reliability of nuclear power plants while maintaining the principles of nuclear safety. An extensive system was developed of computer programs for the analysis of operating and accident conditions of WWER reactor nuclear power plants serving the operating modes and rationalization of operation of nuclear power plants. The programs are used for safety documentation purposes, operating events evaluation, operating regulation improvement, and nuclear power unit modification evaluation. They are briefly described. Instrumentation developed by the Institute is also characterized; it allows systematic monitoring of the operating parameters and the technical and economic indices of nuclear power plant units. Attention is also paid to the evaluation of the environmental impact of nuclear power plants. A set of method was developed in this field for the collection, processing and measurement of environmental samples, and a number of instruments have been developed for monitoring the production and migration of radionuclides in the environment. (Z.M.). 2 figs

  6. Projected role of nuclear power in Egypt and problems encountered in implementing the first nuclear plant

    International Nuclear Information System (INIS)

    This paper reviews the present and projected power demands in Egypt and the factors behind the decision to introduce a nuclear power generation program. Different problems encountered and anticipated in introducing the first nuclear power plant are also discussed

  7. Implementation of the Embalse nuclear power plant's commissioning

    International Nuclear Information System (INIS)

    This work points out the main experiences gathered during the Embalse nuclear power plant start-up, which after the first years of operation arise as quite convenient to be taken into account for future nuclear power plants' start-up. (Author)

  8. Valuation of Embalse Nuclear Power Plant and of heavy water

    International Nuclear Information System (INIS)

    The author describes the Nuclear Power Plant characteristics, the building work, the heavy water valuation criteria and the reasons why he considers that any capital good can be valuated by means of cash-flow. The value of replacement of Embalse Nuclear Power Plant is of U$S 1.593.538.000 (authors)

  9. Embalse nuclear power plant and heavy water valuation

    International Nuclear Information System (INIS)

    The author describes the nuclear power plant characteristics, the building work, the heavy water valuation criteria and the reasons why he considers that any capital good can be valued by the cash-flow method. The Embalse nuclear power plant replacement value is of U$S 1.593.538.000. (author)

  10. Safety goals for nuclear power plants: a discussion paper

    International Nuclear Information System (INIS)

    This report includes a proposed policy statement on safety goals for nuclear power plants published by the Commission for public comment and a supporting discussion paper. Proposed qualitative goals and associated numerical guidelines for nuclear power-plant accident risks are presented. The significance of the goals and guidelines, their bases and rationale, and their proposed mode of implementation are discussed

  11. Wild fire evaluation for Fukushima Daiichi Nuclear Power Plant

    International Nuclear Information System (INIS)

    The evaluation of wild fire effect to Fukushima Daiichi Nuclear Power Plant is described. The analysis of input data on Fukushima Daiichi Nuclear Power Plant builds using FARSITE has given time of arrival, fireline intensity, flame length, and rate of spread etc. (M.H.)

  12. Research on psychological evaluation method for nuclear power plant operators

    International Nuclear Information System (INIS)

    The qualitative and quantitative psychology evaluation methods to the nuclear power plant operators were analyzed and discussed in the paper. The comparison analysis to the scope and result of application was carried out between method of outline figure fitted and method of fuzzy synthetic evaluation. The research results can be referenced to the evaluation of nuclear power plant operators. (authors)

  13. Preliminary regulatory assessment of nuclear power plants vulnerabilities

    International Nuclear Information System (INIS)

    Preliminary attempts to develop models for nuclear regulatory vulnerability assessment of nuclear power plants are presented. Development of the philosophy and computer tools could be new and important insight for management of nuclear operators and nuclear regulatory bodies who face difficult questions about how to assess the vulnerability of nuclear power plants and other nuclear facilities to external and internal threats. In the situation where different and hidden threat sources are dispersed throughout the world, the assessment of security and safe operation of nuclear power plants is very important. Capability to evaluate plant vulnerability to different kinds of threats, like human and natural occurrences and terrorist attacks and preparation of emergency response plans and estimation of costs are of vital importance for assurance of national security. On the basis of such vital insights, nuclear operators and nuclear regulatory bodies could plan and optimise changes in oversight procedures, organisations, equipment, hardware and software to reduce risks taking into account security and safety of nuclear power plants operation, budget, manpower, and other limitations. Initial qualitative estimations of adapted assessments for nuclear applications are shortly presented. (author)

  14. Code on the safety of nuclear power plants: Design

    International Nuclear Information System (INIS)

    This Code is a compilation of nuclear safety principles aimed at defining the essential requirements necessary to ensure nuclear safety. These requirements are applicable to structures, systems and components, and procedures important to safety in nuclear power plants embodying thermal neutron reactors, with emphasis on what safety requirements shall be met rather than on specifying how these requirements can be met. It forms part of the Agency's programme for establishing Codes and Safety Guides relating to land based stationary thermal neutron power plants. The document should be used by organizations designing, manufacturing, constructing and operating nuclear power plants as well as by regulatory bodies

  15. Geology and geotechnic in the implantation of nuclear power plants

    International Nuclear Information System (INIS)

    It is presented a general methodology for geological and geotechnical investigations to be performed in sites selected for the construction of nucldar power plants. Items dealing with the standards applied to licensing of a nuclear power plants, the selection process of sites and identification of geological and geotechnical parameters needed for the regional and local characterization of the area being studied, were incorporated. It is also provided an aid to the writing of technical reports, which are part of the documentation an owner of a nuclear power plant needs to submit to the Comissao Nacional de Energia Nuclear, to fulfill the nuclear installation licensing requirements. (Author)

  16. Nuclear power plant after Fukushima incident: Lessons from Japan to Thailand for choosing power plant options

    OpenAIRE

    Tatcha Sudtasan; Komsan Suriya

    2012-01-01

    This study evaluates four power plant options in Thailand to suggest whether the country should adopt nuclear power plants. It includes a scenario that nuclear power plants are forced to be shut because of natural disaster like what happened at Fukushima Daiishi nuclear power plant in Japan. The results found that, in terms of net present value both in duration of 30 and 50 years, nuclear power plants is the best choice under certainty of no severe natural disaster that would interrupt the op...

  17. Safety review, assessment and inspection for nuclear power plants

    International Nuclear Information System (INIS)

    Qinshan Nuclear Power Plant started first shut down for refuelling and overhaul in October, 1994. The two units of Guangdong Nuclear Power Station also started first shutdown for refuelling and overhaul in December 1994 and in April, 1995 respectively. Hence besides to conduct a routine operational inspection, the NNSA laid stress on the safety supervision of the first refuelling for two nuclear power plants, especially the treatment of event that the drop time of its control rods exceed criteria for the Unit 1 of GNPS. In the course of implementing supervision on the refuelling for nuclear power plants, the NNSA drew experience from foreign nuclear safety authorities to the practice of supervision during the commissioning stage for nuclear power plants, the inspection programs were prepared for outage respectively. The NNSA concerted closely with its regional offices to conduct a routine inspection and to combine with a special item inspection, to ensure the effective implementation of inspections

  18. Geological and geotechnical investigations for nuclear power plants sites

    International Nuclear Information System (INIS)

    This dissertation presents a general methodology for the tasks of geological and geotechnical investigations, to be performed in the proposed sites for construction of nuclear Power Plants. In this work, items dealing with the standards applied to licensing of Nuclear Power Plants, with the selection process of sites and identification of geological and geotechnical parameters needed for the regional and local characterization of the area being studied, were incorporated. This dissertation also provides an aid to the writing of Technical Reports, which are part of the documentation an owner of a Nuclear Power Plant needs to submit to the Comissao Nacional de Energia Nuclear, to fulfill the nuclear installation licensing requirements. Moreover, this work can contribute to the planning of field and laboratory studies, needed to determine the parameters of the area under investigation, for the siting of Nuclear Power Plants. (Author)

  19. Financial and ratepayer impacts of nuclear power plant regulatory reform

    International Nuclear Information System (INIS)

    Three reports - ''The Future Market for Electric Generating Capacity,'' ''Quantitative Analysis of Nuclear Power Plant Licensing Reform,'' and ''Nuclear Rate Increase Study'' are recent studies performed by the Los Alamos National Laboratory that deal with nuclear power. This presents a short summary of these three studies. More detail is given in the reports

  20. The practical zoning at the Blayais nuclear power plant

    International Nuclear Information System (INIS)

    The nuclear facilities have the obligation to create a zoning of their installation. The different parts must allow to identify the waste in nuclear waste or conventional waste. The nuclear power plant of the Blayais is taken as example. (N.C.)

  1. Emergency response and nuclear risk governance. Nuclear safety at nuclear power plant accidents

    International Nuclear Information System (INIS)

    The present study entitled ''Emergency Response and Nuclear Risk Governance: nuclear safety at nuclear power plant accidents'' deals with issues of the protection of the population and the environment against hazardous radiation (the hazards of nuclear energy) and the harmful effects of radioactivity during nuclear power plant accidents. The aim of this study is to contribute to both the identification and remediation of shortcomings and deficits in the management of severe nuclear accidents like those that occurred at Chernobyl in 1986 and at Fukushima in 2011 as well as to the improvement and harmonization of plans and measures taken on an international level in nuclear emergency management. This thesis is divided into a theoretical part and an empirical part. The theoretical part focuses on embedding the subject in a specifically global governance concept, which includes, as far as Nuclear Risk Governance is concerned, the global governance of nuclear risks. Due to their characteristic features the following governance concepts can be assigned to these risks: Nuclear Safety Governance is related to safety, Nuclear Security Governance to security and NonProliferation Governance to safeguards. The subject of investigation of the present study is as a special case of the Nuclear Safety Governance, the Nuclear Emergency governance, which refers to off-site emergency response. The global impact of nuclear accidents and the concepts of security, safety culture and residual risk are contemplated in this context. The findings (accident sequences, their consequences and implications) from the analyses of two reactor accidents prior to Fukushima (Three Mile Iceland in 1979, Chernobyl in 1986) are examined from a historical analytical perspective and the state of the Nuclear Emergency governance and international cooperation aimed at improving nuclear safety after Chernobyl is portrayed by discussing, among other topics, examples of &apos

  2. ISI NDE Total Support System for Korean Nuclear Power Plants

    International Nuclear Information System (INIS)

    Structural integrity of nuclear components is important for a safe operation of nuclear power plants. Therefore, nuclear power plants require to perform reliable, periodic inservice inspections. Korea Electric Power Company(KEPCO) operates the entire Korean nuclear power plants. Since nuclear power plant safety and the associated inservice inspection(ISI) are under the plant owner's responsibility, Korea Electric Power Research Institute(KEPRI), the R and D division of KEPCO, has established the ISI NDE Total Support system(TSS) for an efficient performance of ISI tasks, and initiated both key ISI NDE technology development program and training and qualification system development program for an independent ISI operation. This paper describes details of these programs

  3. Safety aspects of nuclear power plant automation and robotics

    International Nuclear Information System (INIS)

    The question being considered in this report is the extent to which the following aims are promoted through the use of robotics and automatic plant systems: nuclear power is safe (nuclear power plants and related facilities will not be constructed or allowed to continue operating if they are not perceived as being safe); nuclear power is economic (in comparison to other forms of electricity production once the environmental costs have been fully considered and as part of a unified energy policy); nuclear power is conservative (using nuclear fuel does not waste natural resources, damage the atmosphere, or produce unmanageable waste). Refs, figs, tabs

  4. Applications of power from Temelin nuclear power plant

    International Nuclear Information System (INIS)

    The proceedings contain 10 papers of which 9 fall under the INIS scope. They all concern the intentions and possibilities of using heat from nuclear power plants, especially from the Temelin power plant. Waste heat will be used for district heating of adjacent conurbations and for agricultural purposes. Various projects are presented using heat from nuclear power plants, such as greenhouse heating, soil heating, cultivation of algae and fish in warmed-up water. The existing experience is described with the use of heat from the Bohunice nuclear power plant. (M.D.). 15 figs., 6 tabs., 17 refs

  5. Operational experience, availability and reliability of nuclear power plants

    International Nuclear Information System (INIS)

    This lecture presents a survey on nuclear power production and plant performance in the Western World covering all reactor types and light-water reactors in particular and discusses key parameters such as load factors and non-availability analysis, outlines the main reasons for the reliable performance of Swiss nuclear power plants and explains the management function as applied at the Beznau Nuclear Power Station to ensure high power productivity and reliability. (orig./RW)

  6. Nuclear Power Plant Maintenance Optimization with Heuristic Algorithm

    OpenAIRE

    Andrija Volkanovski; Leon Cizelj

    2014-01-01

    The test and maintenance activities are conducted in the nuclear power plants in order to prevent or limit failures resulting from the ageing or deterioration. The components and systems are partially or fully unavailable during the maintenance activities. This is especially important for the safety systems and corresponding equipment because they are important contributors to the overall nuclear power plant safety. A novel method for optimization of the maintenance activities in the nuclear ...

  7. Development of the nuclear plant analyzer for Korean standard Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Shin Hwan; Kim, Hyeong Heon; Song, In Ho; Hong, Eon Yeong; Oh, Yeong Taek [Korea Power Engineering Company Inc., Yongin (Korea, Republic of)

    2000-12-15

    The purpose of this study is to develop an NPA for the Ulchin Nuclear Power Plant Unit 3 and 4, the first KSNP type plant. In this study, the process model simulating the overall plant systems, GUI and simulation executive which provide the functions of an engineering simulator were developed, and the NPA was completed by integrating them. The contents and the scope of this study are as follows : main feedwater system, auxiliary feedwater system, Chemical and Volume Control System(CVCS), Safety Injection System(SIS), Shutdown Cooling System(SCS), electric power supply system, Core Protection Calculator(CPC), various plant control system, development of the graphics screens for each system, real-time simulation, simulation control for the enhancement of functional capabilities, user friendly GUI, collection of the design and operating data, establishment of the NPA database, integration of the GUI and simulation control program with process model, collection of the data for the verification and validation of the developed NPA, collection of the plant test data, collection and review of the results of other computer codes, verification of the simulation accuracy by comparing the NPA results with the actual plant data, validation of the simulation capability of the NPA, comparison against available data from other analysis suing different computer codes.

  8. 75 FR 61779 - R.E. Ginna Nuclear Power Plant, LLC; R.E. Ginna Nuclear Power Plant Environmental Assessment and...

    Science.gov (United States)

    2010-10-06

    ... COMMISSION R.E. Ginna Nuclear Power Plant, LLC; R.E. Ginna Nuclear Power Plant Environmental Assessment and... Operating License No. DPR-18, issued to R.E. Ginna Nuclear Power Plant, LLC (the licensee), for operation of the R.E. Ginna Nuclear Power Plant (Ginna), located in Ontario, New York. In accordance with 10 CFR...

  9. Preparedness of public authorities for emergencies at nuclear power plants

    International Nuclear Information System (INIS)

    The safety guide lays down the requirements for the establishment of suitable procedures to be followed in the event of an emergency situation at a nuclear power plant. Many of the procedures would also be applicable at other nuclear facilities such as fuel manufacturing plants, irradiated fuel processing plants and the like. The guide defines reponsibilities for emergency planning, organization and action, protective measures to be taken, information and instruction of the public, training and cooperation across boundaries

  10. Environmental impacts of fossil-fuel and nuclear power plants

    International Nuclear Information System (INIS)

    Large power plants burning fossil fuels generate emissions with a high content of sulphur dioxide and a content of noxious aerosols and radioisotopes whose radioactivity exceeds the limits set for nuclear power plants. The main problem of nuclear power plants is to secure radiation safety namely in case of an accident even though the probability of such an event is very small. The most complicated problems are related to the treatment of spent fuel, its transport, processing and storage. (B.H.)

  11. Methods for tornado frequency calculation of nuclear power plant

    International Nuclear Information System (INIS)

    In order to take probabilistic safety assessment of nuclear power plant tornado attack event, a method to calculate tornado frequency of nuclear power plant is introduced based on HAD 101/10 and NUREG/CR-4839 references. This method can consider history tornado frequency of the plant area, construction dimension, intensity various along with tornado path and area distribution and so on and calculate the frequency of different scale tornado. (authors)

  12. Fukushima nuclear power plant accident was preventable

    Science.gov (United States)

    Kanoglu, Utku; Synolakis, Costas

    2015-04-01

    On 11 March 2011, the fourth largest earthquake in recorded history triggered a large tsunami, which will probably be remembered from the dramatic live pictures in a country, which is possibly the most tsunami-prepared in the world. The earthquake and tsunami caused a major nuclear power plant (NPP) accident at the Fukushima Dai-ichi, owned by Tokyo Electric Power Company (TEPCO). The accident was likely more severe than the 1979 Three Mile Island and less severe than the Chernobyl 1986 accidents. Yet, after the 26 December 2004 Indian Ocean tsunami had hit the Madras Atomic Power Station there had been renewed interest in the resilience of NPPs to tsunamis. The 11 March 2011 tsunami hit the Onagawa, Fukushima Dai-ichi, Fukushima Dai-ni, and Tokai Dai-ni NPPs, all located approximately in a 230km stretch along the east coast of Honshu. The Onagawa NPP was the closest to the source and was hit by an approximately height of 13m tsunami, of the same height as the one that hit the Fukushima Dai-ichi. Even though the Onagawa site also subsided by 1m, the tsunami did not reach to the main critical facilities. As the International Atomic Energy Agency put it, the Onagawa NPP survived the event "remarkably undamaged." At Fukushima Dai-ichi, the three reactors in operation were shut down due to strong ground shaking. The earthquake damaged all offsite electric transmission facilities. Emergency diesel generators (EDGs) provided back up power and started cooling down the reactors. However, the tsunami flooded the facilities damaging 12 of its 13 EDGs and caused a blackout. Among the consequences were hydrogen explosions that released radioactive material in the environment. It is unfortunately clear that TEPCO and Japan's principal regulator Nuclear and Industrial Safety Agency (NISA) had failed in providing a professional hazard analysis for the plant, even though their last assessment had taken place only months before the accident. The main reasons are the following. One

  13. Reporting nuclear power plant operation to the Finnish Centre for Radiation and Nuclear Safety

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-09-01

    The Finnish Centre for Radiation and Nuclear safety (STUK) is the authority in Finland responsible for controlling the safety of the use of nuclear energy. The control includes, among other things, inspection of documents, reports and other clarification submitted to the STUK, and also independent safety analyses and inspections at the plant site. The guide presents what reports and notifications of the operation of the nuclear facilities are required and how they shall be submitted to the STUK. The guide does not cover reports to be submitted on nuclear material safeguards addressed in the guide YVL 6.10. Guide YVL 6.11 presents reporting related to the physical protection of nuclear power plants. Monitoring and reporting of occupational exposure at nuclear power plants is presented in the guide YVL 7.10 and reporting on radiological control in the environment of nuclear power plants in the guide YVL 7.8.

  14. Life management plants at nuclear power plants PWR; Planes de gestion de vida en centrales nucleares PWR

    Energy Technology Data Exchange (ETDEWEB)

    Esteban, G.

    2014-10-01

    Since in 2009 the CSN published the Safety Instruction IS-22 (1) which established the regulatory framework the Spanish nuclear power plants must meet in regard to Life Management, most of Spanish nuclear plants began a process of convergence of their Life Management Plants to practice 10 CFR 54 (2), which is the current standard of Spanish nuclear industry for Ageing Management, either during the design lifetime of the plant, as well as for Long-Term Operation. This article describe how Life Management Plans are being implemented in Spanish PWR NPP. (Author)

  15. Organization and safety in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Marcus, A.A.; Nichols, M.L.; Bromiley, P.; Olson, J.; Osborn, R.N.; Scott, W.; Pelto, P.; Thurber, J. (Minnesota Univ., Minneapolis, MN (USA). Strategic Management Research Center)

    1990-05-01

    Perspectives from industry, academe, and the NRC are brought together in this report and used to develop a logical framework that links management and organization factors and safety in nuclear power plant performance. The framework focuses on intermediate outcomes which can be predicted by organizational and management factors, and which are subsequently linked to safety. The intermediate outcomes are efficiency, compliance, quality, and innovation. The organization and management factors can be classified in terms of environment, context, organizational governance, organizational design, and emergent processes. Initial empirical analyses were conducted on a limited set of hypotheses derived from the framework. One set of hypotheses concerned the relationships between one of the intermediate outcome variables, efficiency, as measured by critical hours and outage rate, and safety, as measured by 5 NRC indicators. Results of the analysis suggest that critical hours and outage rates and safety, as measured in this study, are not related to each other. Hypotheses were tested concerning the effects on safety and efficiency of utility financial resources and the lagged recognition and correction of problems that accompanies the reporting of major violations and licensee event reports. The analytical technique employed was regression using polynomial distributed lags. Results suggest that both financial resources and organizational problem solving/learning have significant effects on the outcome variables when time is properly taken into account. Conclusions are drawn which point to this being a promising direction to proceed, though with some care, due to the current limitations of the study. 138 refs., 36 figs., 9 tabs.

  16. Seismic hazard mitigation for nuclear power plant

    Institute of Scientific and Technical Information of China (English)

    Frieder Seible

    2013-01-01

    The seismic safety of nuclear power plant(NPP) has always been a major consideration in the site selection,design,operation,and more recently recertification of existing installations.In addition to the actual NPP and all their operational and safety related support systems,the storage of spent fuel in temporary or permanent storage facilities also poses a seismic risk.This seismic risk is typically assessed with state-of-the-art modeling and analytical tools that capture everything from the ground rupture or source of the earthquake to the site specific ground shaking,taking geotechnical parameters and soil-foundation-structure-interaction (SFSI) into account to the non-linear structural response of the reactor core,the containment structure,the core cooling system and the emergency cooling system(s),to support systems,piping systems and non-structural components,and finally the performance of spent fuel storage in the probabilistically determined operational basis earthquake (OBE) or the safe shutdown earthquake (SSE) scenario.The best and most meaningful validation and verification of these advanced analytical tools is in the form of full or very large scale experimental testing,designed and conducted in direct support of model and analysis tool calibration.This paper outlines the principles under which such calibration testing should be conducted and illustrates with examples the kind of testing and parameter evaluation required.

  17. Organization and safety in nuclear power plants

    International Nuclear Information System (INIS)

    Perspectives from industry, academe, and the NRC are brought together in this report and used to develop a logical framework that links management and organization factors and safety in nuclear power plant performance. The framework focuses on intermediate outcomes which can be predicted by organizational and management factors, and which are subsequently linked to safety. The intermediate outcomes are efficiency, compliance, quality, and innovation. The organization and management factors can be classified in terms of environment, context, organizational governance, organizational design, and emergent processes. Initial empirical analyses were conducted on a limited set of hypotheses derived from the framework. One set of hypotheses concerned the relationships between one of the intermediate outcome variables, efficiency, as measured by critical hours and outage rate, and safety, as measured by 5 NRC indicators. Results of the analysis suggest that critical hours and outage rates and safety, as measured in this study, are not related to each other. Hypotheses were tested concerning the effects on safety and efficiency of utility financial resources and the lagged recognition and correction of problems that accompanies the reporting of major violations and licensee event reports. The analytical technique employed was regression using polynomial distributed lags. Results suggest that both financial resources and organizational problem solving/learning have significant effects on the outcome variables when time is properly taken into account. Conclusions are drawn which point to this being a promising direction to proceed, though with some care, due to the current limitations of the study. 138 refs., 36 figs., 9 tabs

  18. Insurance in the construction of nuclear power plants

    International Nuclear Information System (INIS)

    A nuclear power plant and the different kinds of insurance applied to it in the different phases of its lifetime are described. Besides, the scope of the coverage until the beginning of the commercial operation of the plant and the reasons for making a plant construction insurance are characterized. (A.L)

  19. Nuclear plant-aging research on reactor protection systems

    International Nuclear Information System (INIS)

    This report presents the rsults of a review of the Reactor Trip System (RTS) and the Engineered Safety Feature Actuating System (ESFAS) operating experiences reported in Licensee Event Reports (LER)s, the Nuclear Power Experience data base, Nuclear Plant Reliability Data System, and plant maintenance records. Our purpose is to evaluate the potential significance of aging, including cycling, trips, and testing as contributors to degradation of the RTS and ESFAS. Tables are presented that show the percentage of events for RTS and ESFAS classified by cause, components, and subcomponents for each of the Nuclear Steam Supply System vendors. A representative Babcock and Wilcox plant was selected for detailed study. The US Nuclear Regulatory Commission's Nuclear Plant Aging Research guidelines were followed in performing the detailed study that identified materials susceptible to aging, stressors, environmental factors, and failure modes for the RTS and ESFAS as generic instrumentation and control systems. Functional indicators of degradation are listed, testing requirements evaluated, and regulatory issues discussed

  20. Optimum operation cycle of nuclear plant in power system operation

    International Nuclear Information System (INIS)

    Extension of nuclear power plant operation cycle leads to improvement of its capacity factor and affects to suppress thermal plant generation of which fuel cost is relatively high. On the other hand, the number of nuclear fuel assembly to be exchanged at the time of maintenance increases with the operation cycle extension and this makes the fuel cost of nuclear generation high. For this reason, there exists the optimum operation cycle from the power system operation. This report deals with the optimum operation cycle of nuclear plant as the optimum sharing problem of generated energy between nuclear and thermal plants. The incremental fuel cost is considered to find the optimum value. The effects of the generation mix and high burn-up fuel on optimum operation cycle are examined. (author)

  1. Elecnuc. Nuclear power plants in the world. 1997

    International Nuclear Information System (INIS)

    This small booklet provides information about all type of nuclear power plants worldwide. It is based on the data taken from the CEA/DSE/SEE Elecnuc database. The content comprises: the 1996 highlights, the main characteristics of the different type of reactors in operation or under construction, the map of the French nuclear power plant sites, the worldwide status of nuclear power plants at the end of 1996, the nuclear power plants in operation, under construction or on order (by groups of reactor-types), the power capacity evolution of power plants in operation, the net and gross capacity of the power plants on the grid, the commercial operation and grid connection forecasts, the first achieved or expected power generation supplied by a nuclear reactor for each country and the power generation from nuclear reactors, the performance indicator of the PWR units in France, the trends of the power generation indicator worldwide, the nuclear power plants in operation, under construction, on order, planned, cancelled, decommissioned and exported worldwide, the schedule of steam generator replacements, and the MOX fuel plutonium recycling programme. (J.S.)

  2. Construction, Maintenance and Demolition of Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Smet, Camiel de [Hilti Corporation, P.O. Box 333, FL-9494 Schaan (Liechtenstein)

    2008-07-01

    Hilti is your reliable partner in nuclear power plant construction, maintenance and demolition worldwide. Professional advice and innovative solutions for virtually every phase of construction and supply technologically leading products and systems to increase your productivity and help to create and maintain safe and lasting plants is offered. The solutions for nuclear power plants construction, maintenance and demolition have been employed with great success in many different countries on a wide variety of projects due in no small way to their worldwide availability. An unbroken, international exchange of experience upholds a permanent innovation process. This assures our customers that they always receive products on the very latest technological standard. This paper is not intended to cover all topics related to nuclear power plants. The idea is more to give a kind of an overview. The paper covers briefly the following topics: safety (corrosion and fire), fastenings, measuring and finally decommissioning of nuclear power plants. (author)

  3. Next Generation Nuclear Plant Project Evaluation of Siting a HTGR Co-generation Plant on an Operating Commercial Nuclear Power Plant Site

    Energy Technology Data Exchange (ETDEWEB)

    L.E. Demick

    2011-10-01

    This paper summarizes an evaluation by the Idaho National Laboratory (INL) Next Generation Nuclear Plant (NGNP) Project of siting a High Temperature Gas-cooled Reactor (HTGR) plant on an existing nuclear plant site that is located in an area of significant industrial activity. This is a co-generation application in which the HTGR Plant will be supplying steam and electricity to one or more of the nearby industrial plants.

  4. The Fukushima Daiichi nuclear power plant accident: Update on compensation

    International Nuclear Information System (INIS)

    In the three years since the Fukushima Daiichi nuclear power plant (NPP) accident, the international community has gained perspective on the implementation of the Japanese nuclear liability regime, which reflects internationally accepted nuclear liability principles.1 Soon after the emergency, the operator of the damaged nuclear power plant, Tokyo Electric Power Company (TEPCO), and public authorities in Japan established the basic procedures required to compensate victims for damage incurred due to the accident. Since March 2011, these procedures have been adapted to allow the processing of a large number of applications for compensation within a reasonable amount of time. (author)

  5. Nuclear power plant functions: overview, maintenance, design practices, training

    International Nuclear Information System (INIS)

    The author gives a history of the nuclear industry in the US beginning with the Atoms for Peace Proposal in 1954 and summarizes the nuclear industry's importance in the realm of electric power production today. The primary problems facing the domestic nuclear industry are identified as the lengthening schedules for plant licensing and construction, and the associated uncertainty in plant costs and difficulty in financing, and the erosion of public confidence. Views on technological approaches to the future of nuclear power and the role regulation will play in the future as a fundamental force are discusses in the paper. Also discussed are the importance of standardization of advanced reactor designs and quality assurance

  6. Support services for new nuclear power plant projects

    International Nuclear Information System (INIS)

    TECNATOM is a spanish engineering company with more than 50 years of experience working for the nuclear industry all over the world. TECNATOM has worked in over 30 countries in activities related to the Operation and Maintenance of Nuclear Power Plants. It started to work in the design of new Nuclear Power Plants in the early 90s and since then has continued collaborating with different suppliers in the design and licensing of new reactors specially in the areas of plant systems design, Man-Machine Interface design, Main Control Room simulators building, training, qualification of equipment and PSI/ISI engineering services. (author)

  7. Stresses on nuclear power plant buildings by extraordinary events

    International Nuclear Information System (INIS)

    Nuclear power plant buildings must be functional to such an extend that even after the occurence of extraordinary events (earthquake, airoplane crash, gas cloud explosion), the reactor can be safety shut off, in order to avoid danger from the nuclear power plant. Evidence for this can only be given by calculations which shall meet the following requirements: The calculation results shall be safe and reliable. The calculation effort shall match the realizable accuracy. The calculation shall lead to an economical determination. An example of ascertainment of nuclear power plants in regard to earthquakes, shows the difficulties standing against a fulfillment of these requirements. (orig.)

  8. Designing reliable wireless sensor network for nuclear power plant

    International Nuclear Information System (INIS)

    This study proposes an innovative method for the monitoring the nuclear power plant. In this field, false detection of the trouble, both 'false negative' and 'false positive' will become a serious problem. In the other hand, since nuclear power plant is such a complicated system, wireless is required for implementing into real field. Considering these backgrounds, we propose a new reliable health monitoring system for nuclear power plant. This is based on an idea, 'a network on a network', such as 'wireless global network' on 'local network with self-maintenance function.' (author)

  9. Economic evaluation of bids for nuclear power plants

    International Nuclear Information System (INIS)

    The purpose of the guidebook is to assist an organisation responsible for a nuclear power project in evaluating and establishing an economic order of merit among competing bids. An approximate overall time schedule for a first nuclear power plant project is provided. A schematic outline of technical bid evaluation is given. The basic procedure of economic bid evaluation is outlined, e.g. evaluation of the present worth of all cost items of plant capital investment, of the nuclear cycle, of O and M costs (operation and maintenance costs), and of economic corrections. All these cost items are evaluated for the economic life of the plant and corrected for escalation where applicable

  10. A Role for Phosphoinositides in Regulating Plant Nuclear Functions

    Directory of Open Access Journals (Sweden)

    Catherine B Dieck

    2012-03-01

    Full Text Available Nuclear localized inositol phospholipids and inositol phosphates are important for regulating many essential processes in animal cells such as DNA replication, recombination, RNA processing, mRNA export and cell cycle progression. An overview of the current literature suggests that a nuclear phosphoinositide pathway occurs in plants as well. Inositol phospholipids, inositol phosphates and enzymes of the PI pathway have been identified in plant nuclei and are implicated in DNA replication, chromatin remodeling, stress responses and hormone signaling. It is anticipated that future research will help shed light on the functional significance of the plant nuclear PI pathway.

  11. Nuclear power plant life management in a changing business world

    International Nuclear Information System (INIS)

    At the end of 1999, there were 348 nuclear power plants connected to the grid in OECD Member countries, representing a total capacity of 296 GWe and generating some 24% of their electricity. One third of these nuclear power plants had been in operation for over 20 years. The demand for electricity throughout OECD countries is increasing steadily but the construction of new nuclear power plants has become increasingly difficult. Many utilities would like to keep existing nuclear power plants operating for as long as they can continue to function safely and economically because. extending the lifetime of nuclear power plants is a substitute to constructing new plants. Therefore, nuclear plant life management (PLIM) has been carried out in many OECD Member countries and has played a very important role in the nuclear generation field. Nuclear power plant owners seek to economically optimise the output from their plants, taking into consideration internal and external influences, as well as equipment reliability and maintenance workload. Nuclear power plant life management and extension is generally an attractive option for utilities supplying electricity because of its low marginal cost and low investment risk. PLIM has become an important issue in the context of changing business circumstances caused by regulatory reform of the electricity market. Specifically, the economic aspect of PLIM has become an important focus in the competitive electricity market. The international workshop on 'Plant Life Management in a Changing Business World' was hosted by the United States Department of Energy (USDOE) in co-operation with the Electric Power Research Institute (EPRI) and the Nuclear Energy Institute (NEI) in Washington, DC, on 26-27 June 2000. Some 50 senior utility executives and policy makers from 12 Member countries, the International Energy Agency (IEA) and the European Commission (EC) attended the meeting. The objective of the workshop was to examine the status of

  12. Quality assurance in the design of nuclear power plants

    International Nuclear Information System (INIS)

    This Safety Guide provides the requirements and recommendations related to the establishment and implementation of quality assurance for design of items for a nuclear power plant. The requirements of this Guide shall be applied to the extent necessary during all constituent activities of the nuclear power plant project, such as design, manufacture, construction, commissioning and operations. Its requirements and recommendations shall be implemented, as appropriate, by the responsible organization or by its designated representatives: by plant designers, architect-engineers or manufacturers, when involved in performing design activities related to items to be manufactured; by site constructors, when involved in field engineering activities; by plant operators and other organizations, when involved in design activities related to plant modifications or to selection of spare or replacement parts; and by design consultants and other technical organizations, when performing any engineering activity that affects the work of other design organizations during various stages of nuclear power plant projects

  13. Nuclear Power Plants and Sustainable Development on a Liberalized Market

    International Nuclear Information System (INIS)

    Finding a way to generate electricity so as to satisfy the terms of sustainable development of the entire society is the only way which will secure safe energy future. If we talk about energy in the context of sustainable development, one of the most important element is environmental protection. Since CO2 emissions stemming from electricity generation have predominant impact on climate change, one of the options for reducing emissions is the use of fuels without carbon, such as e.g. nuclear fuel. The future of nuclear power plants was considered in view of: nuclear fuel supply; potential impact of fuel cycle on environment, power plant operation, decommissioning and secondary products from electricity generation; and the entire nuclear power plant economy. Nuclear power plants were also examined in the context of the Kyoto Protocol stipulating reduction of greenhouse gases emissions. Nuclear power plants can not reduce CO2 emissions in a short-term because they already operate with maximum output, but in a long-run they can play a significant role. This paper is aiming to analyse the role of nuclear power plants in long term environmental sustainability in electricity sector reform (liberalisation, deregulation, privatisation) in small or medium sized power supply systems. Nuclear power plants are associated with certain environmental aspects which will be taken into account. A comparison will be made through externalities with other energy resources, especially fossil fuels, which are prevailing energy resources, considering possible use of nuclear power plants in the countries with small and medium-size grids. It will be given an example of the role of NPP Krsko on air emissions reduction in Croatia. (author)

  14. Siemens's spectrum of deliveries and services for nuclear power plants

    International Nuclear Information System (INIS)

    In 2001, Siemens and Framatome merged their nuclear activities in the present Areva NP joint venture. Siemens has since focused on the construction and further development of conventional power plants and on the so-called conventional island (CI), the non-nuclear part of a nuclear power plant, i.e. the steam turbine, generator, and plant I and C systems, and also on service for the conventional part of nuclear power plants. Its role as a minority shareholder in Areva NP constrained Siemens. For this reason, the company in January 2009 decided to terminate its interest in Areva NP effective January 30, 2012. By January 2012 at the latest, Siemens will transfer to the majority shareholder Areva, holding 66 percent of the shares, its interest in the joint venture. For the time being, the joint venture still entails certain limitations to Siemens's activities in the nuclear field. Its delivery of the conventional island for the Olkiluoto 3 (OL3) nuclear power plant in Finland confirms the company's know-how in power plant construction. When commissioned, its 1,720 MW power will make OL3 the world's largest nuclear generating unit. The turbo-generator of the CI comprises a double-flow HP turbine and a 6-flow LP turbine. The driven 4-pole generator with a power of up to 2,200 MVA consists of a water-cooled stator and a hydrogen-cooled rotor. (orig.)

  15. Information Technology for Nuclear Power Plant Configuration Management

    International Nuclear Information System (INIS)

    Configuration management (CM) is an essential component of nuclear power plant design, construction and operation. The application of information technology (IT) offers a method to automate and ensure the timely and effective capture, processing and distribution of key nuclear power plant information to support CM principles and practical processes and procedures for implementation of CM at nuclear power plants. This publication reviews some of the principles established in IAEA-TECDOC-1335, 'Configuration Management in Nuclear Power Plants.' It also recaps tenets laid out in IAEA- TECDOC-1284, 'Information Technology Impact on Nuclear Power Plant Documentation' that supports CM programmes. This publication has been developed in conjunction with and designed to support these other two publications. These three publications combined provide a comprehensive discussion on configuration management, information technology and the relationship between them. An extensive discussion is also provided in this publication on the role of the design basis of the facility and its control through the CM process throughout the facility's lifetime. While this report was developed specifically for nuclear power plants, the principles discussed can be usefully applied to any high hazard nuclear facility

  16. Requirements of safety for future nuclear power plants

    International Nuclear Information System (INIS)

    Presently, about 450 different nuclear power plants, partly highly developed, are operating worldwide. Thereby, a great contribution to the worldwide current supply is made by nuclear energy. With a capacity amounting to 360 GWel, these nuclear plants meet 17% of the total energy demand. The use of nuclear energy will become more and more important on a longterm basis, if attention is paid to aspects of resource saving, economic efficiency and care of the environment, with special regard to the reduction of CO2 emissions. This, however, requires high safety demands concerning the operation of plants, the intermediate storage and the final storage. Several approaches regarding the safety aspects of future nuclear plants are pursued today. The new safety quality has to ensure that radioactive fission products remain within the reactor plant in any case of failure and thus no catastrophic consequences can occur outside the plant. This is for instance provided by the modified German Atomic Law (1994). In the following account, the safety concept and the possibilities of nuclear core meltdown so far as well as their consequences are discussed. Based on this, the safety demands for future power stations are defined and put in concrete terms. Some examples of solutions that have already been realised and which meet the requirement of being without any risk of catastrophe are presented in the following. Having discussed the different concepts of realising a core reactor with new safety requirements, details concerning the proof of the safety behaviour of future nuclear power stations are explained. (orig.)

  17. Full-scale impact test data for tornado-missile design of nuclear plants

    International Nuclear Information System (INIS)

    It is standard practice to consider the effects of low-probability impacts of tornado-borne debris (''tornado missiles'' such as utility poles and steel pipes) in the structural design of nuclear power plants in the United States. To provide data that can be used directly in the design procedure, a series of full-scale tornado-missile impact tests was performed. This paper is a brief summary of the results and conclusions from these tests. The tests consisted of reinforced concrete panels impacted by poles, pipes, and rods propelled by a rocket sled. The panels were constructed to current minimum standards and had thicknesses typical of auxiliary buildings of nuclear power plants. A specific objective was the determination of the impact velocities below which the panels do not experience backface scabbing. Another objective was to assess the adequacy of (1) conventional design formulae for penetration and scabbing and (2) conventional design methods for overall structural response. Test missiles and velocities represented those in current design standards. Missiles included utility poles, steel pipes, and steel bars. It is important to interpret the data in this paper in recognition that the test conditions represent conservative assumptions regarding maximum wind speeds, injection of the missile into the wind stream, aerodynamic trajectory, and orientation of missile at impact. Even with the severe assumptions made, the full-scale tests described demonstrate the ability of prototypical nuclear plant walls and roofs to provide adequate protection against postulated tornado-missile impact

  18. SKFUE - a system for telemetric surveilling nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Birkle, M.; Hock, F.; Leins, R.

    1983-01-01

    For telemetric surveilling nuclear power plants the radioactive emissions are recorded at the plant and transmitted to a center at the governmental authority. In the center the contributions of each plant to the ambient background dose are calculated from source emissions and meteorological values by means of a Gaussian model. This publication describes construction and operation of an automatic system for telemetric surveilling nuclear power plants. Essential parts of such a system are the calculation methods, the possibilities of operator-communication and the output of results.

  19. Improving operator quality at Genkai Nuclear Power Plant

    International Nuclear Information System (INIS)

    Improvement in operator quality, or improvement in an operator's skill and professional knowledge, is of prime importance because of its great influence on safe and steady plant operation. This paper describes the education and training of reactor operators at the Genkai pressurized water reactor nuclear power plant with respect to the following topics: organization of Genkai power plant; education and training program management; training at the Nuclear Training Center; training and education on-site including emergency procedures training, normal operating procedures training, informational study of emergency conditions in existing plants, and all-around training of operators; qualifying tests for supervisors; and operator motivation

  20. Nuclear power plant and hydrogen injection device for nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Kobayashi, Masato; Fujisawa, Naoyuki [Hitachi Ltd., Tokyo (Japan)

    1997-11-28

    The present invention provides a nuclear power plant equipped with a hydrogen/oxygen generating device for generating hydrogen and oxygen by electrolysis of water and a hydrogen injection device for the nuclear power plant. Namely, there are disposed storage vessels for the electrolysis for each gas of hydrogen and oxygen and storing them and a means for detecting the amount of gases stored in each of the storage vessels. When the detection means detects that, at least one of the amount of the gas stored in each of the storage vessels is not increased to a predetermined level, the electrolysis of water is continued. When the amount of both of the storage vessels exceeds a predetermined value, the electrolysis of water is stopped or reduced. With such procedures, even when the amount of hydrogen required to be injected is changed, the balance of each of the gases can be kept appropriately. As a result, since an appropriate amount of hydrogen to be injected can be ensured, the amount of oxygen dissolved in filtration water can be kept appropriate. The corrosion potential on the surface of incore structural members can be suppressed to a value at which stress corrosion does not occur. (I.S.)

  1. Basic research on human reliability in nuclear power plants

    International Nuclear Information System (INIS)

    Human reliability in nuclear power plants is one of key factors in nuclear safety and economic operation. According to cognitive science, behaviour theory and ergonomic and on the bases of human cognitive behaviour characteristics, performance shaping factors, human error mechanisms and organization management, the project systematically studied the human reliability in nuclear power plant systems, established the basic theory and methods for analyzing human factor accidents and suggested feasible approaches and countermeasures for precaution against human factor accidents and improving human reliability. The achievement has been applied in operation departments, management departments and scientific research institutions of nuclear power, and has produced guiding significance and practical value to design, operation and management in nuclear power plants. (11 refs.)

  2. KWL Lingen nuclear plant. Technical annual report 2015

    International Nuclear Information System (INIS)

    The technical annual report 2015 on the Lingen nuclear plant covers the following issues: report on the segments operation, process engineering, safety engineering, licensing and supervising procedures, operational data, radiation protection, radioactive materials, and in-service inspections.

  3. Circumstances and consequences of Oural nuclear plant spoils

    International Nuclear Information System (INIS)

    The environment pollution frames serious long-dated problem. The civil nuclear power unhappily does not rest. The liquid waste fuel cycle plant prospective, particularly at their working beginning. 14 refs., 5 tabs

  4. Applying Functional Modeling for Accident Management of Nuclear Power Plant

    DEFF Research Database (Denmark)

    Lind, Morten; Zhang, Xinxin

    2014-01-01

    The paper investigate applications of functional modeling for accident management in complex industrial plant with special reference to nuclear power production. Main applications for information sharing among decision makers and decision support are identified. An overview of Multilevel Flow...

  5. Current problems associated with nuclear plant construction contracts

    International Nuclear Information System (INIS)

    The expansion of nuclear electricity generating programmes has brought to the fore the problems associated with construction of this type of power plant. The paper analyses the contracts for such construction and describes the most common, the turnkey contract. The present tendency is to limit the scope of turnkey contracts to the nuclear system or simply to the reactor and this is especially common in advanced nuclear countries such as the US, Canada, Japan, UK and France, and this is also the case in Italy where the question of contracting nuclear plants is debated. In Germany the power utilities hold a large number of shares in the manufacturing industry and the turnkey contract is therefore more economically attractive. A detailed description of the contracting procedure is provided, including the suppliers' and purchasers' responsibilities, plant commissioning tests and handing over of the plant to the operator. (NEA)

  6. Study on risk management for operation of nuclear generation plant

    International Nuclear Information System (INIS)

    Reputation loss is regarded as a management issue because it impacts to business and industries significantly. Reputation management is one of the approach both business and public organizations. Application of reputation management for nuclear plant management is discussed. (author)

  7. Periodic inspection of CANDU nuclear power plant containment components

    International Nuclear Information System (INIS)

    This Standard is one in a series intended to provide uniform requirements for CANDU nuclear power plants. It provides requirements for the periodic inspection of containment components including the containment pressure suppression systems

  8. Nuclear power plant operating experience. Annual report, 1978

    International Nuclear Information System (INIS)

    This report is the fifth in a series of reports issued annually that summarizes the operating experience of US nuclear power plants in commercial operation. Power generation statistics, plant outages, reportable occurrences, fuel element performance, occupational radiation exposure for each plant are presented. Summary highlights of these areas are discussed. The report includes 1978 data from 65 plants - 25 boiling water reactor plants and 40 pressurized water reactor plants. Discussion of radioactive effluents which has been a part of this report in previous years, has not been included in this issue because of late acquisition of data

  9. Fuel ethanol production using nuclear-plant steam

    International Nuclear Information System (INIS)

    In the United States, the production of fuel ethanol from corn for cars and light trucks has increased from about 6 billion liters per year in 2000 to 19 billion liters per year in 2006. A third of the world's liquid fuel demands could ultimately be obtained from biomass. The production of fuel ethanol from biomass requires large quantities of steam. For a large ethanol plant producing 380 million liters of fuel ethanol from corn per year, about 80 MW(t) of 1-MPa (∼180 deg. C) steam is required. Within several decades, the steam demand for ethanol plants in the United States is projected to be tens of gigawatts, with the worldwide demand being several times larger. This market may become the largest market for cogeneration of steam from nuclear electric power plants. There are strong incentives to use steam from nuclear power plants to meet this requirement. The cost of low-pressure steam from nuclear power plants is less than that of natural gas, which is now used to make steam in corn-to-ethanol plants. Steam from nuclear power plants reduces greenhouse gases compared with steam produced from fossil fuels. While ethanol is now produced from sugarcane and corn, the next-generation ethanol plants will use more abundant cellulose feedstocks. It is planned that these plants will burn the lignin in the cellulosic feedstocks to provide the required steam. Lignin is the primary non-sugar-based component in cellulosic biomass that can not be converted to ethanol. Low-cost steam from nuclear plants creates the option of converting the lignin to other liquid fuels and thus increase the liquid fuel production per unit of biomass. Because liquid fuel production from biomass is ultimately limited by the availability of biomass, steam from nuclear plants can ultimately increase the total liquid fuels produced from biomass. (author)

  10. Possible genetic damage in the Czech nuclear power plant workers

    International Nuclear Information System (INIS)

    The aim of our study was to identify occupational risk of irradiation exposure in the Czech nuclear power plant workers. We analyzed levels of chromosomal aberrations, a well-known biomarker of early biological effects and a predictor of cancer risk. We applied the conventional method of cytogenetic analysis and fluorescence in situ hybridization (FISH, whole chromosome painting for chromosomes 1 and 4, combined with a pancentromeric probe) to three groups: 123 subjects in the Temelin nuclear power plant (2 years in use), 114 subjects in the Dukovany nuclear power plant (20 years in use), and 53 matched controls from Ceske Budejovice. Nuclear power plant workers were divided into two groups: subjects with admittance into the monitored zone, and others. Following factors were also analyzed: GSTM1, GSTT1, GSTP1, XPD, XRCC1, hOGG1, p53, MTHFR, and MS gene polymorphisms, levels of vitamins A, C, E, and folate in plasma, and level of cotinine in urine. Long-term exposure to ionizing radiation in the monitored zone was 0.47 ± 1.50 mSv (miliSievert) in the Temelin nuclear power plant and 5.74 ± 9.57 mSv in the Dukovany nuclear power plant. Using the conventional cytogenetic analysis, we observed 1.90 ± 0.95 and 1.82 ± 1.19% AB.C. (percent of aberrant cells) in the Temelin nuclear power plant, and 2.39 ± 1.01 and 2.33 ± 1.04% AB.C. in the Dukovany nuclear power plant, for monitored zone workers and others, respectively. In the control group, we found 2.25 ± 0.82% AB.C. Genomic frequency of translocations F G/100 measured by FISH was 1.89 ± 1.40 and 2.01 ± 1.68 in the Temelin nuclear power plant, and 2.48 ± 1.93 and 2.14 ± 1.62 in the Dukovany nuclear power plant for monitored zone workers and others, respectively. In the control group, F G/100 was 1.83 ± 1.19. Following factors were identified as potential confounders by the conventional cytogenetic analysis: XPD-6, by the FISH: age, GSTP1 and p53Bst genotypes, long-term use of medication, alcohol consumption

  11. Erosion and corrosion of nuclear power plant materials

    International Nuclear Information System (INIS)

    This conference is composed of 23 papers, grouped in 3 sessions which main themes are: analysis of corrosion and erosion damages of nuclear power plant equipment and influence of water chemistry, temperature, irradiations, metallurgical and electrochemical factors, flow assisted cracking, stress cracking; monitoring and control of erosion and corrosion in nuclear power plants; susceptibility of structural materials to erosion and corrosion and ways to improve the resistance of materials, steels, coatings, etc. to erosion, corrosion and cracking

  12. Generic environmental impact statement for license renewal of nuclear plants

    International Nuclear Information System (INIS)

    Volume 2 of the Generic Environmental Impact Statement for License Renewal of Nuclear Plants contains the appendices. These include: (A) General characterisitics and environmental settings of domestic nuclear plants, (B) Definition of impact initiators, (C) Socioeconomics and case studies, (D) Aquatic organisms and human health, (E) Radiation protection considerations, (F) Methodology for assessing impacts to aquatic ecology and water resources, (G) Postulated accidents, and (H) Environmental statutes and regulations affecting license renewal

  13. Training and qualification of nuclear power plant operators (4)

    International Nuclear Information System (INIS)

    Training center using the simulators, instructor training, training upgrade, deployment of digital control panel and review of training were described with overseas practice. Recently, nuclear power plant on-site simulators were also used for respective operator training. Operator teamwork training, training team performance upgrade, reflection of operating experiences in nuclear power plant accidents, development of training support equipments and management of training records were needed to review and upgrade training and qualification programs. (T. Tanaka)

  14. The protection of nuclear power plants against attacks from outside

    International Nuclear Information System (INIS)

    Up to now nuclear power plants or nuclear research centres have been guarded either by company internal security personnel or chiefly by hired private security companies. According to the author's opinion, it appears advisable, considering the objections made from the view of safety law and constitutional law, to provide such protection by police forces and to have these costs refunded by the plant management. (orig./HSCH)

  15. Electropulse method of decontamination of nuclear power plant equipment

    International Nuclear Information System (INIS)

    A review of existing methods of decontamination of nuclear power plant equipment; it describes the advantages and disadvantages of the existing methods. A new promising method for decontamination of removable NPP equipment with a complex surface configuration. The technology and the advantages of the proposed method. Presented physical -mathematical model that calculates non- steady field electrolyte concentration, temperature and electric field in the electrolyte during electro surface treatment. Key words: corrosion, radioactive contamination, decontamination, equipment, nuclear power plant

  16. Designing reliable sensor network for nuclear power plant

    International Nuclear Information System (INIS)

    This study proposes an innovative method for the monitoring the nuclear power plant. In this field, false detection of the trouble, both 'false negative' and 'false positive' will become a serious problem. In the other hand, since its complexity of nuclear power plant, simplicity of monitoring system is strongly required. Here, we propose a new simple and reliable health monitoring sensor network system. Our pulse width modulation technique realizes a self-maintenance function in single signal line (token ring shaped). (author)

  17. Computer system for nuclear power plant parameter display

    International Nuclear Information System (INIS)

    The computer system for efficient, cheap and simple presentation of data on the screen of the personal computer is described. The display is in alphanumerical or graphical form. The system can be used for the man-machine interface in the process monitoring system of the nuclear power plant. It represents the third level of the new process computer system of the Nuclear Power Plant Krsko. (author)

  18. Lessons of the Chernobyl Nuclear Power Plant accident

    International Nuclear Information System (INIS)

    Insensitivity of radiation without measuring apparatus and health outcome observed in the atomic bomb survivors of Hiroshima and Nagasaki are major sources that make people fear the possible late effects of radiation exposure attributable to nuclear power plant accident. However, the health conditions of people in the last 20 years around Chernobyl indicated the necessity to review the risk assessment suggesting that effects of radiation exposure may considerably be different between the atomic bombing and nuclear power plant accident. (author)

  19. Comparison of buildings of Czechoslovak and foreign nuclear power plants

    International Nuclear Information System (INIS)

    The reliability rate is discussed of comparing nuclear power plants by literature data and an analysis is made of the comparison methodology. The results show that building work in Czechoslovak nuclear power plants is significantly less effective than that in non-socialist countries (adjusted to volumes related to 1 MW of power). The most important characteristic volumes are more than twice as high. Ways are outlined of improving labor productivity. (J.B.). 2 tabs., 4 refs

  20. Educational systems - educational qualification of nuclear power plant personnel

    International Nuclear Information System (INIS)

    In this lecture the following common features of education and training systems are described: - description of general school education, vocational training and engineering study programs, - allocation of categories of activities to normal school training backgrounds, - recommendations for educational and training programs required for various positions in nuclear power plants (formal and on-the-job training), - examinations and licences for the personnel at nuclear power plants. (orig./GL)

  1. Method for treatment of wastewater of nuclear power plants

    International Nuclear Information System (INIS)

    A method for treatment of wastewater of nuclear power plants is characterized by the fact that concentration and volume reduction are performed after Ca and Mg as components for the formation of an adhering scale is converted to an 8-oxyquinoline complex, which is hardly soluble in water, and does not precipitate out as an adhering scale, by the addition of 8-oxyquinoline into nuclear power plant wastewater

  2. Contractual aspects of the establishment of nuclear power plants

    International Nuclear Information System (INIS)

    This paper analyses the complexity of the system for establishing nuclear power plants in Italy, in the light of ENEL's experience and provides a thorough description of the types of contract involved, the respective rights and obligations of the parties concerned and the problems encountered. Reference is made to the legislation governing the licensing procedure for nuclear power plants and the competent authorities in this respect. (NEA)

  3. Report of the Committee Existing Nuclear Power Plants

    International Nuclear Information System (INIS)

    This report embodies the findings of the Committee 'Existing Nuclear Power Plants' of the Dutch Department of Economic Affairs. The terms of reference comprised an actual analysis of several aspects of the Netherlands' nuclear power. Two options are studied: (1) permanent and (2) temporary shutdown of the existing plants. As a substitute, only electric power generation using coal is considered. Subsequently, the committee deals with legal aspects; financial-economical aspects; employment, energy policy, security risks; environmental aspects; international and political aspects. (Auth.)

  4. Nuclear Power Plant Control and Instrumentation in Pakistan

    International Nuclear Information System (INIS)

    Nuclear reactors generate 15% of the world's supply electric power. The substantial growth in world energy demand is inevitably continuing throughout the next century. Nuclear power which has already paid more than enough for itself and its development, will provide increasing share of electricity production both in the developed and developing countries. For Pakistan with limited natural resources such as oil, gas, and fully tapped hydel power, nuclear power is the only viable option. However, things are not simple for developing countries which embark on nuclear power program. A technical infrastructure should be established as it has been shown by the experience of Control and Instrumentation of the Karachi Nuclear Power Plant. The national report describes the program of Pakistan Atomic Energy Commission in (NPP) Computers, Control and Instrumentation for design, construction, operation, and maintenance of nuclear power plants. (author)

  5. Knowledge preservation strategies for nuclear power plants

    International Nuclear Information System (INIS)

    The nuclear industry is currently facing several challenges. An internal threat to the safety and operations of nuclear power plants is the loss of those employees who hold knowledge that is either critical to operations or safety. This report discusses the possibilities to preserve knowledge in nuclear power plants. The major threat to any knowledge-based operation is the often-unclear relationship between the employees' knowledge and the organization's output. Depending on whether the organizational activities are rather product or process-oriented the identification of the critical knowledge is organized differently: while product-oriented activities are rather task driven, the first unit of knowledge preservation analysis in such environments is the task. It is analyzed which employees contribute to the task and how important each employee's contribution to the task fulfilment is. In process-oriented environments a similar procedure is followed. Here the process is analyzed according to which employees provide process input and how critical this input is to the process output. In both situations, those employees that provide critical input to the task/process become the unit of analysis. Employees are analyzed according to which knowledge bases they dispose of and deploy in order to reach their objectives. Knowledge is seen as the capacity for effective action and the result of a process that integrates expertise, methodological knowledge, social competence and meta-knowledge. Knowledge can be differentiated into two types of knowledge: explicit and tacit. While explicit knowledge is not too different from information, tacit knowledge is tough to grasp and tough to handle. While people are able to ride a bicycle or to swim, they are normally not capable to explain why they are able to do this. This is a problem for an organization when it wants to preserve knowledge. Thus tacit knowledge poses the primary barrier to knowledge preservation. Dependent on the

  6. Psychological characteristics of licensed nuclear power plant operators

    International Nuclear Information System (INIS)

    The safe production of electricity by nuclear power plants has been the focus of considerable attention. Much of this concern has been focused on equipment and procedural issues, with less attention to the psychological factors that affect the operations staff of the plants, i.e., those individuals who are most directly responsible for a plant's operations. Stress and type A qualities would be significant for these individuals because of their relationships to job performance and health. Of equal significance would be work-related factors, such as job involvement and work pressure. Also of interest would be hostile tendencies because of the need for cooperation and communications among operations staff. Two variables could influence these psychological factors. One is the degree of responsibility for a plant's nuclear reactors. The individuals with the greatest responsibility are licensed by the US Nuclear Regulatory Commission (NRC). There are also individuals with less direct responsibilities who are not licensed. A second variable is the operating status of the plant, whether or not the plant is currently producing electricity. Relative to ensuring the safe operation of nuclear power plants, these data suggest a positive view of licensed operators. Of interest are the greater stress scores in the licensed staff of the operating plant in contrast with their peers in the nonoperating plant

  7. Method for assigning sites to projected generic nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Holter, G.M.; Purcell, W.L.; Shutz, M.E.; Young, J.R.

    1986-07-01

    Pacific Northwest Laboratory developed a method for forecasting potential locations and startup sequences of nuclear power plants that will be required in the future but have not yet been specifically identified by electric utilities. Use of the method results in numerical ratings for potential nuclear power plant sites located in each of the 10 federal energy regions. The rating for each potential site is obtained from numerical factors assigned to each of 5 primary siting characteristics: (1) cooling water availability, (2) site land area, (3) power transmission land area, (4) proximity to metropolitan areas, and (5) utility plans for the site. The sequence of plant startups in each federal energy region is obtained by use of the numerical ratings and the forecasts of generic nuclear power plant startups obtained from the EIA Middle Case electricity forecast. Sites are assigned to generic plants in chronological order according to startup date.

  8. Annual report 1986 of Grohnde nuclear power plant (KWG)

    International Nuclear Information System (INIS)

    The 1986 annual report about the activities of the Grohnde nuclear power plant discusses the operation, engineering, electro-technics, physics and chemistry of the plant as well as the training aspect. The section referring to the operation of the plant deals with the operational diagram, electric power generation and electric power consumption, availability aspects, cooling modes, notifiable accidents, the up-dating of specific events, etc. Apart from giving a general survey, the engineering section focuses on work orders. The electro-technics section deals with the range of possible events, the breakdown of structural components, the frequency of incidents, and with relevant measures with regard to nuclear power plant revisions. Radiation protection falls under the section on physics and chemistry. The final section refers to the training of nuclear power plant staff. (HAG)

  9. Towards appropriate seismic margins in nuclear plant piping

    International Nuclear Information System (INIS)

    Some results of ongoing research being conducted for the US Nuclear Regulatory Commission (NRC) at the Energy Technology Engineering Center (ETEC) are reported. These results include the development of a methodology for establishing and estimating appropriate seismic margins in nuclear plant piping

  10. Method for assigning sites to projected generic nuclear power plants

    International Nuclear Information System (INIS)

    Pacific Northwest Laboratory developed a method for forecasting potential locations and startup sequences of nuclear power plants that will be required in the future but have not yet been specifically identified by electric utilities. Use of the method results in numerical ratings for potential nuclear power plant sites located in each of the 10 federal energy regions. The rating for each potential site is obtained from numerical factors assigned to each of 5 primary siting characteristics: (1) cooling water availability, (2) site land area, (3) power transmission land area, (4) proximity to metropolitan areas, and (5) utility plans for the site. The sequence of plant startups in each federal energy region is obtained by use of the numerical ratings and the forecasts of generic nuclear power plant startups obtained from the EIA Middle Case electricity forecast. Sites are assigned to generic plants in chronological order according to startup date

  11. Use of artificial intelligence in nuclear power plants

    International Nuclear Information System (INIS)

    The application of artificial intelligence, in the form of expert systems and neural networks, to the control room activities in a nuclear power plant has the potential to reduce operator error and increase plant safety, reliability, and efficiency. Furthermore, there are a large number of non-operating activities (testing, routine maintenance, outage planning, equipment diagnostics, and fuel management) in which artificial intelligence can increase the efficiency and effectiveness of overall plant and corporate operations. This paper reviews the state-of-the-art of artificial intelligence techniques, specifically, expert systems and neural networks, to nuclear power plants. This paper has reviewed the state-of-the-art of artificial intelligence, specifically expert systems and neural networks that are applied to problems in nuclear power plants

  12. Performance evaluation of fiber optic components in nuclear plant environments

    Energy Technology Data Exchange (ETDEWEB)

    Hastings, M.C.; Miller, D.W. [Ohio State Univ., Columbus, OH (United States); James, R.W. [Electric Power Research Institute, Palo Alto, CA (United States)

    1996-03-01

    Over the past several years, the Electric Power Research Institute (EPRI) has funded several projects to evaluate the performance of commercially available fiber optic cables, connective devices, light sources, and light detectors under environmental conditions representative of normal and abnormal nuclear power plant operating conditions. Future projects are planned to evaluate commercially available fiber optic sensors and to install and evaluate performance of instrument loops comprised of fiber optic components in operating nuclear power plant applications. The objective of this research is to assess the viability of fiber optic components for replacement and upgrade of nuclear power plant instrument systems. Fiber optic instrument channels offer many potential advantages: commercial availability of parts and technical support, small physical size and weight, immunity to electromagnetic interference, relatively low power requirements, and high bandwidth capabilities. As existing nuclear power plants continue to replace and upgrade I&C systems, fiber optics will offer a low-cost alternative technology which also provides additional information processing capabilities. Results to date indicate that fiber optics are a viable technology for many nuclear applications, both inside and outside of containments. This work is funded and manage& under the Operations & Maintenance Cost Control research target of EPRI`s Nuclear Power Group. The work is being performed by faculty and students in the Mechanical and Nuclear Engineering Departments and the staff of the Nuclear Reactor Laboratory of the Ohio State University.

  13. The Brazilian participation in the nuclear power plant construction

    International Nuclear Information System (INIS)

    A brief review about the origin of the brazilian nuclear power program and the strategy adopted for its implementation in Brazil is presented. The creation of the Nuclebras Engineering S/A, the Germany technology transfer and the personell job-training in Brasil are discussed. Some management models used for nuclear power plant construction in the world are still presented. (E.G.)

  14. Experience feedback system of nuclear power plant under construction

    International Nuclear Information System (INIS)

    The Experience Feedback System of Hainan Nuclear Power Plant under construction, which is a typical EPC nuclear power project, is introduced in the paper. And the good practice of the system set a good example for those NPPs under construction in China. (authors)

  15. Economics and policies of nuclear plant life management

    International Nuclear Information System (INIS)

    NEA provides an opportunity for international exchange of information on the economics and policies of nuclear plant life management for governments and plant owners. The NEA Secretariat is finalising the 'state-of-the-art report' on the economics and policies of nuclear plant life management, including the model approach and national summaries. In order to meet power supply obligations in the early 2000, taking into account energy security, environmental impact, and the economics of nuclear power plants whose lives have been extended, initiatives at national level must be taken to monitor, co-ordinate, and support the various industry programmes of nuclear plant life management by integrated and consistent policies, public acceptance, R and D, and international co-operation. Nuclear power owners should establish an organisation and objectives to carry nuclear plant life management in the most economic and smoothest way taking into consideration internal and external influences. The organisation must identify the critical item and the ageing processes, and optimise equipment reliability and maintenance workload. (author)

  16. Safety of nuclear power plants: Operation. Safety requirements

    International Nuclear Information System (INIS)

    The safety of a nuclear power plant is ensured by means of its proper siting, design, construction and commissioning, followed by the proper management and operation of the plant. In a later phase, proper decommissioning is required. This Safety Requirements publication supersedes the Code on the Safety of Nuclear Power Plants: Operation, which was issued in 1988 as Safety Series No. 50-C-O (Rev. 1). The purpose of this revision was: to restructure Safety Series No. 50-C-O (Rev. 1) in the light of the basic objectives, concepts and principles in the Safety Fundamentals publication The Safety of Nuclear Installations; to be consistent with the requirements of the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources; and to reflect current practice and new concepts and technical developments. Guidance on fulfillment of these Safety Requirements may be found in the appropriate Safety Guides relating to plant operation. The objective of this publication is to establish the requirements which, in the light of experience and the present state of technology, must be satisfied to ensure the safe operation of nuclear power plants. These requirements are governed by the basic objectives, concepts and principles that are presented in the Safety Fundamentals publication The Safety of Nuclear Installations. This publication deals with matters specific to the safe operation of land based stationary thermal neutron nuclear power plants, and also covers their commissioning and subsequent decommissioning

  17. Preventing the loss of knowledge in nuclear power plants

    International Nuclear Information System (INIS)

    Preventing the loss of nuclear knowledge has become an important concern for the atomic energy industry. A great number of nuclear workers are getting close to the retirement age and there are not enough young qualified people to replace them. It is necessary to identify the key skills to replace senior engineers, managers and experienced workers. This paper proposes a matrix for capturing the strategic nuclear knowledge obtained from plants operation in the past decades. (author)

  18. Almaraz Nuclear Power Plant en 2001

    International Nuclear Information System (INIS)

    At the beginning of the year, both Units were connected to the grid and operating stably at 100% power. During 2001, 16,343 million kWh were generated. The year's accumulated capability factor for both units was greater than 96% (99.81% in Unit I and 92.34% in Unit II). The operating factor was 99.86% in Unit I and 94.05% in Unit II. Unit I was operating all year in its fifteenth operating cicle. The most important activity was the thirteenth refueling and maintenance outage in Unit II. The time spent to complete the programmed activities was 21 days and 4 jours. Both units as a whole have surpassed the production objectives by 3% Unit 1 by 2.31% and Unit II by 3.74%. The main reasons that have contributed to achieving these objectives were, on one hand, the low number of incidents recorded throughout the year and, on the other, the fact that the refueling outage was executed in less than the scheduled time. The multiple milestones achieved in 2001 include the highest figure for electric power produced in one year by the plant, the highest unit capability factor (Unit 1 with 99.8%) a historical record of monthly gross energy production with 727 million kWh (Unit II in December), and the shortest refueling outage. The gross electric power produced by Unit I during the year was 8,458 million kWh, and accumulated production from source was 131,890million kWh. As for Unit II, production was 7.885 million kWh, and accumulated production from source was 127,789 million kWh. At year's end both Units were operating at 100% power, with Unit I supplying 976 MWe and UNit II 979 MWe. The annual emergency drill was carried out on May 24. The main feature was the scope of category IV, ''General Electric'', with the resulting Site evacuation. All involved organizations were mobilized during the drill to check coordination between them and the established channels of communication. The results were qualified as satisfactory. In addition, on November 21, a general PENCA (Caceres

  19. Preparation for commissioning of nuclear plant with reference to British Nuclear Fuels Plc fuel handling plant project

    International Nuclear Information System (INIS)

    The new Fuel Handing Plant at British Nuclear Fuels Sellafield is part of a Pound 550M complex which provides facilities for the receipt, storage and mechanical preparation of both magnox and A.G.R. fuel. The plant is very large and complex with considerable use of computer based process control systems, providing for physical and nuclear safety. The preparation of such plant for ''active'' commissioning necessitates a great many physical checks and technical evaluations in support of its safety case. This paper describes arrangements for plant commissioning checks, against the regulatory framework and explains the physical preparations necessary for their timely accomplishment. (author)

  20. Plant designer's view of the operator's role in nuclear plant safety

    International Nuclear Information System (INIS)

    The nuclear plant operator's role supports the design assumptions and equipment with four functional tasks. He must set up th plant for predictable response to disturbances, operate the plant so as to minimize the likelihood and severity of event initiators, assist in accomplishing the safety functions, and feed back operating experiences to reinforce or redefine the safety analyses' assumptions. The latter role enhances the operator effectiveness in the former three roles. The Safety Level Concept offers a different perspective that enables the operator to view his roles in nuclear plant safety. This paper outlines the operator's role in nuclear safety and classifies his tasks using the Safety Level Concept

  1. Site selection for new nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Rizzo, Paul C.; Dubinsky, Melissa; Tastan, Erdem Onur, E-mail: paul.rizzo@rizzoassoc.com, E-mail: melissa.dubinsky@rizzoassoc.com, E-mail: onur.tastan@rizzoassoc.com [RIZZO Associates Inc., Pittsburgh, PA (United States); Miano, Sandra C., E-mail: scm27@psu.edu [Eletrobras Termonuclear S.A. (ELETRONUCLEAR), RJ (Brazil); Pennsylvania State University, Department of Mechanical and Nuclear Engineering, State College, PA (United States)

    2015-07-01

    The current methodology for selecting the most advantageous site(s) for nuclear power plant (NPP) development is based on the latest evolution of protocols originally established in the 1990's by the Electric Power Research Institute (EPRI) and others for programs in the USA, and more recently by the International Atomic Energy Agency (IAEA), among others. The methodology includes protocols that account for lessons learned from both the Gen III projects and the catastrophic event at Fukushima, Japan. In general, the approach requires consideration of Exclusionary or 'fatal flaw' Criteria first, based on safety as well as significant impact to the environment or human health. Sites must meet all of these Exclusionary Criteria to be considered for NPP development. Next, the remaining sites are evaluated for Avoidance Criteria that affect primarily ease of construction and operations, which allow a ranking of sites best suited for NPP development. Finally, Suitability Criteria are applied to the potential sites to better differentiate between closely ranked sites. Generally, final selection of a Preferred and an Alternate Site will require balancing of factors, expert judgment, and client input, as sites being compared will differ in their scores associated with different Avoidance Criteria and Suitability Criteria. RIZZO Associates (RIZZO) offers in this paper a modification to this methodology for selecting the site for NPP development, which accords to the categories of Exclusionary, Avoidance and Suitability Criteria strict definitions which can be considered as Absolute Factors, Critical Factors, and Economic Factors for a more focused approach to site selection. Absolute Factors include all of the safety-related Exclusionary Criteria. Critical Factors are those that are difficult to overcome unless extraordinary mitigation measures are implemented; they have a significant impact on the ability of the project to be successful and may cause the

  2. Nuclear Power Plant Maintenance Optimization with Heuristic Algorithm

    Directory of Open Access Journals (Sweden)

    Andrija Volkanovski

    2014-01-01

    Full Text Available The test and maintenance activities are conducted in the nuclear power plants in order to prevent or limit failures resulting from the ageing or deterioration. The components and systems are partially or fully unavailable during the maintenance activities. This is especially important for the safety systems and corresponding equipment because they are important contributors to the overall nuclear power plant safety. A novel method for optimization of the maintenance activities in the nuclear power plant considering the plant safety is developed and presented. The objective function of the optimization is the mean value of the selected risk measure. The risk measure is assessed from the minimal cut sets identified in the Probabilistic Safety Assessment. The optimal solution of the objective function is estimated with genetic algorithm. The proposed method is applied on probabilistic safety analysis model of the selected safety system of the reference nuclear power plant. Obtained results show that optimization of maintenance decreases the risk and thus improves the plant safety. The implications of the consideration of different constraints on the obtained results are investigated and presented. The future prospects for the optimization of the maintenance activities in the nuclear power plants with the presented method are discussed.

  3. On the ''Economics of nuclear power plant operation'' study

    International Nuclear Information System (INIS)

    The article presents a critical review of a study BMU commissioned from the Wuppertal Institut and the Oeko Institut about economic aspects of nuclear power plant operation. Besides the fact that the study deals with economic matters within the competency not of the Ministry for the environment but of the Ministry of Economics, it contains a few illogical arguments. The study was supposed to prove these points: (1) Nuclear power plants in Germany have paid off in less than thirty years. (2) The generating costs of nuclear power plants in some instances are above the market price of electricity. (3) During the operating life of a plant, the operators derive considerable economic benefits from the reserves for decommissioning, demolition, and waste management, which more than offset the losses incurred in electricity generation. Under item (1), the expert opinion arrives are contradictory findings: On the one hand, payoff had to be assumed within less than thirty years. On the other hand, present low electricity prices no longer permitted many nuclear power plants to be run economically. Under the heading of electricity prices, the opinion arrives at the conclusion that almost all nuclear power plants should be shut down as the spot market price of electricity was sufficient to cover all costs in hardly any nuclear power plant. Under the cost item, again pure cost considerations and financial assessments are mixed up. Under item (3), reserves, the opinion does discuss the interesting alternative of waste managements funds which, however, according to the opinion, would have to create incentives to shut down a major part of nuclear power plants right away. In summary, the opinion proves item (1), which is hardly a point of conflict, but its findings on items (2) and (3) are highly doubtful. However, this is not likely to prevent the opinion from being used in the political debate. (orig.)

  4. Modeling of the core of Atucha II nuclear power plant

    International Nuclear Information System (INIS)

    This work is part of a Nuclear Engineer degree thesis of the Instituto Balseiro and it is carried out under the development of an Argentinean Nuclear Power Plant Simulator. To obtain the best representation of the reactor physical behavior using the state of the art tools this Simulator should couple a 3D neutronics core calculation code with a thermal-hydraulics system code. Focused in the neutronic nature of this job, using PARCS, we modeled and performed calculations of the nuclear power plant Atucha 2 core. Whenever it is possible, we compare our results against results obtained with PUMA (the official core code for Atucha 2). (author)

  5. Safety-related occurrences at the Finnish nuclear power plants

    International Nuclear Information System (INIS)

    This report contains detailed descriptions of operating incidents and other safety-related matters at the Finnish nuclear power plants regarded as significant by the regulatory authority, the Finnish Centre for Radiation and Nuclear Safety. In this connection, an account is given of the practical actions caused by the incidents, and their significance to reactor safety is evaluated. The main features of the incidents are also described in the general Quartely Report for this period, Operation of Finnish Nuclear Power Plants (STUK-B-YTO 12), which is supplemented by this report intended for experts. (author)

  6. Aging of concrete structures in nuclear power plants

    International Nuclear Information System (INIS)

    The Structural Aging (SAG) Program, sponsored by the US Nuclear Regulatory Commission (USNRC) and conducted by the Oak Ridge National Laboratory (ORNL), had the overall objective of providing the USNRC with an improved basis for evaluating nuclear power plant structures for continued service. The program consists of three technical tasks: materials property data base, structural component assessment/repair technology, and quantitative methodology for continued service determinations. Major accomplishments under the SAG Program during the first two years of its planned five-year duration have included: development of a Structural Materials Information Center and formulation of a Structural Aging Assessment Methodology for Concrete Structures in Nuclear Power Plants. 9 refs

  7. Siting studies for new nuclear power plants in Argentina

    International Nuclear Information System (INIS)

    This paper is a summary of the thesis prepared by the Group of Prospective and Energy Planning of the National Atomic Energy Commission for the 'Specialization on Applications of Nuclear Technology Course' of the Instituto Balseiro in 2007. It describes the evolution of siting studies through time and the main focus worldwide in this type of studies. Then, it makes a brief review of previous siting studies of nuclear power plants conducted in Argentina. It carries out a description of the methodology to conduct a site evaluation for nuclear power plants according to actual international criteria. Finally, it describes the licensing process that follows every site study. (author)

  8. Human factors analyses of nuclear power plant incidents

    International Nuclear Information System (INIS)

    Human action plays vital role in occurrence and progression of many nuclear power plant incidents such as occurred in TMI-2 and Chernobyl reactors. Therefore, it is essential for ensuring safety of nuclear facilities to prevent occurrence of human error and to take proper recovery action if it occurs. It is necessary to have deep understanding of causes and mechanism of human error. For this purpose, we analysed operators behavior in seven U.S. nuclear power plant incidents from the view point of human factors. (author)

  9. Human Performance at the Perry Nuclear Power Plant

    International Nuclear Information System (INIS)

    Provides a description of human performance training for plant workers as implemented at the Perry Nuclear Power Plant. Practical concepts regarding the training are presented as well as a demonstration of some of the training material. Concepts are drawn from INPO, Reason and Deming. The paper encourages the use of site-wide and individual organizational unit training in human performance management techniques. (author)

  10. Nuclear magnetic response imaging of sap flow in plants

    NARCIS (Netherlands)

    Windt, C.W.

    2007-01-01

    This thesis deals with Nuclear Magnetic Resonance (NMR) imaging of long distance transport in plants. Long distance transport in plants is an enigmatic process. The theoretical framework that describes its basic properties has been in place for almost a century, yet at the same time only little is k

  11. Code on the safety of nuclear power plants: Governmental organization

    International Nuclear Information System (INIS)

    This Code recommends requirements for a regulatory body responsible for regulating the siting, design, construction, commissioning, operation and decommissioning of nuclear power plants for safety. It forms part of the Agency's programme for establishing Codes and Safety Guides relating to land based stationary thermal neutron power plants

  12. Layout of China’s Nuclear Power Plants

    Institute of Scientific and Technical Information of China (English)

    2009-01-01

    Plants in operation Qinshan Nuclear Power Plant-total installed capacity of 2.956 gigawatts The first stage started construction in March 1985, was incorporated into grids in December 1991 and began business operation in April 1994. It has an installed capacity of 300

  13. Assuring the competence of nuclear power plant contractor personnel

    International Nuclear Information System (INIS)

    This report was prepared in response to a recommendation by the IAEA International Working Group on Training and Qualification of NPP Personnel (JWG-T and Q) and supported by a number of IAEA meetings on NPP personnel training. IAEA publications on NPP training are the only international documents available to all Member States with nuclear programmes. This report complements the following IAEA publications on NPP personnel training: Technical Reports Series No. 380, Nuclear Power Plant Personnel Training and its Evaluation, A Guidebook; IAEA-TECDOC-1057, Experience in the Use of Systematic Approach to Training (SAT) for Nuclear Power Plant Personnel and IAEA-TECDOC-1063, IAEA World Survey on Nuclear Power Plant Personnel Training. This TECDOC also supplements the IAEA Safety Guide 50-SG-O1 (Rev. 1), Staffing of Nuclear Power Plants and the Recruitment Training and Authorization of Operating Personnel and Safety Standards Series No. NS-R-2, Safety of Nuclear Power Plants. Operation. Within the context of this report NPP contractors are defined as any personnel working for a nuclear power plant who are not directly employed by the nuclear power plant. Competence is the ability to perform to identified standards; it comprises skills, knowledge and attitudes and may be developed through education, experience and training. Qualification is a formal statement of achievement, resulting from an auditable assessment; if competence is assessed, the qualification becomes a formal statement of competence and may be shown on a certificate, diploma, etc. It is recognized that personnel are used to perform tasks that are of a specialised or temporary nature where it is not feasible to hire or maintain a full-time NPP employee. Accordingly, contractors may be used in a variety of situations to support NPPs. Typical situations include: supplies and services being delivered by the contractors that are subject to different quality standards based on a graded approach to assuring

  14. Changes in attitude structure toward nuclear power in the nuclear power plant locations of Tohoku district

    International Nuclear Information System (INIS)

    This survey was examined the changes in structure of attitude toward nuclear power and the influence of environmental value on the attitude structure before and after the accident at the Fukushima No. 1 nuclear power plant. With residents of Aomori, Miyagi, and Fukushima prefectures as participants, we conducted online surveys in November 2009 and October 2011. Comparing the results before and after the accident, we found that trust in the management of nuclear power plants had a stronger influence on the perceived risk and benefit regarding nuclear power after the accident than before the accident. The value of concern about environmental destruction resulted in reduced trust in the management. (author)

  15. An archaeology of nuclear power plants. Alternatives to the complete decommissioning of nuclear power plants in Germany

    Energy Technology Data Exchange (ETDEWEB)

    Egermann, Lino [Hochschule Bremen - University of Applied Sciences (Germany)

    2013-07-01

    In this paper, alternatives to the complete dismantling of the nuclear plant buildings are explored through the help of five hypothetical scenarios. The paper does not question the disadvantages or advantages of nuclear energy but instead focuses on the typological and topological particularities of this Technology.

  16. Nuclear power plant with new-generation WWER-1000 units

    International Nuclear Information System (INIS)

    The Czechoslovak nuclear industry is faced with a serious problem posed by the growing capital demands of nuclear power plants. Comparison with a number of foreign nuclear power plants revealed that the basic units of the Czechoslovak nuclear programme, WWER-1000 plants of the Zaporozhe type, have reserves in their technical design that can be utilized to reduce the capital and operating costs. This is the object of design work on a new-generation WWER-1000 type unit. The goals of the project, its organization and the extent of participation of the Czechoslovak party are described. The main target parameters of the new-generation unit (NGU) per gross output of a 1000 MWe unit, as compared with the Temelin nuclear power plant units, are as follows: concrete consumption (m3/MW) NGU/Temelin: 200/406; physical lifetime of the nuclear power plant (years): 50/30; possibility of power control: daily/weekend; area permanently occupied by the facility including cooling towers (m2/MW): 220/358; area temporarily occupied (m2/MW): 136/385; specific capital costs (CSK/MWh) 180/226. (Z.S.)

  17. Trend analysis of cables failure events at nuclear power plants

    International Nuclear Information System (INIS)

    In this study, 152 failure events related with cables at overseas nuclear power plants are selected from Nuclear Information Database, which is owned by The Institute of Nuclear Safety System, and these events are analyzed in view of occurrence, causal factor, and so on. And 15 failure events related with cables at domestic nuclear power plants are selected from Nuclear Information Archives, which is owned by JANTI, and these events are analyzed by the same manner. As a result of comparing both trends, it is revealed following; 1) A cable insulator failure rate is lower at domestic nuclear power plants than at foreign ones. It is thought that a deterioration diagnosis is performed broadly in Japan. 2) Many buried cables failure events have been occupied a significant portion of cables failure events during work activity at overseas plants, however none has been occurred at domestic plants. It is thought that sufficient survey is conducted before excavating activity in Japan. 3) A domestic age related cables failure rate in service is lower than the overseas one and domestic improper maintenance rate is higher than the overseas one. Maintenance worker' a skill improvement is expected in order to reduce improper maintenance. (author)

  18. Managing key capabilities: A challenge for nuclear plant building companies

    International Nuclear Information System (INIS)

    The nuclear plant building industry faces a paradoxical situation. The use of nuclear reactors to produce energy for civil purposes is both a promising technology, with potentially huge outlets, and a technology facing declining demand. One of the key problems is then: how to maintain the capabilities necessary to benefit from the potential recovery? The resource-based view of strategic management has shown the importance of different types of resources and capabilities in gaining a sustainable competitive advantage. Successful incumbents in the market of nuclear station building have built those kinds of distinctive capabilities that give them a competitive advantage over potential new entrants. But we show that, without a permanent activity in plant building, preserving those capabilities necessitates specific strategic action. We firstly develop the argument that the nuclear plant building industry is in a paradoxical situation in terms of demand and technical performance trends. Secondly, we try to identify the key capabilities of the incumbents. We show that companies in that field use mainly three types of distinctive capabilities: pure technical and scientific knowledge in direct relation to the use of nuclear as an energy generator, competences in risk management and competences in large project management, including financing. Thirdly, we show that although some of those capabilities are used through other nuclear-related activities such as plant maintenance or fuel supply, some of them necessitate taking strategic actions in order to be preserved. We argue that this should be a priority of nuclear equipment company managers in the next few years. (author)

  19. Population distribution analyses for nuclear power plant siting

    Energy Technology Data Exchange (ETDEWEB)

    Durfee, R.C.; Coleman, P.R.

    1983-12-01

    The Nuclear Regulatory Commission is in the process of reviewing guidelines and regulations associated with population distribution criteria around nuclear power plant sites. The purpose of this paper is to describe the methodology for calculating population distributions in the US and then evaluating specific population criteria and their effect upon the selection of future nuclear power plant sites. Through the use of computer systems, different alternatives may be evaluated for individual sites or for major regions of the country to determine their restrictiveness on siting nuclear plants. Two types of criteria were used. They involved the analysis of population distributions radially out from each possible site and the study of angular distributions around each site. Results are presented in both tabular and graphic form using national, regional, and site-level computer maps. 5 references, 39 figures, 8 tables.

  20. Appliance of software engineering in development of nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Baek, Y. W.; Kim, H. C.; Yun, C. [Chungnam National Univ., Taejon (Korea, Republic of); Kim, B. R. [KINS, Taejon (Korea, Republic of)

    1999-10-01

    Application of computer technology in nuclear power plant is also a necessary transformation as in other industry fields. But until now, application of software technology was not wide-spread because of its potential effect to safety in nuclear field. It is an urgent theme to develop evaluation guide and regulation techniques to guarantee safety, reliability and quality assurance. To meet these changes, techniques for development and operation should be enhanced to ensure the quality of software systems. In this study, we show the difference between waterfall model and software life-cycle needed in development of nuclear power plant and propose the consistent framework needed in development of instrumentation and control system of nuclear power plant.

  1. Analysis of nuclear power plant component failures

    Energy Technology Data Exchange (ETDEWEB)

    1984-01-01

    Items are shown that have caused 90% of the nuclear unit outages and/or deratings between 1971 and 1980 and the magnitude of the problem indicated by an estimate of power replacement cost when the units are out of service or derated. The funding EPRI has provided on these specific items for R and D and technology transfer in the past and the funding planned in the future (1982 to 1986) are shown. EPRI's R and D may help the utilities on only a small part of their nuclear unit outage problems. For example, refueling is the major cause for nuclear unit outages or deratings and the steam turbine is the second major cause for nuclear unit outages; however, these two items have been ranked fairly low on the EPRI priority list for R and D funding. Other items such as nuclear safety (NRC requirements), reactor general, reactor and safety valves and piping, and reactor fuel appear to be receiving more priority than is necessary as determined by analysis of nuclear unit outage causes.

  2. Provision of operational radiation protection services at nuclear power plants

    International Nuclear Information System (INIS)

    The purpose of this publication is to provide practical guidance on establishing and maintaining a radiation protection programme for a nuclear power plant that is consistent with the optimization process recommended in the Basic Safety Standards. This publication is written with a view to providing guidance to every person associated with the radiation protection programme for a nuclear power plant and develops the theme that radiation protection requires the commitment of all plant staff, including higher levels of executive management. 12 refs, 2 figs

  3. Data list of nuclear power plants in Japan

    International Nuclear Information System (INIS)

    The development of the database called PPD (Nuclear Power Plant Database) has started in 1983 at JAERI as a six-year program to provide useful information for reactor safety regulation and reactor safety research. In 1988 the program has been accomplished, and since then the data in the database has been updating and adding. Information source of the PPD is based on SAR's (Safety Analysis Report) of 47 nuclear power plants which are operating, under construction or under licensing review in Japan. The report, BWR edition, consists of lists of major data stored in the PPD, relating to safety design of 25 BWR plants in Japan. (author)

  4. Environmental management systems implemented in the Spanish nuclear power plants

    International Nuclear Information System (INIS)

    The companies that own the Spanish Nuclear Power Plants, aware of social concern and in the context of a growing demanding environmental legislation, have a permanent commitment to the electricity production based on the principles of a maximum respect for the environment, safety, quality, professionalism and continuous improvement. In order to minimize the environmental impact of their plants they have implemented and Environmental Management System based on the ISO 14001 Standard. They minimize the environmental impact by identifying the significant environmental aspects and defining the corresponding objectives. This article describes the referred environmental management systems and their environmental objectives, as applied and defined by the Spanish Nuclear Power Plants. (Author)

  5. Use of expert systems in nuclear power plants

    International Nuclear Information System (INIS)

    The application of technologies, particularly expert systems, to the control room activities in a nuclear power plant has the potential to reduce operator error and increase plant safety, reliability, and efficiency. Furthermore, there are a large number of nonoperating activities (testing, routine maintenance, outage planning, equipment diagnostics, and fuel management) in which expert systems can increase the efficiency and effectiveness of overall plant and corporate operations. This document presents a number of potential applications of expert systems in the nuclear power field. 36 refs., 2 tabs

  6. EPRI nuclear power plant groundwater protection program - 59341

    International Nuclear Information System (INIS)

    Document available in abstract form only. Full text of publication follows: The Electric Power Research Institute (EPRI) is a non-profit research organization that supports the energy industry. The Nuclear Power Plant Groundwater Protection Program conducts research related to the management of groundwater at nuclear power plant sites. Experiences at decommissioned and operating nuclear power plants show that leaks and spills from plant systems, structures, and components and work practices can lead to contamination on on-site soils and groundwater. While the levels of radioactivity resulting from such contamination events do not pose health and safety threats to the public, they have raised stakeholder concerns and, in some cases, have required remediation during decommissioning to meet site-release criteria. The EPRI Nuclear Power Plant Groundwater Protection Program provides technical support and guidance to the industry for prevention of leaks and spills, early detection of leaks and spills, monitoring of groundwater contamination, prevention of off-site migration of groundwater contamination, and remediation of groundwater and soil contamination. The EPRI Groundwater Protection Program is composed of two main objectives: 1) provide technical guidance and 2) develop advanced technologies. The cornerstones of the EPRI Groundwater Protection Program are the EPRI Groundwater Protection Guidelines for Nuclear Power Plants and the EPRI Groundwater and Soil Remediation Guidelines

  7. Nuclear magnetic response imaging of sap flow in plants

    OpenAIRE

    Windt, C.W.

    2007-01-01

    This thesis deals with Nuclear Magnetic Resonance (NMR) imaging of long distance transport in plants. Long distance transport in plants is an enigmatic process. The theoretical framework that describes its basic properties has been in place for almost a century, yet at the same time only little is known about the dynamics of long distance transport inside the living plant. The latter is caused by the fact that the two pathways in which transport takes place, the xylem and the phloem, are virt...

  8. Ultrasonic Sensors Supervision of Petrochemical and Nuclear Plant

    OpenAIRE

    Upadhyay, Vimal; Agrawal, Krishna Kant; Chand, Mukesh; Mishra, Devesh

    2013-01-01

    Piping in the oil and nuclear plants are subject to erosion or corrosion inside pipe wall. This corrosion or erosion depends on chemical aggressively of fluids, operational conditions and pipeline materials. In many cases inspection become tough when pipes are mounted several meters above the ground for a human testing personnel. Sometimes, inspection done during shut- down of plant or removal of surrounded armatures. For in service maintenance or inspection of these plants, there is always a...

  9. Development of nuclear power plant technology in Russia

    International Nuclear Information System (INIS)

    Up to its disintegration the Soviet Union was one of the leading nuclear powers in the world. This also applied to the peaceful uses of nuclear energy. The broad spectrum of developments in nuclear power plant technology is astounding. Three reactor lines were developed and built independently: the VVER pressurized water reactor line up to VVER-1000 (water-water power reactor); the graphite-moderated RBMK boiling water reactor line up to RBMK-1500 (high-power reactor with channels), and the sodium cooled fast breeder reactors up to BN-600. The associated scientific installations and the nuclear machine building industry were mainly concentrated in Russia and remained there as a core capability in nuclear power plant technology also after the end of the Soviet Union. The current lines of small, medium-sized and large reactors under development, designed for construction in Russia proper and for exports, are presented in the article. Alongside technical developments, Russia rearranged the economic capacities of her nuclear industry so as to be able to meet her objectives in building nuclear power plants in the country and abroad. The main parts of the nuclear industry are combined in the 'AtomEnergoProm' holding. (orig.)

  10. International guidelines for fire protection at nuclear installations including nuclear fuel plants, nuclear fuel stores, teaching reactors, research establishments

    International Nuclear Information System (INIS)

    The guidelines are recommended to designers, constructors, operators and insurers of nuclear fuel plants and other facilities using significant quantities of radioactive materials including research and teaching reactor installations where the reactors generally operate at less than approximately 10 MW(th). Recommendations for elementary precautions against fire risk at nuclear installations are followed by appendices on more specific topics. These cover: fire protection management and organization; precautions against loss during construction alterations and maintenance; basic fire protection for nuclear fuel plants; storage and nuclear fuel; and basic fire protection for research and training establishments. There are numerous illustrations of facilities referred to in the text. (U.K.)

  11. A primer on the Bataan Nuclear Power Plant

    International Nuclear Information System (INIS)

    This article explains in simple terms about nuclear energy, nuclear research and power reactor and its operations. It gives the historical background of the presently being constructed Philippine Nuclear Power Plant (PNPP-I) at Napot Point, Bataan. Because of rising opposition to its construction aggravated by the TMI accident, the author tries to explain and convince those against nuclear power that the reactor will be safe within reasonable risk as deduced from testimonies of experts involved in the construction and later in its operation. (author)

  12. Project Management in Nuclear Power Plant Construction: Guidelines and Experience

    International Nuclear Information System (INIS)

    Project management is a leadership function primarily concerned with the organization, coordination and control of large undertakings, with the aim of achieving technical excellence, by working to quality standards, by optimizing the schedule, the supply chain and by minimizing costs. Competent project management can reduce costs through more efficient work sequences, higher productivity, shorter activity durations and the parallel reduction of accumulated interest during construction of nuclear power plants. Based on past proven practices in Member States, this publication provides advice and guidelines to project management from the preparatory phase to plant turnover to commissioning of nuclear power plants. The guidelines and experiences will enable project managers to obtain better performance in nuclear power plant construction. (author)

  13. The Next Generation Nuclear Plant (NGNP) Project

    Energy Technology Data Exchange (ETDEWEB)

    F. H. Southworth; P. E. MacDonald

    2003-11-01

    The Next Generation Nuclear Power (NGNP) Project will demonstrate emissions-free nuclearassisted electricity and hydrogen production by 2015. The NGNP reactor will be a helium-cooled, graphite moderated, thermal neutron spectrum reactor with a design goal outlet temperature of 1000 C or higher. The reactor thermal power and core configuration will be designed to assure passive decay heat removal without fuel damage during hypothetical accidents. The fuel cycle will be a once-through very high burnup low-enriched uranium fuel cycle. This paper provides a description of the project to build the NGNP at the Idaho National Engineering and Environmental Laboratory (INEEL). The NGNP Project includes an overall reactor design activity and four major supporting activities: materials selection and qualification, NRC licensing and regulatory support, fuel development and qualification, and the hydrogen production plant. Each of these activities is discussed in the paper. All the reactor design and construction activities will be managed under the DOE’s project management system as outlined in DOE Order 413.3. The key elements of the overall project management system discussed in this paper include the client and project management organization relationship, critical decisions (CDs), acquisition strategy, and the project logic and timeline. The major activities associated with the materials program include development of a plan for managing the selection and qualification of all component materials required for the NGNP; identification of specific materials alternatives for each system component; evaluation of the needed testing, code work, and analysis required to qualify each identified material; preliminary selection of component materials; irradiation of needed sample materials; physical, mechanical, and chemical testing of unirradiated and irradiated materials; and documentation of final materials selections. The NGNP will be licensed by the NRC under 10 CFR 50 or 10

  14. 77 FR 3009 - Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Advanced Boiling Water Reactors

    Science.gov (United States)

    2012-01-20

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Advanced Boiling Water Reactors..., ``Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Advanced Boiling Water Reactors.''...

  15. Safety culture in the maintenance of nuclear power plants

    International Nuclear Information System (INIS)

    Safety culture is the complexity of beliefs, shared values and behaviour reflected in making decisions and performing work in a nuclear power plant or nuclear facility. The definition of safety culture and the related concepts presented in the IAEA literature are widely known to experts. Since the publication of Safety Culture, issued by the IAEA as INSAG-4 in 1991, the IAEA has produced a number of publications on strengthening the safety culture in organizations that operate nuclear power plants and nuclear facilities. However, until now the focus has been primarily on the area of operations. Apart from operations, maintenance in plants and nuclear facilities is an aspect that deserves special attention, as maintenance activities can have both a direct and an indirect effect on equipment reliability. Adverse safety effects can arise, depending upon the level of skill of the personnel involved, safety awareness and the complexity of the work process. Any delayed effects resulting from challenges to maintenance can cause interruptions in operation, and hence affect the safety of a plant or facility. Building upon earlier IAEA publications on this topic, this Safety Report reviews how challenges to the maintenance of nuclear power plants can affect safety culture. It also highlights indications of a weakening safety culture. The challenges described are in areas such as maintenance management; human resources management; plant condition assessment and the business environment. The steps that some Member States have taken to address safety culture aspects are detailed and singled out as good practices, with a view to disseminating and exchanging experiences and lessons learned. Although this report is primarily directed at plant maintenance organizations, the subject matter is applicable to a wider audience, including plant contracting organizations and regulatory authorities

  16. Rationalization of design and construction of buildings for nuclear power plants

    International Nuclear Information System (INIS)

    This article presents various rationalization methods introduced in the past few years for design and construction of BWR nuclear power plant buildings. When the site for a nuclear power plant has been decided, investigation is made on various aspects of possible earthquakes, based on which anti-earthquake design for the plant site is established. The next step is to examine the displacements and stresses that may occur to various parts of the bulding from a postulated earthquake. This is normally called the earthquake response analysis and consists of calculating the behaviors of the buildings using large computers. A seismic controlled structure system has recently proposed, aiming to reduce the displacements and stresses of the building itself by controlling the flexibility of the installed seismic apparatus against the input of external loads. Lately, high strength concrete and high strength reinforcing steel bars (rebars) are being considered for practical application. If advanced computers and related accessories are utilized to the maximum, it will lead not only to efficiency in the design work but to the possibility of optimized design. For rational construction, a combined scaffolding and temporary support has been devised to reduce the time and volume of required temporary work. What have been developed for rationalization of construction work also include robots for heavy weight rebar fabrication, horizontal reed blind type rebars, portable concrete distributor, all weather environment facilities, and construction materials conveyance system. (Nogami, K.)

  17. Introduction to naval nuclear propulsion plants: basic concepts and details; Introducao as instalacoes propulsoras nucleares navais: conceitos basicos e particularidades

    Energy Technology Data Exchange (ETDEWEB)

    Guimaraes, Leonam dos Santos [Centro Tecnologico da Marinha em Sao Paulo (CTMSP), SP (Brazil)

    1996-07-01

    A brief introduction to nuclear warship propulsion plants is presented, discussing some specific issues which differentiate these installations from commercial nuclear power plants. The advantages of PWR for naval propulsion applications and some general design goals are also presented. (author)

  18. Russian nuclear power plants for marine applications

    Energy Technology Data Exchange (ETDEWEB)

    Reistad, O. [Norwegian Radiation Protection Authority (Norway); Oelgaard, P.L. [Risoe National Lab. (Denmark)

    2006-04-15

    In order to establish a systematic approach for future proliferation and environmental analyses of Russia's marine nuclear reactor systems, this paper summarizes and analyzes the available open-source information on the design properties of reactor systems and nuclear fuels. The most distinctive features of Russian marine reactor development are pointed out, and similarities and differences between Russian military and civilian reactor systems and fuel are discussed. Relevant updated information on all Russian vessels using nuclear propulsion is presented in Annex I. The basic analytic division in this paper follows vessel generations first to third generation; and reactor types PWR and LMC technology. Most of the available information is related to nuclear icebreakers. This information is systematically analyzed in order to identify stages in the development of Russia's civilian naval nuclear reactors. Three different reactor models are discussed: OK-150, OK-900 and KLT-40, together with several versions of these. Concerning military reactors, it is not possible to identify characteristics for the individual reactor models, so the basic division follows vessel generations first to third generation. From the information available, however, it is possible to identify the main lines along which the design of submarines of especially the first and the second generation has been made. The conclusions contain a discussion of possible implications of the results, in addition to suggestions for further work. (au)

  19. Russian nuclear power plants for marine applications

    International Nuclear Information System (INIS)

    In order to establish a systematic approach for future proliferation and environmental analyses of Russia's marine nuclear reactor systems, this paper summarizes and analyzes the available open-source information on the design properties of reactor systems and nuclear fuels. The most distinctive features of Russian marine reactor development are pointed out, and similarities and differences between Russian military and civilian reactor systems and fuel are discussed. Relevant updated information on all Russian vessels using nuclear propulsion is presented in Annex I. The basic analytic division in this paper follows vessel generations first to third generation; and reactor types PWR and LMC technology. Most of the available information is related to nuclear icebreakers. This information is systematically analyzed in order to identify stages in the development of Russia's civilian naval nuclear reactors. Three different reactor models are discussed: OK-150, OK-900 and KLT-40, together with several versions of these. Concerning military reactors, it is not possible to identify characteristics for the individual reactor models, so the basic division follows vessel generations first to third generation. From the information available, however, it is possible to identify the main lines along which the design of submarines of especially the first and the second generation has been made. The conclusions contain a discussion of possible implications of the results, in addition to suggestions for further work. (au)

  20. Increasing reliability of nuclear energy equipment and at nuclear power plants

    International Nuclear Information System (INIS)

    The Institute of Nuclear Energy at the Technical University in Brno cooperates with nuclear power plants in increasing their reliability. The teaching programme is briefly described. The scientific research programme of the Department of Heat and Nuclear Power Energy Equipment in the field of reliability is based on a complex systematic concept securing a high level of reliability. In 1996 the Department prepared a study dealing with the evaluation of the maintenance system in a nuclear power plant. The proposed techniques make it possible to evaluate the reliability and maintenance characteristics of any individual component in a nuclear power plant, and to monitor, record and evaluate data at any given time intervals. (M.D.)

  1. Ecological impacts and damage - comparison of selected components for nuclear and conventional power plants (example of Mochovce nuclear power plant)

    International Nuclear Information System (INIS)

    A comparison is given of ecological damage for the nuclear power plant in Mochovce and a conventional power plant with the same power. Ecological effects and damage are divided into three groups: comparable damage, ecological damage caused only by conventional power plants and ecological damage caused only by nuclear power plants. In the first group the factors compared are land requisition, consumption of utility water and air consumption. In the second group are enumerated losses of crops (cereals, sugar beet, potatoes, oleaginous plants) and losses caused by increased disease rate owing to polluted environment by conventional power plants. In the third group health hazards are assessed linked with ionizing radiation. Also considered are vent stack escapes. (E.S.)

  2. Nuclear plant operation: achieving excellence through quality

    International Nuclear Information System (INIS)

    Nuclear power operation is characterised by a very high level of safety and availability resulting in economically competitive electricity production. This achievement must not only be maintained but must be further developed if nuclear power is to regain momentum in the light of its widely recognized environmental advantages. Therefore this meeting bring together all those, managers and technical staff, responsible for the operation of the nuclear in order to allow them to exchange views, experience and knowledge on fundamental aspects such as: management philosophy, quality assurance, human resources and international co-operation; focusing on training (incident analysis and management), human factors and experience feedback; maintenance philosophy, life extension and upgrading, organisation and administration. (A.L.B.)

  3. Nuclear plant operation: achieving excellence through quality

    Energy Technology Data Exchange (ETDEWEB)

    Bergstrom, L. [Barseback Nuclear Power Plant (Sweden); Bergeron, J.P. [Electricite de France (EDF), 75 - Paris (France); Coakley, W. [and others

    1992-07-01

    Nuclear power operation is characterised by a very high level of safety and availability resulting in economically competitive electricity production. This achievement must not only be maintained but must be further developed if nuclear power is to regain momentum in the light of its widely recognized environmental advantages. Therefore this meeting bring together all those, managers and technical staff, responsible for the operation of the nuclear in order to allow them to exchange views, experience and knowledge on fundamental aspects such as: management philosophy, quality assurance, human resources and international co-operation; focusing on training (incident analysis and management), human factors and experience feedback; maintenance philosophy, life extension and upgrading, organisation and administration. (A.L.B.)

  4. Safety assessment and verification for nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    This Safety Guide was prepared under the IAEA programme for safety standards for nuclear power plants. The present publication is a revision of the IAEA Safety Guide on Management of Nuclear Power Plants for Safe Operation issued in 1984. It supplements Section 2 of the Safety Requirements publication on Safety of Nuclear Power Plants: Operation. Nuclear power technology is different from the customary technology of power generation from fossil fuel and by hydroelectric means. One major difference between the management of nuclear power plants and that of conventional generating plants is the emphasis that should be placed on nuclear safety, quality assurance, the management of radioactive waste and radiological protection, and the accompanying national regulatory requirements. This Safety Guide highlights the important elements of effective management in relation to these aspects of safety. The attention to be paid to safety requires that the management recognize that personnel involved in the nuclear power programme should understand, respond effectively to, and continuously search for ways to enhance safety in the light of any additional requirements socially and legally demanded of nuclear energy. This will help to ensure that safety policies that result in the safe operation of nuclear power plants are implemented and that margins of safety are always maintained. The structure of the organization, management standards and administrative controls should be such that there is a high degree of assurance that safety policies and decisions are implemented, safety is continuously enhanced and a strong safety culture is promoted and supported. The objective of this publication is to guide Member States in setting up an operating organization which facilitates the safe operation of nuclear power plants to a high level internationally. The second objective is to provide guidance on the most important organizational elements in order to contribute to a strong safety

  5. The operating organization for nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    This Safety Guide was prepared under the IAEA programme for safety standards for nuclear power plants. The present publication is a revision of the IAEA Safety Guide on Management of Nuclear Power Plants for Safe Operation issued in 1984. It supplements Section 2 of the Safety Requirements publication on Safety of Nuclear Power Plants: Operation. Nuclear power technology is different from the customary technology of power generation from fossil fuel and by hydroelectric means. One major difference between the management of nuclear power plants and that of conventional generating plants is the emphasis that should be placed on nuclear safety, quality assurance, the management of radioactive waste and radiological protection, and the accompanying national regulatory requirements. This Safety Guide highlights the important elements of effective management in relation to these aspects of safety. The attention to be paid to safety requires that the management recognize that personnel involved in the nuclear power programme should understand, respond effectively to, and continuously search for ways to enhance safety in the light of any additional requirements socially and legally demanded of nuclear energy. This will help to ensure that safety policies that result in the safe operation of nuclear power plants are implemented and that margins of safety are always maintained. The structure of the organization, management standards and administrative controls should be such that there is a high degree of assurance that safety policies and decisions are implemented, safety is continuously enhanced and a strong safety culture is promoted and supported. The objective of this publication is to guide Member States in setting up an operating organization which facilitates the safe operation of nuclear power plants to a high level internationally. The second objective is to provide guidance on the most important organizational elements in order to contribute to a strong safety

  6. Design and construction of nuclear power plants

    CERN Document Server

    Schnell, Jürgen; Meiswinkel, Rüdiger; Bergmeister, Konrad; Fingerloos, Frank; Wörner, Johann-Dietrich

    2013-01-01

    Despite all the efforts being put into expanding renewable energy sources, large-scale power stations will be essential as part of a reliable energy supply strategy for a longer period. Given that they are low on CO2 emissions, many countries are moving into or expanding nuclear energy to cover their baseload supply.Building structures required for nuclear installations whose protective function means they are classified as safety-related, have to meet particular construction requirements more stringent than those involved in conventional construction. This book gives a comprehensive overv

  7. Essays on the economics of licensing nuclear power plants

    International Nuclear Information System (INIS)

    Regulation and licensing of nuclear power plants by the United States Atomic Energy Commission and the United States Nuclear Regulatory Commission are discussed. Chapter 1 overviews the licensing process and issues raised in licensing cases. Based on a sample of plants licensed between 1967 and 1978, a statistical study of the impact of public participation in licensing is performed. The study concludes that public participation has had a major impact on licensing and power-plant costs. The impact is due to a fundamental weakness of the Commissions: their inability to resolve certain issues related to acceptable social risk. The study has important policy implications for reforming the Federal licensing process. Chapter 2 contains an analysis of the Price-Anderson Act, a Federal program for compensating victims of large nuclear accidents. The Price-Anderson Act is placed within the context of generalized federal disaster relief. A model is developed that allows an evaluation programs on the basis of moral hazard and equity principles. Chapter 3 analyzes the Nuclear Regulatory Commission's treatment of its mandatory antitrust review of applicants for nuclear power plants. The main conclusion of the chapter is that the reviews have not addressed the central economic issues of antitrust that are relevant to nuclear power. Instead, the reviews contribute to further cartelization of the electric utility industry. While politically expedient, the reviews are counter-productive to the development of an optimal industry structure

  8. Survey on product properties of bituminized waste concentrates from reprocessing, nuclear installations and nuclear power plants

    International Nuclear Information System (INIS)

    This report contains a brief survey on the product properties after solidification with bitumen of waste concentrates from reprocessing plants, nuclear research installations and nuclear power plants. The leach behaviour of bitumen products in water and saturated salt solutions is described as well as the radiolytic and thermal stability of the products. The reports also contain some data on sedimentation of salts fixed in bitumen. (orig.)

  9. Talks on nuclear plant break down

    Index Scriptorium Estoniae

    2007-01-01

    Kasvavad probleemid Leedu tuumaelektrijaama projektiga. Läbirääkimistest Leedu valitsuse ja NDX Energija vahel. DnB Nord Bankas nimetas projekti liiga riskantseks ja kulukaks. Lisa: Eesti Energia board member suggests plant for Estonia

  10. US nuclear power plant operating cost and experience summaries

    International Nuclear Information System (INIS)

    NUREG/CR-6577, U.S. Nuclear Power Plant Operating Cost and Experience Summaries, has been prepared to provide historical operating cost and experience information on U.S. commercial nuclear power plants. Cost incurred after initial construction are characterized as annual production costs, representing fuel and plant operating and maintenance expenses, and capital expenditures related to facility additions/modifications which are included in the plant capital asset base. As discussed in the report, annual data for these two cost categories were obtained from publicly available reports and must be accepted as having different degrees of accuracy and completeness. Treatment of inconclusive and incomplete data is discussed. As an aid to understanding the fluctuations in the cost histories, operating summaries for each nuclear unit are provided. The intent of these summaries is to identify important operating events; refueling, major maintenance, and other significant outages; operating milestones; and significant licensing or enforcement actions. Information used in the summaries is condensed from annual operating reports submitted by the licensees, plant histories contained in Nuclear Power Experience, trade press articles, and the Nuclear Regulatory Commission (NRC) web site (www.nrc.gov)

  11. Feedback of operational safety experience from nuclear power plants

    International Nuclear Information System (INIS)

    The IAEA and the Nuclear Energy Agency of the OECD jointly organized this Symposium, on the Feedback of Operational Safety Experience from Nuclear Power Plants, which was held in Paris from 16 to 20 May 1988. The purpose of the Symposium was to provide a forum for the detailed exchange of experience and to discuss various ways of closing the feedback loop, with the ultimate goal of enhancing the level of operational safety at nuclear power plants. Participants at the Symposium dealt with many of the essential aspects of the optimization of plant operational safety. The Symposium was attended by 167 participants from 28 Member States and 4 international organizations. Fifty-nine papers were presented and discussed during four scientific sessions. Additional sessions were devoted to a Panel Discussion by a group of senior experts on future trends in the efforts to improve the operational safety of nuclear power plants and the presentation of a statement summarizing the Symposium. These Proceedings include the full texts of the papers presented during the sessions and the Panel Discussion, and of the summary of the Symposium. The presentations were subdivided into 4 sessions: Methods of identification of operational safety issues in Nuclear Power Plants (12 papers); Methods of analysis of operational safety issues (16 papers); Corrective actions implemented as a result of operating experience (15 papers); Operational safety experience feedback systems (15 papers). A separate abstract was prepared for each of these papers. Refs, figs and tabs

  12. US nuclear power plant operating cost and experience summaries

    Energy Technology Data Exchange (ETDEWEB)

    Kohn, W.E.; Reid, R.L.; White, V.S.

    1998-02-01

    NUREG/CR-6577, U.S. Nuclear Power Plant Operating Cost and Experience Summaries, has been prepared to provide historical operating cost and experience information on U.S. commercial nuclear power plants. Cost incurred after initial construction are characterized as annual production costs, representing fuel and plant operating and maintenance expenses, and capital expenditures related to facility additions/modifications which are included in the plant capital asset base. As discussed in the report, annual data for these two cost categories were obtained from publicly available reports and must be accepted as having different degrees of accuracy and completeness. Treatment of inconclusive and incomplete data is discussed. As an aid to understanding the fluctuations in the cost histories, operating summaries for each nuclear unit are provided. The intent of these summaries is to identify important operating events; refueling, major maintenance, and other significant outages; operating milestones; and significant licensing or enforcement actions. Information used in the summaries is condensed from annual operating reports submitted by the licensees, plant histories contained in Nuclear Power Experience, trade press articles, and the Nuclear Regulatory Commission (NRC) web site (www.nrc.gov).

  13. Experience in operation of nuclear power plant

    International Nuclear Information System (INIS)

    Following a brief description of the structure, financing and generating plant of Sydkraft, the Barsebaeck plant is briefly described. The construction schedule and personnel are outlinrd as are the investment and operating costs, which are compared with the utility's oil-fired generating costs. The causes of outages are briefly presented and discussed. The wastes from generating the same amount of power as Barsebaeck in 1977 using oil fuel are compared with the radioactive waste for that year. (JIW)

  14. Meteorological measurements at nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-31

    On-site meteorological measurements are necessary for evaluating atmospheric dispersion of gaseous effluents. Radiation doses in a plant`s vicinity due to these effluents are calculated from the results of dispersion evaluations. The guide addresses the requirements for on-site meteorological measurement systems. Guide YVL 7.3 addresses atmospheric dispersion evaluations and calculation methods, Guide YVL 7.2 radiation dose calculations and Guide YVL 7.8 environmental data reporting. (5 refs.).

  15. Nuclear Power Plant Life Management. Proceedings of An International Symposium

    International Nuclear Information System (INIS)

    The original design life of a nuclear power plant (NPP) is commonly around 30-40 years, depending on manufacture and type. However, the actual operational life may be shorter, or longer, based on many factors. Plant life management (PLiM) is a methodology that is appropriate for any length of plant operational life. The proceedings of this symposium reflect the growing interest of Member States in this topic and summarize the conclusions of six major programmatic sessions: approaches to plant life management; economics; ageing management and related operational programmes; system, structure and component design modification, modernization, refurbishment and replacement; managerial issues; and regulatory issues. This publication provides operators and regulators with a comprehensive overview of the state of the science and technology involved in the main issues concerning safe, long term operation, ageing management and the basic economic aspects of plant life management for the nuclear power industry. (author)

  16. Supervisory monitoring system in nuclear power plants

    International Nuclear Information System (INIS)

    Monitoring of a power plant is one of the essential tasks during operation and the computer-based implementations are nowadays seemingly quite mature. However, presently these are still not satisfactory enough to meet the high standards to the licensing requirements and they are mostly not truly integrated to the plant's design-based monitoring system. This is basically due to the robustness problem as the majority of the methods are not robust enough for the monitoring of the safety parameter set in a plant or intelligent supervision. Therefore, a supervisory monitoring system (SMS) in a plant is necessary to supervise the monitoring tasks: determining the objectives to be obtained and finding the means to support them. SMS deals with the changing plant status and the coordination of the information flow among the monitoring subunits. By means of these robustness and consistency in monitoring is achieved. The paper will give the guidelines of knowledge and data management techniques in a framework of robust comprehensive and coordinated monitoring which is presented as supervisory monitoring. Such a high level monitoring serves for consistent and immediate actions in fault situations while this particularly has vital importance in preventing imminent severe accidents next to the issues of recognition of the monitoring procedures for licensing and enhanced plant safety. (author). 8 refs, 5 figs

  17. Chinese Public Willingness to Pay to Avoid Having Nuclear Power Plants in the Neighborhood

    OpenAIRE

    Chuanwang Sun; Nan Lyu; Xiaoling Ouyang

    2014-01-01

    In spite of the decreasing share of nuclear power all over the world, China resumed the approval of large-scale construction of nuclear power plants in 2012. However, influenced by the worldwide spreading anti-nuclear attitudes, people who live near nuclear power plants showed increasing concerns about nuclear risks. Consequently, the Not In My Backyard (NIMBY) syndrome of nuclear power plants should be evaluated prudently to support the healthy development of nuclear power in China. Based on...

  18. Activities of Brazilian Nuclear Energy Commission in the field of nuclear power plant licesing

    International Nuclear Information System (INIS)

    The objectives, the procedures and the ways of implementation of measures aiming at safety use of nuclear energy are presented. The juridical aspects in the licensing area and the regulatory activities used by CNEN. The description of nuclear power plants and the methodology used in studies of environmental protection and radiation protection are presented

  19. Tornado-resistance design for the nuclear safety structure of Qinshan Nuclear Power Plant

    International Nuclear Information System (INIS)

    The primary design consideration of anti-tornado of the nuclear safety structure of Qinshan Nuclear Power Plant is briefly presented. It mainly includes estimating the probability of tornado arising in the site, ascertaining the design requirments of the anti-tornado structures and deciding the tornado load acted on the structures

  20. International Nuclear Technology Forum: Future prospects of nuclear power plants and Turkey

    International Nuclear Information System (INIS)

    The document includes 19 papers presented at the 'International Nuclear Technology Forum: Future Prospects of Nuclear Power Plants in Turkey', held between 12-15 October 1993 in Ankara (Turkey). A separate abstract was prepared for each paper prepared for each paper

  1. Stainless steel forgings for nuclear chemical plants

    International Nuclear Information System (INIS)

    This Specification covers detailed requirements for the supply of austenitic stainless steel forgings used in radioactive and corrosive areas within the Nuclear Industry. With the exception of 316S51 the materials specified are all suitable for contact with nitric acid, 316S51 being included as suitable for use in contact with sodium and other alkali metals at elevated temperatures. (author)

  2. Automatic control of nuclear power plants

    International Nuclear Information System (INIS)

    The fundamental concepts in automatic control are surveyed, and the purpose of the automatic control of pressurized water reactors is given. The response characteristics for the main components are then studied and block diagrams are given for the main control loops (turbine, steam generator, and nuclear reactors)

  3. Evaluating and improving nuclear power plant operating performance

    International Nuclear Information System (INIS)

    This report aims to provide the basis for improvements in the understanding of nuclear power plants operation and ideas for improving future productivity. The purpose of the project was to identify good practices of operating performance at a few of the world's most productive plants. This report was prepared through a series of consultants meetings, a specialists meeting and an Advisory Group meeting with participation of experts from 23 Member States. The report is based on self-assessment of half a dozen plants that have been chosen as representatives of different reactor types in as many different countries, and the views and assessment of the participants on good practices influencing plant performance. Three main areas that influence nuclear power plant availability and reliability were identified in the discussions: (1) management practices, (2) personnel characteristics, and (3) working practices. These areas cover causes influencing plant performance under plant management control. In each area the report describes factors or good practices that positively influence plant availability. The case studies, presented in annexes, contain the plant self-assessment of areas that influence their availability and reliability. Six plants are represented in the case studies: (1) Dukovany (WWER, 1760 MW) in the Czech Republic; (2) Blayais (PWR, 3640 MW) in France; (3) Paks (WWER, 1840 MW) in Hungary; (4) Wolsong 1 (PHWR, 600 MW) in the Republic of Korea; (5) Trillo 1 (PWR, 1066 MW) in Spain; and (6) Limerick (BWR, 2220 MW) in the United States of America

  4. Reliability methods in nuclear power plant ageing management

    Energy Technology Data Exchange (ETDEWEB)

    Simola, K. [VTT Automation, Espoo (Finland). Industrial Automation

    1999-07-01

    The aim of nuclear power plant ageing management is to maintain an adequate safety level throughout the lifetime of the plant. In ageing studies, the reliability of components, systems and structures is evaluated taking into account the possible time-dependent degradation. The phases of ageing analyses are generally the identification of critical components, identification and evaluation of ageing effects, and development of mitigation methods. This thesis focuses on the use of reliability methods and analyses of plant- specific operating experience in nuclear power plant ageing studies. The presented applications and method development have been related to nuclear power plants, but many of the approaches can also be applied outside the nuclear industry. The thesis consists of a summary and seven publications. The summary provides an overview of ageing management and discusses the role of reliability methods in ageing analyses. In the publications, practical applications and method development are described in more detail. The application areas at component and system level are motor-operated valves and protection automation systems, for which experience-based ageing analyses have been demonstrated. Furthermore, Bayesian ageing models for repairable components have been developed, and the management of ageing by improving maintenance practices is discussed. Recommendations for improvement of plant information management in order to facilitate ageing analyses are also given. The evaluation and mitigation of ageing effects on structural components is addressed by promoting the use of probabilistic modelling of crack growth, and developing models for evaluation of the reliability of inspection results. (orig.)

  5. Reliability methods in nuclear power plant ageing management

    International Nuclear Information System (INIS)

    The aim of nuclear power plant ageing management is to maintain an adequate safety level throughout the lifetime of the plant. In ageing studies, the reliability of components, systems and structures is evaluated taking into account the possible time-dependent degradation. The phases of ageing analyses are generally the identification of critical components, identification and evaluation of ageing effects, and development of mitigation methods. This thesis focuses on the use of reliability methods and analyses of plant- specific operating experience in nuclear power plant ageing studies. The presented applications and method development have been related to nuclear power plants, but many of the approaches can also be applied outside the nuclear industry. The thesis consists of a summary and seven publications. The summary provides an overview of ageing management and discusses the role of reliability methods in ageing analyses. In the publications, practical applications and method development are described in more detail. The application areas at component and system level are motor-operated valves and protection automation systems, for which experience-based ageing analyses have been demonstrated. Furthermore, Bayesian ageing models for repairable components have been developed, and the management of ageing by improving maintenance practices is discussed. Recommendations for improvement of plant information management in order to facilitate ageing analyses are also given. The evaluation and mitigation of ageing effects on structural components is addressed by promoting the use of probabilistic modelling of crack growth, and developing models for evaluation of the reliability of inspection results. (orig.)

  6. Evaluation of seismic hazards for nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    The main objective of this Safety Guide is to provide recommendations on how to determine the ground motion hazards for a plant at a particular site and the potential for surface faulting, which could affect the feasibility of construction and safe operation of a plant at that site. The guidelines and procedures presented in this Safety Guide can appropriately be used in evaluations of site suitability and seismic hazards for nuclear power plants in any seismotectonic environment. The probabilistic seismic hazard analysis recommended in this Safety Guide also addresses the needs for seismic hazard analysis of external event PSAs conducted for nuclear power plants. Many of the methods and processes described may also be applicable to nuclear facilities other than power plants. Other phenomena of permanent ground displacement (liquefaction, slope instability, subsidence and collapse) as well as the topic of seismically induced flooding are treated in Safety Guides relating to foundation safety and coastal flooding. Recommendations of a general nature are given in Section 2. Section 3 discusses the acquisition of a database containing the information needed to evaluate and address all hazards associated with earthquakes. Section 4 covers the use of this database for construction of a seismotectonic model. Sections 5 and 6 review ground motion hazards and evaluations of the potential for surface faulting, respectively. Section 7 addresses quality assurance in the evaluation of seismic hazards for nuclear power plants

  7. The nuclear safety account and the Chernobyl nuclear power plant

    International Nuclear Information System (INIS)

    In 1993, the G-7 officially proposed that the European Bank for Reconstruction and Development set up the Nuclear Safety Account (NSA) and act as the Account's secretariat. The Bank's Board of Directors approved this proposal and the Rules of the NSA on 22 March 1993 and the NSA became effective on 14 April 1993. The NSA finances, through grants, operational and near-term technical safety improvements for Soviet-designed nuclear reactors in the countries of the former Soviet Union, central and eastern Europe. Priority is given to those reactors which present the highest level of risk that can be significantly reduced by short-term and cost-effective safety improvements, and which are necessary to ensure the continuing electricity supply in the region. Efforts are therefore focused on WWER 440/230 and RBMK types of reactors and on the purchase of equipment as opposed to studies, which a number of donors already fund. Finance from the NSA is not used to extend the operating lifetime of unsafe reactors

  8. New technologies of information treatment in the ERP of the Almaraz and Trillo nuclear power plants; Nuevas tecnologias de tratamiento de la informacion en el ERP de las centrales nucleares de Almaraz y Trillo

    Energy Technology Data Exchange (ETDEWEB)

    Martin Lopez-Suevos, C.; Gonzalez Crego, E.

    2013-03-01

    The Almaraz and Trillo Nuclear Power Plants are equipped with an Integrated Operation Management System (SIGE), which covers practically all of their transactional and management needs in all areas, with the exception of some specific engineering and simulation tools. In recent years, applications based on new computer technologies have been developed and integrated into the SIGE, including a Maintenance Dashboard, an Admissions Office ant the use of bar code readers, all of which are described in this article. (Author)

  9. Plant succession after hydrologic disturbance: Inferences from contemporary vegetation on a chronosequence of bars, Willamette River, Oregon, USA

    Science.gov (United States)

    Historic unconstrained, unregulated streamflow along the upper mainstem of the Willamette River, Oregon, produced a floodplain of coalescent bars supporting a mosaic of vegetation patches. We sampled the contemporary vegetation of 42 bars formed 3 to 64 + years ago in four, 1 km...

  10. Ways to improvements in nuclear plant operators' training and assessment

    International Nuclear Information System (INIS)

    Some results and findings of the research project of the Ministry of Industry and Trade No. 2A-3TP1/144 'Research into management tools and methods for increasing the reliability of the human factors in the operation of nuclear power plants', addressed in collaboration with the Nuclear Research Institute, are presented. The article highlights the gaps in the training of nuclear power plant control room operators in the field of the purely human aspects of the work of operators, reactor unit managers, shift engineers and shift masters, such as mutual communication, management of briefings/debriefings, joint decision making, expression of one's own perception of a situation, warning of impending danger, and so on (Non-Technical Skills, or Crew Resource Management (CRM)). Some important suggestions for the development and implementation of training and assessment of the latest generation of CRM in the nuclear power industry are put forward. (orig.)

  11. Regulatory practices for nuclear power plants in India

    Indian Academy of Sciences (India)

    S S Bajaj

    2013-10-01

    The Atomic Energy Regulatory Board (AERB) is the national authority for ensuring that the use of ionizing radiation and nuclear energy does not cause any undue risk to the health of workers, members of the public and to the environment. AERB is responsible for the stipulation and enforcement of rules and regulations pertaining to nuclear and radiological safety. This paper describes the regulatory process followed by AERB for ensuring the safety of nuclear power plants (NPPs) during their construction as well as operation. This regulatory process has been continuously evolving to cater to the new developments in reactor technology. Some of the recent initiatives taken by AERB in this direction are briefly described. Today, AERB faces new challenges like simultaneous review of a large number of new projects of diverse designs, a fast growing nuclear power program and functioning of operating plants in a competitive environment. This paper delineates how AERB is gearing up to meet these challenges in an effective manner.

  12. The marketing concept of nuclear power plant constructors

    International Nuclear Information System (INIS)

    The paper examines the largely non-investigated area of marketing theory and energy sciences. The author considers the structure of the nuclear power industry and of marketing, analyses the nuclear power station market and its factors of influence, and gives a market forecast. The marketing concept requires especially a typologization of the investment good nuclear power plant. Project-dependent and project-independent marketing activities are coordinated in a marketing programme, and are integrated into mixed marketing efforts. Problems result from insecurity related to the further development of political, social and economic factors of influence. Constructors of nuclear power plants in the Federal Republic of Germany have to adapt to this insecurity and to face risks presented by entrepreneurial activities and the environment by means of flexible planning. (HSCH)

  13. Regulatory practices for nuclear power plants in India

    International Nuclear Information System (INIS)

    The Atomic Energy Regulatory Board (AERB) is the national authority for ensuring that the use of ionizing radiation and nuclear energy does not cause any undue risk to the health of workers, members of the public and to the environment. AERB is responsible for the stipulation and enforcement of rules and regulations pertaining to nuclear and radiological safety. This paper describes the regulatory process followed by AERB for ensuring the safety of nuclear power plants (NPPs) during their construction as well as operation. This regulatory process has been continuously evolving to cater to the new developments in reactor technology. Some of the recent initiatives taken by AERB in this direction are briefly described. Today, AERB faces new challenges like simultaneous review of a large number of new projects of diverse designs, a fast growing nuclear power program and functioning of operating plants in a competitive environment. This paper delineates how AERB is gearing up to meet these challenges in an effective manner. (author)

  14. Study on evaluation system for Chinese nuclear power plants

    Institute of Scientific and Technical Information of China (English)

    LI Song-bai; CHENG Jian-xiu

    2006-01-01

    This paper analyzes the meaning, structure, function and assessment methods of a nuclear power plant evaluation system, and the similarities and differences among various assessment methods. Based on this research an integrated and detailed suggestion is proposed on how to establish and improve internal and external evaluation systems for Chinese NPPs. It includes: to prepare and implement the nuclear power plant operational management program, to build an integrated performance indicator system, to improve the present audit system and conduct the comprehensive evaluation system, to set up and implement the integrated corrective action system, to position precisely the status of operation assessment of nuclear power plants, to conduct the assessment activities on constructing NPP, to initiate the specific assessment in some important areas, to establish industry performance indicator system, to improve the assessment methods, to share the assessment results, to select,cultivate and certify the reviewers, and to enhance international communication and cooperation.

  15. Development of third Qinshan nuclear power plant risk monitor

    International Nuclear Information System (INIS)

    A risk monitor, an integrated risk analysis tool for real-time monitoring, was widely used in the management of nuclear power plants around the world. A risk monitor prototype system, named RiskAngel, has been developed by FDS Team, China, in which the fault tree analysis engine RiskA was integrated. Based on these, Third Qinshan nuclear power plant Risk Monitor (TQRM) has been developed considering the safety characteristics and the management process of Third Qinshan nuclear power plant. The status and development trend of risk monitor were given in this paper. An overview of the architecture and functions of TQRM was introduced. The key algorithms and technical features were also presented. (authors)

  16. Planning and architectural safety considerations in designing nuclear power plants

    International Nuclear Information System (INIS)

    To achieve optimum safety and to avoid possible hazards in nuclear power plants, considering architectural design fundamentals and all operating precautions is mandatory. There are some planning and architectural precautions should be considered to achieve a high quality design and construction of nuclear power plant with optimum safety. This paper highlights predicted hazards like fire, terrorism, aircraft crash attacks, adversaries, intruders, and earthquakes, proposing protective actions against these hazards that vary from preventing danger to evacuating and sheltering people in-place. For instance; using safeguards program to protect against sabotage, theft, and diversion. Also, site and building well design focusing on escape pathways, emergency exits, and evacuation zones, and the safety procedures such as; evacuation exercises and sheltering processes according to different emergency classifications. In addition, this paper mentions some important codes and regulations that control nuclear power plants design, and assessment methods that evaluate probable risks. (author)

  17. Operational experience, availability and reliability of nuclear power plants

    International Nuclear Information System (INIS)

    This lecture - presents a survey on nuclear power production and plant performance in the Western World covering all reactor types and light-water reactors in particular and discusses key parameters such as load factors and non-availability analysis. - outlines the main reasons for the reliable performance of Swiss nuclear power plants - quality equipment - operator qualification and training - engineering know how on site - maintenance philosophy and outage planning - information system and feedback of experience - explains the management functions as applied at the Beznau Nuclear Power Station to ensure high power productivity and reliability - improvement - a feedback control system - analysis of production losses - optimization in shut-down planning - minimizing disturbances during plant operation - optimizing personnel qualification and efficiency. (orig.)

  18. Laser technologies for the nuclear power plant maintenance

    International Nuclear Information System (INIS)

    The recent improvement of laser technologies will contribute to the maintenance of nuclear power plants. The Japan Atomic Energy Agency developed a specially designed probing system was developed to inspect and repair the cracks of the welded beads of the heat exchanger tubes of nuclear power plants. Eddy current testing detected inner wall cracks in heat exchanger tubes. The tubes thickness was 4.5 mm and the inner diameter was 23 mm. The minimum detectable depth of the cracks was 10% of the tube thickness. Endoscope observation confirmed the cracks along the welded beads. Laser welding by a 300 W compact fiber laser successfully repaired them. The probing system will operate in new nuclear power plants with various laser monitoring technologies for coolant pipes. (author)

  19. Bid Preparation and Evaluation for Nuclear Power Plant Project Management

    International Nuclear Information System (INIS)

    Bid preparation and evaluation is one of the main activities in Nuclear Power Plant Project management. International Atomic Energy Agency guide and Korean experience was studied for Malaysian requirement in realization of first Nuclear Power Plant. Several aspects shall be taken into consideration such as political scenario, financial capabilities, sitting, human resource, technologies, fuel supplies and decommissioning for long term exceeded hundred years. Bidding process and activities is proposed for our country requirement. The main activities included but unlimited to Bid Invitation Specification, Bid Evaluation Process, Technical Evaluation, Economic Bid Evaluation and Contracting. On the end of day, Malaysia need safe and reliable Nuclear Power Plant. Malaysian Economic Transformation Programme also get benefit from spin-off localization products and services as well as Technology Transfer Programme. (author)

  20. mobile nuclear energy power plants for Turkey and III. world

    International Nuclear Information System (INIS)

    It is estimated that if there is no alternative energy source, there will be increase in building nuclear energy power plants. This source of energy and know how along with technology must be put into the possession of Turkey. Since almost all of Turkey is 1 st degree earthquake region and in view of the regional political instability, the requirement of ample amount of water for prolonged times, the density of settlement, environmental problems, high cost of building nuclear energy power plants it becomes necessary to think about their application techniques. In this study, mobile nuclear energy power plants having a wide area of use in conditions prevailing in Turkey , their draft drawings for making them by using metal/steel are shown. The positive-negative aspects of the topic is presented for discussions

  1. Human factors engineering plan for reviewing nuclear plant modernization programs

    Energy Technology Data Exchange (ETDEWEB)

    O' Hara, John; Higgins, James [Brookhaven National Laboratory, Upton, NY (United States)

    2004-12-01

    The Swedish Nuclear Power Inspectorate reviews the human factors engineering (HFE) aspects of nuclear power plants (NPPs) involved in the modernization of the plant systems and control rooms. The purpose of a HFE review is to help ensure personnel and public safety by verifying that accepted HFE practices and guidelines are incorporated into the program and nuclear power plant design. Such a review helps to ensure the HFE aspects of an NPP are developed, designed, and evaluated on the basis of a structured top-down system analysis using accepted HFE principles. The review addresses eleven HFE elements: HFE Program Management, Operating Experience Review, Functional Requirements Analysis and Allocation, Task Analysis, Staffing, Human Reliability Analysis, Human-System Interface Design, Procedure Development, Training Program Development, Human Factors Verification and Validation, and Design Implementation.

  2. The site of a nuclear power plant and environmental safety

    International Nuclear Information System (INIS)

    The purpose of this report is to give the reader a general view of the things associated with the site of a nuclear power plant. In this context the effect of a nuclear power plant and site on environmental safety is considered. Planning, construction and operating a nuclear power plant require several judgements and licenses based on different laws. The location of the planned nuclear facility project and environmental conditions contribute in great detail to the compliance arguments of permits. At first the environmental impacts of the siting project and its alternatives shall be investigated in the Environmental Impact Assessment procedure. Then the decision in principle according to the Nuclear Energy Act can be applied from the Council of State, the decision shall further be confirmed by Parliament. When the decision in principle is considered the overall good of society shall be assessed by means of considering i.a. site alternatives and safety. The safety related basic principle is that operation of a nuclear power plant may not cause danger to the environment, public or property. After the affirmative principle approval the construction license and later on the operation license can be applied from the Council of State, these licenses need to be supported i.a. by building and environmental licenses of separate authorities. Also some international contracts concern realisation of a nuclear power plant siting. The nuclear power plant site shall be suitable for the needs of the electricity production and the transmission system and it shall be technically appropriate for building and operation of a power plant. The site shall be safe enough on the other hand from the view of external events threatening the power plant - although one can be partly prepared for these things in the design of the plant - and on the other hand from the point of public safety. Requirements for the safety of the site are directed in the decision of the Council of State's general

  3. Radioactive materials released from nuclear power plants

    International Nuclear Information System (INIS)

    Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1987 have been compiled and reported. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1987 release data are summarized in tabular form. Data covering specific radionuclides are summarized. 16 tabs

  4. Management of radioactive waste nuclear power plants

    International Nuclear Information System (INIS)

    The authors give a survey of the sources, types and amounts of radioactive waste in LWR nuclear power stations (1,300 MWe). The amount of solid waste produced by a Novovorenezh-type PWR reactor (2 x 400 resp. 1 x 1,000 MWe) is given in a table. Treatment, solidification and final storage of radioactive waste are shortly discussed with special reference to the problems of final storage in the CSR. (HR)

  5. Radioactive materials released from nuclear power plants

    International Nuclear Information System (INIS)

    Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1991 have been compiled and reported. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1991 release data are summarized in tabular form. Data Covering specific radionuclides are summarized

  6. Project management skills for nuclear power plants

    International Nuclear Information System (INIS)

    Full text: The E and C Division of L and T has executed several power projects in India and abroad and thus possesses the requisite wherewithal to execute nuclear power projects on a fast track basis. To achieve this L and T has set up a separate Strategic Business Unit (SBU) to have a focused attention to the nuclear power industry in the country. All the four important and necessary hallmarks for successful implementation of any project namely (i) engineering capabilities, (ii) sophisticated project management tools, (iii) ability to mobilize resources, and (iv) skilled personnel to execute the project have been adequately addressed. These could be realized either by establishing fruitful collaborations with other specialist Companies and/or creating powerful and multitasking software tools for effective implementation. The execution of nuclear power projects on a fast track basis could be implemented by following the EPC route and by minimizing the number of packages. Details of this scheme for project implementation will be highlighted during the talk

  7. Heterogonous Nanofluids for Nuclear Power Plants

    Science.gov (United States)

    Alammar, Khalid

    2014-09-01

    Nuclear reactions can be associated with high heat energy release. Extracting such energy efficiently requires the use of high-rate heat exchangers. Conventional heat transfer fluids, such as water and oils are limited in their thermal conductivity, and hence nanofluids have been introduced lately to overcome such limitation. By suspending metal nanoparticles with high thermal conductivity in conventional heat transfer fluids, thermal conductivity of the resulting homogeneous nanofluid is increased. Heterogeneous nanofluids offer yet more potential for heat transfer enhancement. By stratifying nanoparticles within the boundary layer, thermal conductivity is increased where temperature gradients are highest, thereby increasing overall heat transfer of a flowing fluid. In order to test the merit of this novel technique, a numerical study of a laminar pipe flow of a heterogeneous nanofluid was conducted. Effect of Iron-Oxide distribution on flow and heat transfer characteristics was investigated. With Iron-Oxide volume concentration of 0.009 in water, up to 50% local heat transfer enhancement was predicted for the heterogeneous compared to homogeneous nanofluids. Increasing the Reynolds number is shown to increase enhancement while having negligible effect on pressure drop. Using permanent magnets attached externally to the pipe, an experimental investigation conducted at MIT nuclear reactor laboratory for similar flow characteristics of a heterogeneous nanofluid have shown upto 160% enhancement in heat transfer. Such results show that heterogeneous nanofluids are promising for augmenting heat transfer rates in nuclear power heat exchanger systems.

  8. Virtual reality technology in nuclear power plant operation and maintenance

    International Nuclear Information System (INIS)

    In this paper a generic virtual reality comprehensive system focusing on the operation and maintenance in Nuclear Power Plant (NPP) is proposed. Under this layout, some key topics and means of the system are discussed. As example 'Virtual Nuclear Island' comprehensive system and its typical applications in NPP are set up. In the end, it prospects the applications of virtual reality technology in NPP operation, training and maintenance. (author)

  9. Inventory of stress situations in nuclear power plants

    International Nuclear Information System (INIS)

    Anxious to pursue an in-depth analysis of stress phenomena in nuclear power plants in order to offer utilities appropriate solutions, Electricite de France and the Commissariat a l'Energie Atomique have jointly asked the Laboratoire de Psychologie du Travail to prepare an inventory of stress situations in nuclear electricity-generating centers. This document describes the approach used, the main concepts which have served as guidelines, and the methods of interpreting the results obtained through observations and questionnaires

  10. Health protection and industrial safety. Nuclear power plants

    International Nuclear Information System (INIS)

    The standard applies to components of the primary circuit including its auxiliary facilities, and of the secondary circuit of nuclear power plants with pressurized water reactors; to lifting gear and load take-ups for the transport of nuclear fuel and primary circuit components; to elevators within the containment, electrical installations, and piping and valves of radiation protection monitoring equipment. Part 1 defines the terms and specifies engineered safety requirements

  11. An analysis of nuclear power plant operating costs

    International Nuclear Information System (INIS)

    This report presents the results of a statistical analysis of nonfuel operating costs for nuclear power plants. Most studies of the economic costs of nuclear power have focused on the rapid escalation in the cost of constructing a nuclear power plant. The present analysis found that there has also been substantial escalation in real (inflation-adjusted) nonfuel operating costs. It is important to determine the factors contributing to the escalation in operating costs, not only to understand what has occurred but also to gain insights about future trends in operating costs. There are two types of nonfuel operating costs. The first is routine operating and maintenance expenditures (O and M costs), and the second is large postoperational capital expenditures, or what is typically called ''capital additions.'' O and M costs consist mainly of expenditures on labor, and according to one recently completed study, the majoriy of employees at a nuclear power plant perform maintenance activities. It is generally thought that capital additions costs consist of large maintenance expenditures needed to keep the plants operational, and to make plant modifications (backfits) required by the Nuclear Regulatory Commission (NRC). Many discussions of nuclear power plant operating costs have not considered these capital additions costs, and a major finding of the present study is that these costs are substantial. The objective of this study was to determine why nonfuel operating costs have increased over the past decade. The statistical analysis examined a number of factors that have influenced the escalation in real nonfuel operating costs and these are discussed in this report. 4 figs, 19 tabs

  12. Application of Nuclear Energy for Seawater Desalination: Design Concepts of Nuclear Desalination Plants

    International Nuclear Information System (INIS)

    Nuclear energy is playing an important role in electricity generation, producing 16% of the world's electricity. However, most of the world's energy consumption is in the form of heat, in which case nuclear energy could also play an important role. In particular, process heat for seawater desalination using nuclear energy has been of growing interest to some Member States of the International Atomic Energy Agency over the past two decades. This growing interest stems from increasingly acute freshwater shortages in many arid and semi-arid zones around the world. Indeed, several national and international nuclear desalination demonstration programs are already under way or being planned. Of particular interest are projects for seawater nuclear desalination plants in coastal regions, where saline feed water can serve the dual purpose of cooling water for the nuclear reactor and as feed water for the desalination plant. In principle any nuclear reactor can provide energy (low-grade heat and/or electricity), as required by desalination processes. However, there are some additional requirements to be met under specific conditions in order to introduce nuclear desalination. Technical issues include meeting more stringent safety requirements (nuclear reactors themselves and nuclear-desalination integrated complexes in particular), and performance improvement of the integrated systems. Economic competitiveness is another important factor to be considered for a broader deployment of nuclear desalination. For technical robustness and economic competitiveness a number of design variants of coupling configurations of nuclear desalination integrated plant concepts are being evaluated. This paper identifies and discusses various factors, which support the attractiveness of nuclear desalination. It further summarizes some of the key approaches recommended for nuclear desalination complex design and gives an overview of various design concepts of nuclear desalination plants, which

  13. A dynamical systems model for nuclear power plant risk

    Science.gov (United States)

    Hess, Stephen Michael

    The recent transition to an open access generation marketplace has forced nuclear plant operators to become much more cost conscious and focused on plant performance. Coincidentally, the regulatory perspective also is in a state of transition from a command and control framework to one that is risk-informed and performance-based. Due to these structural changes in the economics and regulatory system associated with commercial nuclear power plant operation, there is an increased need for plant management to explicitly manage nuclear safety risk. Application of probabilistic risk assessment techniques to model plant hardware has provided a significant contribution to understanding the potential initiating events and equipment failures that can lead to core damage accidents. Application of the lessons learned from these analyses has supported improved plant operation and safety over the previous decade. However, this analytical approach has not been nearly as successful in addressing the impact of plant processes and management effectiveness on the risks of plant operation. Thus, the research described in this dissertation presents a different approach to address this issue. Here we propose a dynamical model that describes the interaction of important plant processes among themselves and their overall impact on nuclear safety risk. We first provide a review of the techniques that are applied in a conventional probabilistic risk assessment of commercially operating nuclear power plants and summarize the typical results obtained. The limitations of the conventional approach and the status of research previously performed to address these limitations also are presented. Next, we present the case for the application of an alternative approach using dynamical systems theory. This includes a discussion of previous applications of dynamical models to study other important socio-economic issues. Next, we review the analytical techniques that are applicable to analysis of

  14. The assessment of the environmental external costs of power plants for both coal-fired plant and nuclear power plant

    International Nuclear Information System (INIS)

    Efforts were made to assess the environmental external costs of power plants for both Samchonpo coal-fired plant and Younggwang nuclear power plant by using the computer program developed by the IAEA. In the case that the emission control devices such as precipitator for particulates reduction, wet scrubber for SO2, and low-NOx burner for NOx were installed in the coal-fired power plant, total environmental external cost was estimated as 33.97Won/kWh, much higher than 0.76Won/kWh of Younggwang nuclear power plant. And this study also assessed and compared the environmental external costs when Younggwang nuclear power plant was replaced by the coal-fired power plant at the same site and with the same capacity. According to the result, total environmental external cost of coal-fired power plant, with the emisison control devices installed, was estimated as 792 million US$ and it was about 50 times higher than 15 million US$ of Younggwang nuclear power plant. Although the result of this study had some limits due to using the simplified model, it was still true that nuclear power was much more environmentally friendly power source than coal-fired power

  15. Radiation protection performance indicators at the Nuclear Power Plant Krsko.

    Science.gov (United States)

    Janzekovic, Helena

    2006-06-01

    Nuclear power plant safety performance indicators are developed "by nuclear operating organisations to monitor their own performance and progress, to set their own challenging goals for improvement, and to gain additional perspective on performance relative to that of other plants". In addition, performance indicators are widely used by regulatory authorities although the use is not harmonised. Two basic performance indicators related to good radiation protection practice are collective radiation exposure and volume of low-level radioactive waste. In 2000, Nuclear Power Plant Krsko, a Westinghouse pressurised water reactor with electrical output 700 MW, finished an extensive modernisation including the replacement of both steam generators. While the annual volume of low-level radioactive waste does not show a specific trend related to modernisation, the annual collective dose reached maximum, i.e. 2.60 man Sv, and dropped to 1.13 man Sv in 2001. During the replacement of the steam generators in 2000, the dose associated with this activity was 1.48 man Sv. The annual doses in 2002 and 2003 were 0.53 and 0.80 man Sv, respectively, nearing thus the goal set by the US Institute of Nuclear Power Operators, which is 0.65 man Sv. Therefore, inasmuch as collective dose as the radiation protection performance indicator are concerned, the modernisation of the Krsko nuclear power plant was a success.

  16. Report on aging of nuclear power plant reinforced concrete structures

    Energy Technology Data Exchange (ETDEWEB)

    Naus, D.J.; Oland, C.B. [Oak Ridge National Lab., TN (United States); Ellingwood, B.R. [Johns Hopkins Univ., Baltimore, MD (United States). Dept. of Civil Engineering

    1996-03-01

    The Structural Aging Program provides the US Nuclear Regulatory Commission with potential structural safety issues and acceptance criteria for use in continued service assessments of nuclear power plant safety-related concrete structures. The program was organized under four task areas: Program Management, Materials Property Data Base, Structural Component Assessment/Repair Technology, and Quantitative Methodology for Continued Service Determinations. Under these tasks, over 90 papers and reports were prepared addressing pertinent aspects associated with aging management of nuclear power plant reinforced concrete structures. Contained in this report is a summary of program results in the form of information related to longevity of nuclear power plant reinforced concrete structures, a Structural Materials Information Center presenting data and information on the time variation of concrete materials under the influence of environmental stressors and aging factors, in-service inspection and condition assessments techniques, repair materials and methods, evaluation of nuclear power plant reinforced concrete structures, and a reliability-based methodology for current and future condition assessments. Recommendations for future activities are also provided. 308 refs., 61 figs., 50 tabs.

  17. Virtual and augmented reality in the nuclear plant lifecycle perspective

    International Nuclear Information System (INIS)

    The paper presents a subset of the research and development performed over the last decade by the OECD Halden Reactor Project (HRP) using virtual reality (VR) and augmented reality (AR) in design, operation, maintenance and decommissioning to solve real world problems in the nuclear plant lifecycle. The use of VR in training at Leningrad Nuclear Power Plant (LNPP) in Russia started in 1999 with the introduction of VR technology developed by Institute for Energy Technology (IFE) for the training and presentation of procedures related to safe operation and maintenance of the refuelling machine. At Chernobyl Nuclear Power Plant (ChNPP) in Ukraine, the establishment of the Chernobyl Decommissioning Visualisation Centre (CDVC) was started in 2007. The CDVC will be used for planning, training and presentation of dismantling procedures. In the future, the CDVC will also offer calculation of the occupational dose. VR has proven to be an effective technology for better communicating the layout of project proposals in design of control rooms. AR can be used to supplement reality by blending the physical and the virtual in the actual physical environment. IFE has developed a practical solution for using the AR technology. The paper also discusses how and for what areas the VR and AR applications can contribute to the nuclear safety for symbiosis and sustainability. Finally, IFE's plans for future use of VR and AR technologies in a nuclear plant lifecycle perspective are discussed. (author)

  18. Report on aging of nuclear power plant reinforced concrete structures

    International Nuclear Information System (INIS)

    The Structural Aging Program provides the US Nuclear Regulatory Commission with potential structural safety issues and acceptance criteria for use in continued service assessments of nuclear power plant safety-related concrete structures. The program was organized under four task areas: Program Management, Materials Property Data Base, Structural Component Assessment/Repair Technology, and Quantitative Methodology for Continued Service Determinations. Under these tasks, over 90 papers and reports were prepared addressing pertinent aspects associated with aging management of nuclear power plant reinforced concrete structures. Contained in this report is a summary of program results in the form of information related to longevity of nuclear power plant reinforced concrete structures, a Structural Materials Information Center presenting data and information on the time variation of concrete materials under the influence of environmental stressors and aging factors, in-service inspection and condition assessments techniques, repair materials and methods, evaluation of nuclear power plant reinforced concrete structures, and a reliability-based methodology for current and future condition assessments. Recommendations for future activities are also provided. 308 refs., 61 figs., 50 tabs

  19. Regulatory practices for nuclear power plants in India

    International Nuclear Information System (INIS)

    Atomic Energy Regulatory Board (AERB) is the national authority to ensure that the use of ionizing radiation and nuclear energy in India does not cause undue risk to the health of workers and members of the public, and the environment. AERB fulfills its mission by stipulating and enforcing rules and regulations concerned with nuclear and radiological safety. This paper describes the regulatory authorization process of AERB as applicable to nuclear power plants (NPPs) during their construction as well as operating phases. The safety review process during construction is presented as case studies. Some current issues related to operating plants are also described. Two typical examples of safety upgradations made in old generation nuclear plants are given. The regulatory process in India is continuously evolving to cater to the new developments. Some of the recent initiatives taken by AERB in that direction are briefly described. Today AERB faces new challenges like simultaneous review of a large number of new projects of diverse designs, a fast growing nuclear power program and functioning of operating plants in a competitive environment. This paper delineates how AERB is gearing up itself to meet these challenges in an effective manner

  20. Nuclear power plants seismic instrumentation: Spanish practice

    International Nuclear Information System (INIS)

    Seismic Instrumentation system of Spanish plants are required to reach the following main goals: first at all to determine the OBE exceedance, and second to obtain site specific data in order to capture or reduce both uncertainties from the site and the structural design (e.g. near field attenuation and site effects models, or structural ageing effects and design models), and to Improve the safety re-evaluation analysis. From licensing, the main Spanish NPP's (5 sites) were equipped with the best analogical Instrumentation at that time, adequate to record strong earthquakes, but with limited resolution to register on free field low accelerations with reasonably confidence. In a general way, seismic PRA results addressed new and higher perception on the earthquake occurrence probability in Spain, and a cost/benefit program to Improve seismic Instrumentation of all plants was planned. Implementing this action requires to get new digital free field Instrumentation, and to develop procedures to quickly decide an OBE exceedance, like it is recommended in USNRC regulatory guides 1.12, rev. 2, and 1.166. Plant owners endorsed these guides and proposed a full change of their seismic monitoring system Instrumentation, what includes a review of the plant Technical Specifications. Some instrumental improvements like universal time reference or higher resolution than 12 bits are recommended. (authors)