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Sample records for yonggwang nuclear units

  1. Nuclear design report for Yonggwang nuclear power plant unit 2 cycle 7

    International Nuclear Information System (INIS)

    Zee, Sung Kyun; Choi, Gyoo Hwan; Lee, Ki Bog; Park, Sang Yoon

    1993-02-01

    This report presents nuclear design calculations for Cycle 7 of Yonggwang Unit 2. Information is given on fuel loading, power density distributions, reactivity coefficients, control rod worths and operational limits. In addition, the report contains all necessary data for the startup tests including predicted values for the comparison with the measured data. The reload consists of 64 KOFA's enriched by nominally 3.70 w/o U235. Among the KOFA's, 40 fuel assemblies contain gadolinia rods. The fuel assemblies in the core are arranged in a low leakage loading pattern. The cycle length of Cycle 7 amounts to 367 EFPD corresponding to a cycle burnup of 14770 MWD/MTU. (Author)

  2. Nuclear design report for Yonggwang nuclear power plant unit 4 cycle 2

    International Nuclear Information System (INIS)

    Park, Chan Oh; Park, Sang Yoon; Yoo, Choon Sung; Ryu, Hyo Sang; Park, Jin Ha; Cho, Young Chul; Song, Jae Woong; Lee Chung Chan.

    1996-10-01

    This report presents nuclear design calculations for Cycle 2 of Yonggwang Unit 4. Information is given on fuel loading, power density distributions, reactivity coefficients, control rod worths, and operational limits. In addition, the report contains necessary data for the startup tests and for the assurance of shutdown margin during reactor operation. The reload core consists of 48 fresh KSFAs. Among the 48 fresh KSFAs, 32 fuel assemblies contain burnable poison rods. The fuel assemblies in the core are arranged in a low leakage loading pattern. The cycle length of Cycle 2 amounts to 275 EFPD corresponding to a cycle burnup of 10,100 MWD/MTU. (author). 31 tabs., 92 figs., 7 refs

  3. Nuclear design report for Yonggwang nuclear power plant unit 3 cycle 2

    Energy Technology Data Exchange (ETDEWEB)

    Zee, Sung Kyun; Song, Jae Woong; Song, Jae Seung; Park, Sang Yoon; Yoo, Choon Sung; Baek, Byung Chan; Ryu, Hyo Sang; Park, Jin Ha; Cho, Young Chul [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1996-01-01

    This report presents nuclear design calculations for Cycle 2 of Yonggwang Unit 3. Information is given on fuel loading, power density distributions, reactivity coefficients, control rod worths, and operational limits. In addition, the report contains necessary data for the startup tests and for the assurance of shutdown margin during reactor operation. The reload core consists of 48 fresh Korean Standard Fuel Assemblies (KSFAs)and 129 burned KSFAs. Among the 48 fresh KSFAs, 32 fuel assemblies contain burnable poison rods. The fuel assemblies in the core are arranged in a low leakage loading pattern. The cycle length of Cycle 2 amounts to 276 EFPD corresponding to a cycle burnup of 10,160 MWD/MTU. 95 figs., 31 tabs., 7 refs. (Author) .new.

  4. Comprehensive vibration assessment program for Yonggwang nuclear power plant unit 4

    International Nuclear Information System (INIS)

    Rhee, Hui Nam; Hwang, Jong Keun; Kim, Tae Hyung; Kim, Jung Kyu; Song, Heuy Gap; Kim, Beom Shig

    1995-01-01

    A Comprehensive Vibration Assessment Program (CVAP) has been performed for Yonggwang Nuclear Power Plant Unit 4 (YGN 4) in order to verify the structural integrity of the reactor internals for flow induced vibrations prior to commercial operation. The theoretical evidence for the structural integrity of the reactor internals and the basis for measurement and inspection are provided by the analysis. Flow induced hydraulic loads and reactor internals vibration response data were measured during pre-core hot functional testing in YGN 4 site. Also, the critical areas in the reactor internals were inspected visually to check any existence of structural abnormality before and after the pre-core hot functional testing. Then, the measured data have been analyzed and compared with the predicted data by analysis. The measured stresses are less than the predicted values and the allowable limits. It is concluded that the vibration response of the reactor internals due to the flow induced vibration under normal operation is acceptable for long term operation

  5. Analysis of radiation field distribution in Yonggwang unit 3 with MCNP code

    International Nuclear Information System (INIS)

    Lee, Cheol Woo; Ha, Wi Ho; Shin, Chang Ho; Kim, Soon Young; Kim, Jong Kyung

    2004-01-01

    Radiation field analysis is performed at the inside of the containment building of nuclear power plant(NPP) using the well-known MCNP code. The target NPP in this study is Yonggwang Unit 3 Cycle 8. In this work, whole transport calculations were done using MCNPX 2.4.0 due to the functional benefits, such as Mesh Tally, that the code provides. The neutron spectra released from the operating reactor core were firstly evaluated as a radiation source term, and then dose distributions in the work areas of the NPP were calculated

  6. Initial startup and operations of Yonggwang Units 3 and 4

    International Nuclear Information System (INIS)

    Collier, T.J.; Chari, D.R.; Kiraly, F.

    1996-01-01

    A significant milestone in the nuclear power industry was achieved in 1995, when Yonggwang (YGN) Units 3 and 4 were accepted into in commercial operation by Korea Electric Power Corporation (KEPCO). YGN Unit 3 was accepted into commercial operation on March 31, 1995, the original date established during project initiation. YGN Unit 4 was accepted into operation on January 1, 1996, 3 months ahead of schedule. Each YGN unit produces approximately 1,050 Mwe and supplies approximately ten percent of the total electric power demand in the Republic of Korea (ROK). The overall plant efficiency is approximately 37% which is at least 1% higher than most nuclear units. Since achieving commercial operation, YGN Unit 3 has operated at essentially full power which has resulted in an annual performance rate in excess of 85%. YGN Unit 3 is the first of six pressurized water reactors which are currently under design and construction in the ROK and serves as the reference design for the Korean Standard Nuclear Power Plant program. Both YGN Units 3 and 4 include a System 800 Nuclear Steam Supply System (NSSS). The NSSS is rated at 2,815 Mwth and is the ABB-CE standard design. The design includes numerous advanced design features which enhance plant safety, performance and operability. A well executed startup test program was successfully completed on both units prior to commercial operation. A summary of the YGN NSSS design features, the startup test program and selected test results demonstrating the performance of those features are presented in this paper

  7. Evaluation of the control system checkout test at 100% power for Yonggwang Nuclear Power Plant Unit 3

    International Nuclear Information System (INIS)

    Kim, Shin Whan; Lee, Joo Han; Baek, Jong Man; Seo, Jong Tae; Lee, Sang Keun; Kang, In Koo; Ju, Hee Wan; Min, Kyung Soo; Kim, Byung Gon

    1995-01-01

    Control system checkout tests at various powers for Yonggwang Nuclear Power Plant Unit 3(YGN3) were performed to demonstrate the accuracies and proper performances of the control systems of the plant. Tested control systems included the feedwater control system, steam bypass control system, reactor regulation system, control element drive mechanism control system, pressurizer level control system, and pressurizer pressure control system. The measured test data during the control system checkout test at 100% power are evaluated. The test results showed that the control systems of YGN 3 properly control system was simulated by using the LTC code which is the performance analysis code for YGN 3 and 4 design. Comparisons of the predicted results with the measured data confirmed that the feedwater control system controls the steam generator level as designed

  8. Water Hammer Analysis using RELAP5/MOD 3.3 for Yonggwang Nuclear Power Unit 1 and 2 Blowdown System

    International Nuclear Information System (INIS)

    Lee, Sang Il; Kim, Hea Zoo; Chu, Jung Ho; Ahn, Se Hong; Jung, Chang Ho

    2010-01-01

    Water hammer can be defined as a rapid pressure step occurring in the liquid in a closed pipe caused by a sudden change in the liquid velocity. This pressure acts for a period which is twice the transit time of sonic wave in the pipe. Generally, water hammer can occur in any thermal-hydraulic systems like nuclear power plant and is extremely dangerous for nuclear power plant piping system since, if the pressure induced exceeds the pressure range of the pipe given by the manufacturer, it can lead to the failure of the piping system integrity. For Yonggwang nuclear power unit 1 and 2, water hammer occurred repeatedly on the outlet piping of regenerative heat exchanger of steam generator blowdown system. Thus, design modification was performed to prevent the water hammer and the analysis of effect on water hammer before and after design modification was performed to verify the validity of the design modification

  9. Final report for the 5th surveillance test of the reactor pressure vessel material (capsule Y) of Yonggwang Nuclear Power Plant unit 2

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Sam Lai; Kim, ByoungChul; Chang, Kee Ok (and others)

    2006-02-15

    Surveillance testing for reactor vessel materials is performed in order to evaluate the irradiation embrittlement due to neutrons during operation and set the condition of safe operation of nuclear reactor. The 5th surveillance testing was performed completely by Korea Atomic Energy Research Institute at Daejeon after the capsule was transported from Yonggwang site including its removal from reactor. Fast neutron fluences for capsules were calculated and various testing including mechanical and chemistry analysis were performed in order to evaluate the integrity of Yonggwang unit 2 reactor vessel during the operation until life time. The evaluation results are as follows; Fast neutron fluences for capsules U, V, X, W and Y are 5.777E+18, 1.5371E+19, 3.7634E+19, 4.3045E+19, and 4.8662E+19n/cm{sup 2}, respectively. The bias factor, the ratio of calculation/measurement, was 0.953 for the 1st through 5th testing and the calculational uncertainty,7.2% satisfied the requirement of USNRC Reg.Guide 1.190, 20%. The best estimated neutron fluence for reactor vessel inside surface was 1.659E+19n/cm{sup 2} based on the end of 13th fuel cycle and it was predicted that the fluences of vessel inside surface at 32, 48, 56 and 64EFPY would reach 3.625E+19, 5.293E+19, 6.127E+19 and 6.960E+19n/cm{sup 2} based on the current calculation. The result through this analysis for Yonggwang unit 2 showed that there would be no problem for the Pressurized Thermal Shock(PTS) during the operation until design life.

  10. Uncertainly propagation analysis for Yonggwang nuclear unit 4 by McCARD/MASTER core analysis system

    Energy Technology Data Exchange (ETDEWEB)

    Park, Ho Jin [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Lee, Dong Hyuk; Shim, Hyung Jin; Kim, Chang Hyo [Seoul National University, Seoul (Korea, Republic of)

    2014-06-15

    This paper concerns estimating uncertainties of the core neutronics design parameters of power reactors by direct sampling method (DSM) calculations based on the two-step McCARD/MASTER design system in which McCARD is used to generate the fuel assembly (FA) homogenized few group constants (FGCs) while MASTER is used to conduct the core neutronics design computation. It presents an extended application of the uncertainty propagation analysis method originally designed for uncertainty quantification of the FA FGCs as a way to produce the covariances between the FGCs of any pair of FAs comprising the core, or the covariance matrix of the FA FGCs required for random sampling of the FA FGCs input sets into direct sampling core calculations by MASTER. For illustrative purposes, the uncertainties of core design parameters such as the effective multiplication factor (k{sub eff}), normalized FA power densities, power peaking factors, etc. for the beginning of life (BOL) core of Yonggwang nuclear unit 4 (YGN4) at the hot zero power and all rods out are estimated by the McCARD/MASTER-based DSM computations. The results are compared with those from the uncertainty propagation analysis method based on the McCARD-predicted sensitivity coefficients of nuclear design parameters and the cross section covariance data.

  11. Evaluation of Yonggwang unit 4 cycle 5 using SPNOVA code

    International Nuclear Information System (INIS)

    Choi, Y. S.; Cha, K. H.; Lee, E. K.; Park, M. K.

    2004-01-01

    Core follow calculation of Yonggwang (YGN) unit 4 cycle 5 is performed to evaluate SPNOVA code if it can be applicable or not to Korean standard nuclear power plant (KSNP). SPNOVA code consists of BEPREPN and ANC code to represent incore detector and neutronics model, respectively. SPNOVA core deflection model is compared and verified with ANC depletion results in terms of critical boron concentration (CBC), peaking factor (Fq) and radial power distribution. In YGN4, SPNOVA predicts 30 ppm lower than that of ROCS predicting CBC. Fq and radial power distribution behavior of SPNOVA calculation have conservatively higher than those of ROCS predicting values. And also SPNOVA predicting results are compared with measurement data from snapshot and CECOR core calculation. It is reasonable to accept SPNOVA to analyze KSNP. The model of SPNOVA for KSNP will be used to develop the brand-new incore detector of platinum and vanadium

  12. Qualification of McCARD/MASTER Code System for Yonggwang Unit 4

    International Nuclear Information System (INIS)

    Park, Ho Jin; Shim, Hyung Jin; Joo, Han Gyu; Kim, Chang Hyo

    2011-01-01

    Recently, we have developed the new two-step procedure based on the Monte Carlo (MC) methods. In this procedure, one can generate the few group constants including the few-group diffusion constants by the MC method augmented by the critical spectrum, which is provided by the solution to the homogeneous 0-dimensional B1 equation. In order to examine the qualification of the few-group constants generated by MC method, we combine MASTER with McCARD to form McCARD/MASTER code system for two-step core neutronics calculations. In the fictitious PWR system problems, the core design parameters calculated by the two-step McCARD/MASTER analysis agree well with those from the direct MC calculations. In this paper, a neutronic design analysis for the initial core of Yonggwang Nuclear Unit 4 (YGN4) is conducted using McCARD/MASTER two-step procedure to examine the qualification of two group constants from McCARD in terms of a real PWR core problem. To compare with the results, the nuclear design report and measured data are chosen as the reference solutions

  13. The 4th surveillance test and evaluation of the reactor pressure vessel material (capsule W) of Yonggwang nuclear power plant unit 2

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Kee Ok; Kim, Byoung Chul; Lee, Sam Lai; Choi, Kwon Jae; Gong, Un Sik; Chang, Jong Hwa; Joo, Yong Sun; Ahn, Sang Bok; Hong, Joon Hwa [Korea Atomic Energy Research Institute, Taejeon (Korea)

    2001-02-01

    Surveillance testing for reactor vessel materials is performed in order to evaluate the irradiation embrittlement due to neutrons during operation and set the condition of safe operation of nuclear reactor. The 4th surveillance testing was performed completely by Korea Atomic Energy Research Institute at Taejeon after the capsule was transported from Kori site including its removal from reactor. Fast neutron fluences for capsules were calculated and various testing including mechanical and chemistry analysis were performed in order to evaluate the integrity of Yonggwang unit 2 reactor vessel during the operation until life time. The evaluation results are as follows; Fast neutron fluences for capsules U, V, X and W are 5.762E+18, 1.5391E+19, 3.5119E+19, and 4.2610E+19 n/cm{sup 2}, respectively. The bias factor, the ratio of measurement versus calculation, was 0.899 for the 1st through 4th testing and the calculational uncertainty, 12.3% satisfied the requirement of USNRC Reg.Guide DG-1053, 20%. The best estimated neutron fluence for reactor vessel inside surface was 1.357E+19 n/cm{sup 2} based on the end of 11th fuel cycle and it was predicted that the fluences of vessel inside surface at 32, 40, 48 and 56EFPY would reach 3.525E+19, 4.337E+19, 5.148E+19 and 5.960E+19 n/cm{sup 2} based on the current calculation. The result through this analysis for Yonggwang unit 2 showed that there would be no problem for the pressurized thermal shock(PTS) during the operation until design life. 48 refs., 35 figs., 42 tabs. (Author)

  14. Human Factors Evaluation of Procedures for Periodic Safety Review of Yonggwang Unit no. 1, 2

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Yong Hee; Lee, Jung Woon; Park, Jae Chang (and others)

    2006-01-15

    This report describes the results of human factors assessment on the plant operating procedures as part of Periodic Safety Review(PSR) of Yonggwang Nuclear Power Plant Unit no. 1, 2. The suitability of item and appropriateness of format and structure in the key operating procedures of nuclear power plants were investigated by the review of plant operating experiences and procedure documents, field survey, and experimental assessment on some part of procedures. A checklist was used to perform this assessment and record the review results. The reviewed procedures include EOP(Emergency Operating Procedures), GOP(General Operating Procedures), AOP(Abnormal Operating Procedures), and management procedures of some technical departments. As results of the assessments, any significant problem challenging the safety was not found on the human factors in the operating procedures. However, several small items to be changed and improved were discovered. An action plan is recommended to accommodate the suggestions and review comments. It will enhance the plant safety on the operating procedure.

  15. Final report for the 2nd Ex-Vessel Neutron Dosimetry Installations and Evaluations for Yonggwang Unit 2 Reactor Pressure Vessel

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Byoung Chul; Yoo, Choon Sung; Lee, Sam Lai; Gong, Un Sik; Choi, Kwon Jae; Chung, Kyoung Ki; Kim, Kwan Hyun; Chang, Jong Hwa; Ha, Jea Ju

    2008-01-15

    This report describes a neutron fluence assessment performed for the Yonggwang Unit 2 pressure vessel beltline region based on the guidance specified in Regulatory Guide 1.190. In this assessment, maximum fast neutron exposures expressed in terms of fast neutron fluence (E>1 MeV) and iron atom displacements (dpa) were established for the beltline region of the pressure vessel. During Cycle 16 of reactor operation, an Ex-Vessel Neutron Dosimetry Program was instituted at Yonggwang Unit 2 to provide continuous monitoring of the beltline region of the reactor vessel. The use of the Ex-Vessel Neutron Dosimetry Program coupled with available surveillance capsule measurements provides a plant specific data base that enables the evaluation of the vessel exposure and the uncertainty associated with that exposure over the service life of the unit. Ex-Vessel Neutron Dosimetry has been evaluated at the conclusion of Cycle 16.

  16. Final Report of the 2nd Ex-Vessel Neutron Dosimetry Installation And Evaluations for Yonggwang Unit 1 Reactor Pressure Vessel

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Byoung Chul; Yoo, Choon Sung; Lee, Sam Lai; Chang, Kee Ok; Gong, Un Sik; Choi, Kwon Jae; Chang, Jong Hwa; Li, Nam Jin; Hong, Joon Wha

    2007-01-15

    This report describes a neutron fluence assessment performed for the Yonggwang Unit 1 pressure vessel belt line region based on the guidance specified in Regulatory Guide 1.190. In this assessment, maximum fast neutron exposures expressed in terms of fast neutron fluence (E>1 MeV) and iron atom displacements (dpa) were established for the belt line region of the pressure vessel. During Cycle 16 of reactor operation, 2nd Ex-Vessel Neutron Dosimetry Program was instituted at Yonggwang Unit 1 to provide continuous monitoring of the belt line region of the reactor vessel. The use of the Ex-Vessel Neutron Dosimetry Program coupled with available surveillance capsule measurements provides a plant specific data base that enables the evaluation of the vessel exposure and the uncertainty associated with that exposure over the service life of the unit. Ex-Vessel Neutron Dosimetry has been evaluated at the conclusion of Cycle 16.

  17. A flow test for calibrating 177 core tubes of 1/5-scale reactor flow model for Yonggwang nuclear units 3 and 4

    International Nuclear Information System (INIS)

    Lee, Byung Jin; Jang, Ho Cheol; Cheong, Jong Sik; Kuh, Jung Eui

    1990-01-01

    A flow test was performed to find out the hydraulic characteristics of every one of 177 core tubes, representing a fuel assembly respectively, as a preparatory step of 1/5 scale reactor flow model test for Yonggwang Nuclear Units (hereafter YGN) 3 and 4. The axial hydraulic resistance of the fuel assembly was simulated in the square core tube with six orifice plates positioned along the tube length; core support structure below each fuel assembly was done in the core upstream geometry section of the test loop. For each core tube the pressure differentials across the inlet, exit orifice plate and overall tube length were measured, along with the flow rates and temperatures of the test fluid. The measured pressure drops were converted to pressure loss or flow metering coefficients. The metering coefficient of the inlet orifice plate was sensitive to the configuration and location of the upstream geometry. The hydraulic resistance of the core tubes were reasonably coincided with a target value and consistent. The polynomial curve fits of the calibrated coefficients for the 177 core tubes were obtained with reasonable data scatters

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

    International Nuclear Information System (INIS)

    1995-05-01

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

  19. Removal of Secondary Side Deposit and Foreign Objects in SG of Yonggwang Nuclear Power Plant, Unit 2

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Wootae [KHNP-CRI, Daejeon (Korea, Republic of); Yun, Sangjung; Choi, Yongseok; Kim, Taehwa; Seo, Hongchang [Byucksan Digital Valley II, Seoul (Korea, Republic of)

    2014-05-15

    Mock-up test and training before the service were made to minimize operation time and radiation dose. 8 bag filters and 49 cartridge filters were consumed for filtering of soft and hard sludge in SG A, B, and C. Total 21.05 kilograms of sludge was removed. Five foreign objects were found and removed in tube bundle of SG A, in annulus and tube bundle of SG B, and in tube bundle of SG C. During the 20{sup th} OH of Yonggwang NPP unit 2, we removed 21.05 kilograms of sludge and five foreign objects from three steam generators. Gradual increase in weight of sludge removed is assumed to show us that more sludge is created as operation time of steam generator increases. Low level chemical cleaning at 19{sup th} OH removed 517 kilograms of sludge which was dominant of all the sludge removal weight. We could assume, from this fact, that high level chemical cleaning could remove significant amount of sludge compared to mechanical lancing method. Five foreign objects which were removed from inside of SG showed us that more thorough inside cleaning and inspection is necessary during fabrication of steam generator.

  20. Atmospheric Dispersion Assessment for Potential Accidental Releases at Yonggwang Nuclear Power Plants

    International Nuclear Information System (INIS)

    Na, Man Gyun; Sim, Young Rok; Jung, Chul Kee; Lee, Goung Jin; Kim, Soong Pyung; Chung, Sung Tai

    2000-01-01

    XOQ DW code is currently used to assess the atmospheric dispersion for the routine releases of radioactive gaseous effluents at Yonggwang nuclear power plants. This code was developed based on XOQDOQ code and an additional code is required to assess the atmospheric dispersion for potential accidental releases. In order to assess the atmospheric dispersion for the accidental releases, XOQAR code has been developed by using PAVAN code that is based on Reg. Guide 1.145. The terrain data of XOQ DW code inputs and the relative concentrations (X/Q) of XOQ DW code outputs are used as the inputs of the XOQAR code through the interface with XOQ DW code. By using this code, the maximum values of X/Q at exclusion area and low population zone boundaries except for sea areas were assessed as 1.33 x 10 -4 and 7.66 x 10 -6 sec/m 3 , respectively. Through the development of this code, a code system is prepared for assessing the atmospheric dispersion for the accidental releases as well as the routine releases. This developed code can be used for other domestic nuclear power plants by modifying the terrain input data

  1. Comparison of 2D and 3D Neutron Transport Analyses on Yonggwang Unit 3 Reactor

    International Nuclear Information System (INIS)

    Maeng, Aoung Jae; Kim, Byoung Chul; Lim, Mi Joung; Kim, Kyung Sik; Jeon, Young Kyou; Yoo, Choon Sung

    2012-01-01

    10 CFR Part 50 Appendix H requires periodical surveillance program in the reactor vessel (RV) belt line region of light water nuclear power plant to check vessel integrity resulting from the exposure to neutron irradiation and thermal environment. Exact exposure analysis of the neutron fluence based on right modeling and simulations is the most important in the evaluation. Traditional 2 dimensional (D) and 1D synthesis methodologies have been widely applied to evaluate the fast neutron (E > 1.0 MeV) fluence exposure to RV. However, 2D and 1D methodologies have not provided accurate fast neutron fluence evaluation at elevations far above or below the active core region. RAPTOR-M3G (RApid Parallel Transport Of Radiation - Multiple 3D Geometries) program for 3D geometries calculation was therefore developed both by Westinghouse Electronic Company, USA and Korea Reactor Integrity Surveillance Technology (KRIST) for the analysis of In-Vessel Surveillance Test and Ex-Vessel Neutron Dosimetry (EVND). Especially EVND which is installed at active core height between biological shielding material and concrete also evaluates axial neutron fluence by placing three dosimetries each at Top, Middle and Bottom part of the angle representing maximum neutron fluence. The EVND programs have been applied to the Korea Nuclear Plants. The objective of this study is therefore to compare the 3D and the 2D Neutron Transport Calculations and Analyses on the Yonggwang unit 3 Reactor as an example

  2. Nuclear design report for Yonggwang nuclear power plant unit 1 cycle 9

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Young chul; Kim, Jae Hak; Song, Jae Woong [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-03-01

    This report presents nuclear design calculations for Cycle 6 of Yonggwng Unit 1. Information is given on fuel loading, power density distributions, reactivity coefficients, control rod worths and operational limits. In addition, the report contains all necessary data for the startup tests including predicted values for the comparison with the measured data. The reload consists of 76 KOFA`s enriched by nominally 4.00 w/o U{sub 235}. Among the KOFA`s, 60 fuel assemblies contain gadolinia rods. The fuel assemblies in the core are arranged in a low leakage loading pattern. The cycle length of Cycle 9 amounts to 434 EFPD corresponding to a cycle burnup of 17470 MWD/MTU. (Author) 8 refs., 55 figs., 19 tabs.

  3. Nuclear design report for Yonggwang nuclear power plant unit 1, cycle 8

    International Nuclear Information System (INIS)

    Cho, Young Chul; Kim, Jae Hak; Park, Sang Yoon; Zee, Sung Kyun; Lee, Sang Keun; Ahn, Dawk Hwan

    1993-10-01

    This report presents nuclear design calculations for cycle 8 of Kori unit 1. Information is given on fuel loading, power density distributions, reactivity coefficients, control rod worths and operational limits. In addition, the report contains all necessary data for the startup tests including predicted values for the comparison with the measured data. The reload consists of 76 KOFA's enriched by nominally 3.70 w/o U 235 . Among the KOFA's, 56 fuel assemblies contain gadolinia rods. The fuel assemblies in the core are arranged in a low leakage loading pattern. The cycle length of cycle 8 amounts to 447 EFPD corresponding to a cycle burnup of 18020 MWD/MTU. (Author) 8 refs., 39 figs., 17 tabs

  4. Nuclear design report for Yonggwang nuclear power plant unit 1, cycle 8

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Young Chul; Kim, Jae Hak; Park, Sang Yoon; Zee, Sung Kyun; Lee, Sang Keun; Ahn, Dawk Hwan [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1993-10-01

    This report presents nuclear design calculations for cycle 8 of Kori unit 1. Information is given on fuel loading, power density distributions, reactivity coefficients, control rod worths and operational limits. In addition, the report contains all necessary data for the startup tests including predicted values for the comparison with the measured data. The reload consists of 76 KOFA`s enriched by nominally 3.70 w/o U{sub 235}. Among the KOFA`s, 56 fuel assemblies contain gadolinia rods. The fuel assemblies in the core are arranged in a low leakage loading pattern. The cycle length of cycle 8 amounts to 447 EFPD corresponding to a cycle burnup of 18020 MWD/MTU. (Author) 8 refs., 39 figs., 17 tabs.

  5. Evaluation of Steam Generator Level behavior for Determination of Turbine Runback rate on COPs trip for Yonggwang 1 and 2 Power Uprating Units

    International Nuclear Information System (INIS)

    Lee, Kyung Jin; Hwang, Su Hyun; Yoo, Tae Geun; Chung, Soon Il; An, Byung Chang; Park, Jung Gu

    2010-01-01

    4.5% power uprate project has been progressing for the first time in Yonggwang 1 and 2(YGN1 and 2). Reviews for design change due to the power uprate were accomplished. Steam generator level behavior was one of the most important parameters because it could be cause of reactor trip or turbine trip. As the results of the reviews, YGN1 and 2 had to reassess it for change of turbine runback rate when turbine runback occurs due to the condensate operating pumps (COP) trip. This study has been carried out for evaluating the steam generator level behavior for determination of turbine runback rate on COPs trip for Yonggwang 1 and 2 Power Uprating Units. The steam generator water level evaluation program for YGN1 and 2 (SLEP-Y1) has been developed for it. The program includes models for the steam generator water level response. SLEP-Y1 is programmed with advanced continuous system simulation language (ACSL). The language has been used to simulate physical systems as a commercial tool used to evaluate system designs

  6. Workstation environment supports for startup of YGN 3 and 4 nuclear unit

    International Nuclear Information System (INIS)

    Lee, Won Jae; Kim, Won Bong; Lee, Byung Chae

    1995-07-01

    Light water reactor fuel development division of Korea Atomic Energy Research Institute participated in the installation of the plant computer system and software, and the user support activities of Asea Brown Boveri/Combustion Engineering for the Plant Monitoring System during the startup phase of YGN-3 nuclear unit. The main purpose of the participation is to have the self-reliant plant- computer technology for the independent design and startup of next nuclear units. This report describes the activities performed by KAERI with ABB/CE at the plant site. In addition, it describes the direct transfer of data files between PMS and workstation which was independently carried out by KAERI. Since KAERI should support the site in setting-up the plant computer environment independent of ABB-CE from the next nuclear units, the review was performed for the technical details of activities provided to the site in order to provide the better computer environment in the next nuclear units. In conclusion, this report is expected to provide the technical background for the supporting of plant computing environment and the scope of support work at plant site during Yonggwang 3, 4 startup in the area of plant computer for the next nuclear units. 6 refs. (Author) .new

  7. Workstation environment supports for startup of YGN 3 and 4 nuclear unit

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Won Jae; Kim, Won Bong; Lee, Byung Chae [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-07-01

    Light water reactor fuel development division of Korea Atomic Energy Research Institute participated in the installation of the plant computer system and software, and the user support activities of Asea Brown Boveri/Combustion Engineering for the Plant Monitoring System during the startup phase of YGN-3 nuclear unit. The main purpose of the participation is to have the self-reliant plant- computer technology for the independent design and startup of next nuclear units. This report describes the activities performed by KAERI with ABB/CE at the plant site. In addition, it describes the direct transfer of data files between PMS and workstation which was independently carried out by KAERI. Since KAERI should support the site in setting-up the plant computer environment independent of ABB-CE from the next nuclear units, the review was performed for the technical details of activities provided to the site in order to provide the better computer environment in the next nuclear units. In conclusion, this report is expected to provide the technical background for the supporting of plant computing environment and the scope of support work at plant site during Yonggwang 3, 4 startup in the area of plant computer for the next nuclear units. 6 refs. (Author) .new.

  8. The applicability of ALPHA/PHOENIX/ANC nuclear design code system on Korean standard PWR's

    International Nuclear Information System (INIS)

    Lee, Kookjong; Choi, Kie-Yong; Lee, Hae-Chan; Roh, Eun-Rae

    1996-01-01

    For the Korean Standard Nuclear Power Plant (KSNPP) designed based on Combustion Engineering (CE) System 80, the Westinghouse nuclear design code system ALPHA/PHOENIX/ANC was applied to the follow-up design of initial and reload core of KSNPP. The follow-up design results of Yonggwang Unit 3 Cycle 1, 2 and Yonggwang Unit 4 Cycle 1 have shown good agreements with the measured data. The assemblywise power distributions have shown less than 2% average differences and critical boron concentrations have shown less than 20 ppm differences. All the low power physics test parameters are in good agreement. Consequently, APA design code system can be applied to KNSPP cores. (author)

  9. Human Factors Evaluation of Man-Machine Interface for Periodic Safety Review of Yonggwang Unit no. 1, 2

    International Nuclear Information System (INIS)

    Lee, Yong Hee; Lee, Jung Woon; Park, Jae Chang

    2006-01-01

    This report describes the research results of human factors assessment on the MMI(Man Machine Interface) equipment as part of Periodic Safety Review(PSR) of Yonggwang Unit no. 1, 2. As MMI is a key factor among human factors to be reviewed in PSR, we reviewed the MMI components of nuclear power plants in aspect of human factors engineering. The availability, suitability, and effectiveness of the MMI devices were chosen to be reviewed. The MMI devices were investigated through the review of design documents related to the MMI, survey of control panels, evaluation of experts, and experimental assessment. Checklists were used to perform this assessment and record the review results. The items mentioned by the expert comments to review in detail in relation with task procedures were tested by experiments with operators' participation. For some questionable issues arisen during this MMI review, operator workload and possibility of errors in operator actions were analysed. The reviewed MMI devices contain MCR(Main Control Room), SPDS(Safety Parameter Display System), RSP(Remote Shutdown Panel), and the selected LCBs(Local Control Boards) importantly related to safety. As results of the assessments, any significant problem challenging the safety was not found on human factors in the MMI devices. However, several small items to be changed and improved in suitability of MMI devices were discovered. An action plan is recommended to accommodate the suggestions and review comments. It will enhance the plant safety on MMI area

  10. Human Factors Evaluation of Man-Machine Interface for Periodic Safety Review of Yonggwang Unit no. 1, 2

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Yong Hee; Lee, Jung Woon; Park, Jae Chang (and others)

    2006-01-15

    This report describes the research results of human factors assessment on the MMI(Man Machine Interface) equipment as part of Periodic Safety Review(PSR) of Yonggwang Unit no. 1, 2. As MMI is a key factor among human factors to be reviewed in PSR, we reviewed the MMI components of nuclear power plants in aspect of human factors engineering. The availability, suitability, and effectiveness of the MMI devices were chosen to be reviewed. The MMI devices were investigated through the review of design documents related to the MMI, survey of control panels, evaluation of experts, and experimental assessment. Checklists were used to perform this assessment and record the review results. The items mentioned by the expert comments to review in detail in relation with task procedures were tested by experiments with operators' participation. For some questionable issues arisen during this MMI review, operator workload and possibility of errors in operator actions were analysed. The reviewed MMI devices contain MCR(Main Control Room), SPDS(Safety Parameter Display System), RSP(Remote Shutdown Panel), and the selected LCBs(Local Control Boards) importantly related to safety. As results of the assessments, any significant problem challenging the safety was not found on human factors in the MMI devices. However, several small items to be changed and improved in suitability of MMI devices were discovered. An action plan is recommended to accommodate the suggestions and review comments. It will enhance the plant safety on MMI area.

  11. Tube Plugging Criterion for the TPCCW Heat Exchanger of Yonggwang NPP 1 and 2

    International Nuclear Information System (INIS)

    Kim, Hyung Nam; Yoo, Hyun Ju; Choi, Sung Nam; Song, Seok Yoon

    2009-01-01

    The turbine plant component cooling water(TPCCW) system circulates the cooling water to cool the components in the turbine building and discharges the heat from the components through the TPCCW heat exchanger. Recently, Yonggwang NPP 1 and 2 replaced the TPCCW heat exchanger because of tube degradation. The tubing material of new TPCCW heat exchanger of Yonggwang NPP 1 and 2 is titanium. If the tube wall cannot withstand the pressure, the cooling water with the chemicals flows into the tube side and it is discharged to the open water. The chemicals can pollute the open water. Therefore, the tubes of the TPCCW heat exchanger should be inspected and degraded tubes should be plugged. It is inevitable for the materials of the components to be degraded as the power plants become older. The degradation accompanies increasing maintenance cost as well as creating safety issues. The materials and wall thickness of heat exchanger tubes in nuclear power plants are selected to withstand system temperature, pressure, and corrosion. However, tubes have experienced leaks and failures and plugged based upon eddy current testing (ET) results. There are some problems for plugging the heat exchanger tubes since the criterion and its basis are not clearly described. For this reason, the criteria for the tube wall thickness are addressed in order to operate the heat exchangers in nuclear power plant without trouble during the cycle. There are many codes and standards to be referred for calculating the minimum thickness of the heat exchanger tube in the designing stage. However, the codes and standards related to show the tube plugging criteria may not exist currently. In this paper, a method to establish the tube plugging criteria of BOP heat exchangers, which is based on the USNRC Regulatory Guide 1.121, is introduced and the tube plugging criteria for the TPCCW heat exchanger of Yonggwang NPP No. 1 and 2. This method relies on the similar plugging criteria used in the steam generator

  12. Tube Plugging Criterion for the TPCCW Heat Exchanger of Yonggwang NPP 1 and 2

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hyung Nam; Yoo, Hyun Ju; Choi, Sung Nam; Song, Seok Yoon [Korea Electric Power Research Institute, Daejeon (Korea, Republic of)

    2009-05-15

    The turbine plant component cooling water(TPCCW) system circulates the cooling water to cool the components in the turbine building and discharges the heat from the components through the TPCCW heat exchanger. Recently, Yonggwang NPP 1 and 2 replaced the TPCCW heat exchanger because of tube degradation. The tubing material of new TPCCW heat exchanger of Yonggwang NPP 1 and 2 is titanium. If the tube wall cannot withstand the pressure, the cooling water with the chemicals flows into the tube side and it is discharged to the open water. The chemicals can pollute the open water. Therefore, the tubes of the TPCCW heat exchanger should be inspected and degraded tubes should be plugged. It is inevitable for the materials of the components to be degraded as the power plants become older. The degradation accompanies increasing maintenance cost as well as creating safety issues. The materials and wall thickness of heat exchanger tubes in nuclear power plants are selected to withstand system temperature, pressure, and corrosion. However, tubes have experienced leaks and failures and plugged based upon eddy current testing (ET) results. There are some problems for plugging the heat exchanger tubes since the criterion and its basis are not clearly described. For this reason, the criteria for the tube wall thickness are addressed in order to operate the heat exchangers in nuclear power plant without trouble during the cycle. There are many codes and standards to be referred for calculating the minimum thickness of the heat exchanger tube in the designing stage. However, the codes and standards related to show the tube plugging criteria may not exist currently. In this paper, a method to establish the tube plugging criteria of BOP heat exchangers, which is based on the USNRC Regulatory Guide 1.121, is introduced and the tube plugging criteria for the TPCCW heat exchanger of Yonggwang NPP No. 1 and 2. This method relies on the similar plugging criteria used in the steam generator

  13. Natural circulation cooldown analysis for Yonggwang 3 and 4 per US NRC BTP RSB 5-1 requirements

    International Nuclear Information System (INIS)

    Seo, J.T.; Ko, C.S.; Ro, T.S.; Simoni, L.P.

    2004-01-01

    The Natural Circulation Cooldown (NCC) analysis from normal operations to shutdown cooling entry conditions for Yonggwang units 3 and 4 (YGN 3 and 4) was performed within the requirements of U.S. Nuclear Regulatory Commission (NRC) Branch Technical Position (BTP) RSB 5-1. The results showed that the YGN 3 and 4 can be cooled and depressurized to the shutdown entry conditions (350 deg F, 410 psia) within 16 hours under natural circulation condition requiring only 78% of the minimum condensate water storage capacity in conformance with BTP RSB 5-1 requirements. The results also demonstrated that the safety grade Reactor Coolant Gas Vent System (RCGVS) has sufficient capacity for the RCS depressurization as well as for the steam void control in the reactor vessel upper head region. (author)

  14. Verification and uncertainty evaluation of HELIOS/MASTER nuclear design system

    Energy Technology Data Exchange (ETDEWEB)

    Song, Jae Seung; Kim, J. C.; Cho, B. O. [Korea Atomic Energy Research Institute, Taejon (Korea)

    1999-03-01

    A nuclear design system HELIOS/MASTER was established and core follow calculations were performed for Yonggwang Unit 1 cycles 1 through 7 and Yonggwang Unit 3 cycles 1 through 2. The accuracy of HELIOS/MASTER system was evaluated by estimations of uncertainties of reactivity and peaking factors and by comparisons of the maximum differences of isothermal temperature coefficient, inverse boron worth and control rod worth with the CASMO-3/MASTER uncertainties. The reactivity uncertainty was estimated by 362 pcm, and the uncertainties of three-dimensional, axially integrated radial, and planar peaking factors were evaluated by 0.048, 0.034, and 0.044 in relative power unit, respectively. The maximum differences of isothermal temperature coefficient, inverse boron worth and control rod worth were within the CASMO-3/MASTER uncertainties. 17 refs., 17 figs., 10 tabs. (Author)

  15. The 4th surveillance test and evaluation of the reactor pressure vessel material (capsule W) of Younggwang nuclear power plant unit1

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Byoung Chul; Lee, Sam Lai; Choi, Kwon Jae [Korea Atomic Energy Research Institute, Taejeon (Korea)

    2001-08-01

    Surveillance testing for reactor vessel materials is performed in order to evaluate the irradiation embrittlement due to neutrons during operation and set the condition of safe operation of nuclear reactor. The 4th surveillance testing was performed completely by Korea Atomic Energy Research Institute at Taejeon after the capsule was transported from Yonggwang site including its removal from reactor. Fast neutron fluences for capsules were calculated and various testing including mechanical and chemistry analysis were performed in order to evaluate the integrity of Yonggwang unit 1 reactor vessel during the operation until life time. The evaluation results are as follows; Fast neutron fluences for capsules U, V, X and W are 5.555E+18, 1.662E+19, 3.358E+19, and 4.521E+19 n/cm{sup 2}, respectively. The bias factor, the ratio of measurement versus calculation, was 0.859 for the 1st through 4th testing and the calculational uncertainty, 11.80% satisfied the requirement of USNRC Reg.Guide 1.190, 20%. The best estimated neutron fluence for reactor vessel inside surface was 1.551E+19 n/cm{sup 2} based on the end of 12th fuel cycle and it was predicted that the fluences of vessel inside surface at 32, 40, 48 and 56EFPY would reach 3.929E+19, 4.880E+19, 5.831E+19 and 6.782E+19 n/cm{sup 2} based on the current calculation. The result through this analysis for Yonggwang unit 1 showed that there would be no problem for the pressurized thermal shock(PTS) during the operation until design life. 4 refs., 41 figs., 35 tabs. (Author)

  16. Analysis of Gamma Dose Rate Caused by Corrosion Products inside the Containment Building of Yonngwang Nuclear Power Plant Unit 3 During Shutdown Period

    Energy Technology Data Exchange (ETDEWEB)

    Ha, Wi Ho; Kim, Jae Cheon; Kim, Soon Young; Kim, Jong Kyung [Hanyang Univ., Seoul (Korea, Republic of)

    2005-07-01

    Occupational radiation exposure(ORE) of nuclear power plant(NPP) workers mainly occurs during the shutdown period. Major radioactive sources are the corrosion products released from the reactor coolant system(RCS). The corrosion products consist of circulating crud and deposited crud. Major radioactive corrosion products, {sup 58}Co and {sup 60}Co, are known to contribute approximately more than 70% of the total ORE. In this study, the corrosion products regarding cobalt were evaluated during the shutdown period, and gamma dose rates caused by them were calculated at the main working area inside the containment building of the Yonggwang NPP Unit 3.

  17. Study on application of operating experience to new nuclear power plant

    International Nuclear Information System (INIS)

    Hong, Nam Pyo

    1991-01-01

    From the standpoint of designing the nuclear power plant, nine operating units have been designed and constructed as turn-key base by foreign Nuclear Steam Supply System (NSSS) Suppliers or as component base by foreign Architect/Engineer companies. In case of the component base project, the owner of electric company generally has merits that owner's operational experiences can be effectively incorporated from the beginning stage of design by A/E. Even though six nuclear units, Kori Units 3 and 4, Yonggwang Units 1 and 2, and Ulchin Units 1 and 2, were designed as component base by foreign A/E's, operational experience feedback from Kori Unit 1, such as design improvement and system upgrade, could not be reflected, because the design process of the following units started well ahead before Kori Unit 1 operating experience is obtained enough to reflect on future nuclear power plant design. It can be stated that foreign A/E's used their experience in designing nuclear projects on very limited basis

  18. Development of an intelligent annunciation system for nuclear power plants

    International Nuclear Information System (INIS)

    Kim, Chang-Gi; Che, Myoung-Eun

    1997-01-01

    Yonggwang Nuclear Units 1 and 2 have developed an intelligent annunciation system to replace the existing obsolete system and to enhance operator support. The new annunciation system, which is currently operating at both units, uses the distributed control technology to enhance reliability and to provide versatile function to operations and maintenance personnel. The hardware and software configuration is based on redundancy so that a component failure would not initiate system malfunction. The data base of the new system provides, through a touch screen, an automatic alarm response procedure for selected alarms, which increases availability of information for plant operation. Other KEPCO nuclear units and the fossil plants are considering installing the new system. (author). 6 figs, 2 tabs

  19. Development of an intelligent annunciation system for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Chang-Gi; Che, Myoung-Eun [Instrumentation and Control, Yonggwang Nuclear Units 1 and 2, Korea Electric Power Corp. (Korea, Republic of)

    1997-09-01

    Yonggwang Nuclear Units 1 and 2 have developed an intelligent annunciation system to replace the existing obsolete system and to enhance operator support. The new annunciation system, which is currently operating at both units, uses the distributed control technology to enhance reliability and to provide versatile function to operations and maintenance personnel. The hardware and software configuration is based on redundancy so that a component failure would not initiate system malfunction. The data base of the new system provides, through a touch screen, an automatic alarm response procedure for selected alarms, which increases availability of information for plant operation. Other KEPCO nuclear units and the fossil plants are considering installing the new system. (author). 6 figs, 2 tabs.

  20. RCGVS design improvement and depressurization capability tests for Ulchin nuclear power plant units 3 and 4

    Energy Technology Data Exchange (ETDEWEB)

    Sung, Kang Sik; Seong, Ho Je; Jeong, Won Sang; Seo, Jong Tae; Lee, Sang Keun [Korea Power Engineering Company, Inc., Seoul (Korea, Republic of); Lim, Keun Hyo; Choi, Kwon Sik; Oh, Chul Sung [Korea Electric Power Cooperation, Taejon (Korea, Republic of)

    1999-12-31

    The Reactor Coolant Gas Vent System(RCGVS) design for Ulchin Nuclear Power Plant Units 3 and 4 (UCN 3 and 4) has been improved from the Yonggwang Nuclear Power Plant Units 3 and 4 (YGN 3 and 4) based on the evaluation results for depressurization capability tests performed at YGN 3 and 4. There has been a series of plant safety analyses for Natural Circulation Cooldown(NCC) event and thermo-dynamic analyses with RELAP5 code for the steam blowdown phenomena in order to optimize the orifice size of UCN 3 and 4 RCGVS. Based on these analyses results, the RCGVS orifics size for UCN 3 and 4 has been reduced to 9/32 inch from the 11/32 inch for YGN 3 and 4. The depressurization capability tests, which were performed at UCN 3 in order to verify the FSAR NCC analysis results, show that the RCGVS depressurization rates are being within the acceptable ranges. Therefore, it is concluded that the orificed flow path of UCN 3 and 4 RCGVS is adequately designed, and can provide the safety-grade depressurization capability required for a safe plant operation. 6 refs., 5 figs., 1 tab. (Author)

  1. RCGVS design improvement and depressurization capability tests for Ulchin nuclear power plant units 3 and 4

    Energy Technology Data Exchange (ETDEWEB)

    Sung, Kang Sik; Seong, Ho Je; Jeong, Won Sang; Seo, Jong Tae; Lee, Sang Keun [Korea Power Engineering Company, Inc., Seoul (Korea, Republic of); Lim, Keun Hyo; Choi, Kwon Sik; Oh, Chul Sung [Korea Electric Power Cooperation, Taejon (Korea, Republic of)

    1998-12-31

    The Reactor Coolant Gas Vent System(RCGVS) design for Ulchin Nuclear Power Plant Units 3 and 4 (UCN 3 and 4) has been improved from the Yonggwang Nuclear Power Plant Units 3 and 4 (YGN 3 and 4) based on the evaluation results for depressurization capability tests performed at YGN 3 and 4. There has been a series of plant safety analyses for Natural Circulation Cooldown(NCC) event and thermo-dynamic analyses with RELAP5 code for the steam blowdown phenomena in order to optimize the orifice size of UCN 3 and 4 RCGVS. Based on these analyses results, the RCGVS orifics size for UCN 3 and 4 has been reduced to 9/32 inch from the 11/32 inch for YGN 3 and 4. The depressurization capability tests, which were performed at UCN 3 in order to verify the FSAR NCC analysis results, show that the RCGVS depressurization rates are being within the acceptable ranges. Therefore, it is concluded that the orificed flow path of UCN 3 and 4 RCGVS is adequately designed, and can provide the safety-grade depressurization capability required for a safe plant operation. 6 refs., 5 figs., 1 tab. (Author)

  2. Axial power distribution calculation using a neural network in the nuclear reactor core

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Y H; Cha, K H; Lee, S H [Korea Electric Power Research Institute, Taejon (Korea, Republic of)

    1998-12-31

    This paper is concerned with an algorithm based on neural networks to calculate the axial power distribution using excore detector signals in the nuclear reactor core. The fundamental basis of the algorithm is that the detector response can be fairly accurately estimated using computational codes. In other words, the training set, which represents relationship between detector signals and axial power distributions, for the neural network can be obtained through calculations instead of measurements. Application of the new method to the Yonggwang nuclear power plant unit 3 (YGN-3) shows that it is superior to the current algorithm in place. 7 refs., 4 figs. (Author)

  3. Axial power distribution calculation using a neural network in the nuclear reactor core

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Y. H.; Cha, K. H.; Lee, S. H. [Korea Electric Power Research Institute, Taejon (Korea, Republic of)

    1997-12-31

    This paper is concerned with an algorithm based on neural networks to calculate the axial power distribution using excore detector signals in the nuclear reactor core. The fundamental basis of the algorithm is that the detector response can be fairly accurately estimated using computational codes. In other words, the training set, which represents relationship between detector signals and axial power distributions, for the neural network can be obtained through calculations instead of measurements. Application of the new method to the Yonggwang nuclear power plant unit 3 (YGN-3) shows that it is superior to the current algorithm in place. 7 refs., 4 figs. (Author)

  4. Development of RCM analysis software for Korean nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young Ho; Choi, Kwang Hee; Jeong, Hyeong Jong [Korea Electric Power Research Institute, Taejon (Korea, Republic of)

    1999-12-31

    A software called KEPCO RCM workstation (KRCM) has been developed to optimize the maintenance strategies of Korean nuclear power plants. The program modules of the KRCM were designed in a manner that combines EPRI methodologies and KEPRI analysis technique. The KRCM is being applied to the three pilot system, chemical and volume control system, main steam system, and compressed air system of Yonggwang Units 1 and 2. In addition, the KRCM can be utilized as a tool to meet a part of the requirements of maintenance rule (MR) imposed by U.S. NRC. 3 refs., 4 figs. (Author)

  5. Development of RCM analysis software for Korean nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young Ho; Choi, Kwang Hee; Jeong, Hyeong Jong [Korea Electric Power Research Institute, Taejon (Korea, Republic of)

    1998-12-31

    A software called KEPCO RCM workstation (KRCM) has been developed to optimize the maintenance strategies of Korean nuclear power plants. The program modules of the KRCM were designed in a manner that combines EPRI methodologies and KEPRI analysis technique. The KRCM is being applied to the three pilot system, chemical and volume control system, main steam system, and compressed air system of Yonggwang Units 1 and 2. In addition, the KRCM can be utilized as a tool to meet a part of the requirements of maintenance rule (MR) imposed by U.S. NRC. 3 refs., 4 figs. (Author)

  6. KHIC's experience in the design and fabrication of nuclear components

    International Nuclear Information System (INIS)

    Suh, S.-C.

    1992-01-01

    Since 1980, Korea Heavy Industries ampersand Construction Company, Ltd. (KHIC) has specialized in the design and equipment supply for nuclear power facilities in Korea. In April 1987, KHIC became the prime contractor for the construction of Yonggwang 3 ampersand 4 (YGN 3 ampersand 4) nuclear power project. Accordingly, KHIC's technological self-reliance capability for the manufacturing processes of the primary system equipment and components has increased from 18% during the initial stage of Yonggwang 1 ampersand 2 (YGN 1 ampersand 2) project to 63% for YGN 3 ampersand 4 project. Self-reliance capability for the secondary system equipment and components has increased from 28% to 84% during the same period of time as well. The ultimate goal is to achieve complete and total assurance that our products are of the finest quality in the nuclear industry in the world market. Henceforth, we will be able to guarantee complete customer satisfaction and reliability of our products with safety assurance and leading edge technology

  7. Investigations on the optimum design of chemical addition system for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Byong Hoon [Junior College of Inchon, Inchon (Korea, Republic of); Chung, Chang Kyu; Choi, Han Rim; Kim, Eun Kee; Ro, Tae Sun [Korea Power Engineering Company, Inc. Taejon (Korea, Republic of)

    1998-12-31

    Mixing characteristics of the chemical additives in the chemical injection tank of the chemical and volume control system(CVCS) were investigated for the Yonggwang Nuclear units 5 and 6. Numerical calculations were performed with a low-Reynolds number turbulence model. Studies were also conducted for the injection tank with a disk located at 1/4H, 2/4H, and 3/4H from the inlet in order to see the effect in the enhancement of chemical mixing. Results show that the optimum arrangement is to locate a disk close to the inlet. 10 refs., 4 figs. (Author)

  8. Investigations on the optimum design of chemical addition system for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Byong Hoon [Junior College of Inchon, Inchon (Korea, Republic of); Chung, Chang Kyu; Choi, Han Rim; Kim, Eun Kee; Ro, Tae Sun [Korea Power Engineering Company, Inc. Taejon (Korea, Republic of)

    1997-12-31

    Mixing characteristics of the chemical additives in the chemical injection tank of the chemical and volume control system(CVCS) were investigated for the Yonggwang Nuclear units 5 and 6. Numerical calculations were performed with a low-Reynolds number turbulence model. Studies were also conducted for the injection tank with a disk located at 1/4H, 2/4H, and 3/4H from the inlet in order to see the effect in the enhancement of chemical mixing. Results show that the optimum arrangement is to locate a disk close to the inlet. 10 refs., 4 figs. (Author)

  9. Modification of reference temperature program in reactor regulating system

    Energy Technology Data Exchange (ETDEWEB)

    Yu, Sung Sik; Lee, Byung Jin; Kim, Se Chang; Cheong, Jong Sik [Korea Power Engineering Company, Inc., Seoul (Korea, Republic of); Kim, Ji In; Doo, Jin Yong [Korea Electric Power Cooperation, Yonggwang (Korea, Republic of)

    1999-12-31

    In Yonggwang nuclear units 3 and 4 currently under commercial operation, the cold temperature was very close to the technical specification limit of 298 deg C during initial startup testing, which was caused by the higher-than-expected reactor coolant system flow. Accordingly, the reference temperature (Tref) program needed to be revised to allow more flexibility for plant operations. In this study, the method of a specific test performed at Yonggwang nuclear unit 4 to revise the Tref program was described and the test results were discussed. In addition, the modified Tref program was evaluated on its potential impacts on system performance and safety. The methods of changing the Tref program and the associated pressurizer level setpoint program were also explained. Finally, for Ulchin nuclear unit 3 and 4 currently under initial startup testing, the effects of reactor coolant system flow rate on the coolant temperature were evaluated from the thermal hydraulic standpoint and an optimum Tref program was recommended. 6 refs., 4 figs., 2 tabs. (Author)

  10. Modification of reference temperature program in reactor regulating system

    Energy Technology Data Exchange (ETDEWEB)

    Yu, Sung Sik; Lee, Byung Jin; Kim, Se Chang; Cheong, Jong Sik [Korea Power Engineering Company, Inc., Seoul (Korea, Republic of); Kim, Ji In; Doo, Jin Yong [Korea Electric Power Cooperation, Yonggwang (Korea, Republic of)

    1998-12-31

    In Yonggwang nuclear units 3 and 4 currently under commercial operation, the cold temperature was very close to the technical specification limit of 298 deg C during initial startup testing, which was caused by the higher-than-expected reactor coolant system flow. Accordingly, the reference temperature (Tref) program needed to be revised to allow more flexibility for plant operations. In this study, the method of a specific test performed at Yonggwang nuclear unit 4 to revise the Tref program was described and the test results were discussed. In addition, the modified Tref program was evaluated on its potential impacts on system performance and safety. The methods of changing the Tref program and the associated pressurizer level setpoint program were also explained. Finally, for Ulchin nuclear unit 3 and 4 currently under initial startup testing, the effects of reactor coolant system flow rate on the coolant temperature were evaluated from the thermal hydraulic standpoint and an optimum Tref program was recommended. 6 refs., 4 figs., 2 tabs. (Author)

  11. History on foundation of Korea nuclear power

    International Nuclear Information System (INIS)

    Park, Ik Su

    1999-12-01

    This reports the history on foundation of Korea nuclear power from 1955 to 1980, which is divided ten chapters. The contents of this book are domestic and foreign affairs before foundation of nuclear power center, establishment of nuclear power and research center, early activity and internal conflict about nuclear power center, study for nuclear power business and commercialization of the studying ordeal over nuclear power administration and new phase, dispute for jurisdiction on nuclear power business and the process, permission for nuclear reactor, regulation and local administration, the process of deliberation and decision of reactor 3. 4 in Yonggwang, introduction of nuclear reprocessing facilities and activities for social organization.

  12. Development of Megawatt Demand Setter for Plant Operating Flexibility

    International Nuclear Information System (INIS)

    Kim, Se Chang; Hah, Yeong Joon; Song, In Ho; Lee, Myeong Hun; Chang, Do Ik; Choi, Jung In

    1993-05-01

    The Conceptual design of the Megawatt Demand Setter (MDS) is presented for the Korean Standardized Nuclear Power Plant. The MDS is a digital supervisory limitation system. The MDS assures that the plant does not exceed the operating limits by regulating the plant operations through monitoring the operating margins of the critical parameters. MDS is aimed at increasing the operating flexibility which allow the nuclear plant to meet the grid demand in very efficient manner. It responds to the grid demand without penalizing plant availability by limiting the load demand when the operating limits are approached or violated. MDS design concepts were tested using simulation responses of Yonggwang Units 3, 4. The design of the Yonggwang Units 3, 4 would be used as a reference which designs of Korean Standardized Nuclear Power Plants would be based upon. The simulation results illustrate that the MDS can be used to improve operating flexibility. (Author)

  13. Thermal Analysis for Environmental Qualification of Kori Nuclear power plant unit 3 and 4

    International Nuclear Information System (INIS)

    Seo, Kwi Hyun; Byun, Choong Sup; Song, Dong Soo

    2006-01-01

    This paper shows the temperature profiles of safety related electrical equipment exposed to MSLB inside containment. It must be demonstrated that the LOCA qualification conditions exceed or are equivalent to the maximum calculated MSLB conditions. COPATTA as Bechtel's vendor code is used for the containment pressure and temperature prediction in power uprating project for Kori 3,4 and Yonggwang 1,2 nuclear power plants(NPPs). However, CONTEMPT-LT/028 is used for calculating the containment pressure and temperatures in equipment qualification project for the same NPPs. Power uprating code that is, COPATTA benchmarking study performed in six equipment at saturation temperature and surface temperature. Specially, thermal analysis carefully investigate that view point environmental qualification and NUREG- 0588 be mentioned in regard to safety-related heat sink it boundary condition or geometry information

  14. Thermal Analysis for Environmental Qualification of Kori Nuclear power plant unit 3 and 4

    Energy Technology Data Exchange (ETDEWEB)

    Seo, Kwi Hyun [ENERGEO Inc., Sungnam (Korea, Republic of); Byun, Choong Sup; Song, Dong Soo [KEPRI, Taejon (Korea, Republic of)

    2006-07-01

    This paper shows the temperature profiles of safety related electrical equipment exposed to MSLB inside containment. It must be demonstrated that the LOCA qualification conditions exceed or are equivalent to the maximum calculated MSLB conditions. COPATTA as Bechtel's vendor code is used for the containment pressure and temperature prediction in power uprating project for Kori 3,4 and Yonggwang 1,2 nuclear power plants(NPPs). However, CONTEMPT-LT/028 is used for calculating the containment pressure and temperatures in equipment qualification project for the same NPPs. Power uprating code that is, COPATTA benchmarking study performed in six equipment at saturation temperature and surface temperature. Specially, thermal analysis carefully investigate that view point environmental qualification and NUREG- 0588 be mentioned in regard to safety-related heat sink it boundary condition or geometry information.

  15. History on foundation of Korea nuclear energy

    International Nuclear Information System (INIS)

    Park, Ik Su

    1999-12-01

    This book reports the history of establishment of Korea nuclear power. It is divided into twelve chapters, which deals with situation of domestic and foreign countries before establishment of nuclear power agency, foundation of nuclear power agency and nuclear power research center, the early activity of nuclear power agency and internal conflict, research for nuclear power business and commercialization, new phase and ordeal of administration of nuclear power, the process of nuclear power business, permission and regulation on nuclear power, building of the third and fourth reactor in Yonggwang and antinuclear campaign, establishment of nuclear power plant and commission, introduction of nuclear reprocessing facilities and frustration of nuclear weapon, the process on KEDO, association and social organization related nuclear power.

  16. Software development for simplified performance tests and weekly performance check in Younggwang NPP Unit 3 and 4

    International Nuclear Information System (INIS)

    Hur, K. Y.; Jang, S. H.; Lee, J. W.; Kim, J. T.; Park, J. C.

    2002-01-01

    This paper covers the current status of turbine cycle performance test in nuclear power plants and the software development which can solve some shortcomings related to performance tests. The software developed is for simplified performance tests and weekly performance checks in Yonggwang nuclear power plant unit 3 and 4. This software includes the requirements from the efficiency division for the consistency with actual performance analysis work and the usability of the collected performance test data. From the working survey, we identify the difference between the embedded performance analysis modules and the actual performance analysis work. This software helps operation or maintenance personnel to reduce work load, to support the trend analysis of essential parameters in a turbine cycle, and to utilize the correction curves for the decision-making in their work

  17. Development of reliability program for emergency diesel generators in domestic nuclear power plants

    International Nuclear Information System (INIS)

    Kim, Young Ho; Jung, Hyun Jong; Choi, Kwang Hee; Hong, Seoung Yeul

    2001-01-01

    Surveillance tests of Emergency Diesel Generators (EDGs) in Nuclear Power Plants (NPPs) have been conducted periodically to verify the reliability and integrity of the EDGs, however, it was found that these surveillance methods were so conservative and severe as to accelerate the degradation of the EDGs. Hence, new regulatory guideline, Reg. Guide 1.9 Rev. 3, was established by the U.S. NRC to resolve these problems. But it requires the additional implementation of reliability program of the EDGs to improve the actual reliability of them. In Korea, the EDGs of Yonggwang nuclear units 3 and 4 were the first plant applying new Reg. guide 1.9 rev.3 and implementing EDG reliability program. Furthermore it is expected that new guideline for the EDGs will be applied to other EDGs of Korean NPPs. In this paper, this reliability program is described, and it can be used as a reference for other EDGs in Korean NPPs

  18. The current status and future prospects of the Korean nuclear power industry

    International Nuclear Information System (INIS)

    Lee, J. J.

    2006-01-01

    Recently, countries all over the world are becoming aware of the values and importance of nuclear energy which can help respond to energy crises caused by a sharp rise in oil prices and protect the earth from global warming. Since 1978, when Kori Unit 1(587MW), opened the nuclear generation era as a semi-domestic energy resource in Korea which is absolutely in short supply of energy, nuclear power generation in Korea has developed continuously for the past 28 years. Four new units including the Yonggwang 5 and 6 and Ulchin 5 and 6 have been successfully completed, raising the total nuclear installed capacity to 17,716MW from 20 units. At present, the nuclear generation in Korea is stably supplying about 40% of total electric generation, which is the fundamental energy of the nation, supporting the dynamic economic growth of Korea. In particular, Korean nuclear industry has been achieving excellent performance in nuclear power plant operation. The average capacity factor in 2005 hit the record of 95.5%, surpassing the previous record of 94.2% in 2003 in two years. Kori Unit 4 and another four units were listed at the top five in the capacity factor rating list of 2005 released by Nucleonics Week. In 2005, the site for radioactive waste disposal, which had been a long-cherished hope and the largest pending issue of the nuclear industry, was successfully selected in Korea through resident ballot as the first case of a national policy project, and as such, a national agenda was solved after 19 long years. Such a method in site selection has a significant meaning and establishes an excellent precedence; a large national policy project was decided upon by the residents themselves. As one of the model countries of building and operating nuclear power plants and technological independence, Korea is willing to contribute to the common goals of the world nuclear circle which can be summarized into energy security and environment preservation, by sharing accumulated

  19. Nuclear power in the United States

    International Nuclear Information System (INIS)

    Johnston, J.B.

    1985-01-01

    All over the world except in the United States, nuclear energy is a low cost, secure, environmentally acceptable form of energy. In the United States, civilian nuclear power is dead. 112 nuclear power plants have been abandoned or cancelled in the last decade, and there has been no new order for nuclear plants since 1978. It will be fortunate to have 125 operating nuclear plants in the United States in the year 2000. There are almost 90 completed nuclear power plants and about 45 under construction in the United States, but several of those under construction will eventually be abandoned. About 20 % of the electricity in the United States will be generated by nuclear plants in 2000 as compared with 13 % supplied in the last year. Under the present regulatory and institutional arrangement, American electric utilities would not consider to order a new nuclear power plant. Post-TMI nuclear plants became very expensive, and there is also ideological opposition to nuclear power. Coal-firing plants are also in the similar situation. The uncertainty about electric power demand, the cost of money, the inflation of construction cost and regulation caused the situation. (Kako, I.)

  20. 76 FR 40754 - Duke Energy Carolinas, LLC Catawba Nuclear Station, Units 1 and 2; McGuire Nuclear Station, Units...

    Science.gov (United States)

    2011-07-11

    ... NUCLEAR REGULATORY COMMISSION [NRC-2011-0100; Docket Nos. 50-413 and 50-414; Docket Nos. 50-369 and 50-370; Docket Nos. 50-269, 50-270, And 50-287] Duke Energy Carolinas, LLC Catawba Nuclear Station, Units 1 and 2; McGuire Nuclear Station, Units 1 and 2; Oconee Nuclear Station, Units 1, 2, and 3; Notice...

  1. Nuclear development in the United States

    International Nuclear Information System (INIS)

    Brewer, S.

    1983-01-01

    The history of the nuclear development in the United States has been one of international cooperation relations so far. The United States is to offer the technical information on atomic energy utilization to foreign countries in exchange for the guarantee that they never attempt to have or develop nuclear weapons. Actually, the United States has supplied the technologies on nuclear fuel cycle and other related fields to enable other countries to achieve economical and social progress. The Department of Energy clarified the public promise of the United States regarding the idea of international energy community. The ratio of nuclear power generation to total electric power supply in the United States exceeded 12%, and will exceed 20% by 1990. Since 1978, new nuclear power station has not been ordered, and some of the contracted power stations were canceled. The atomic energy industry in the United States prospered at the beginning of 1970s, but lost the spirit now, mainly due to the institutional problems rather than the technical ones. As the policy of the government to eliminate the obstacles, the improvement of the procedure for the permission and approval, the establishment of waste disposal capability, the verification of fast breeder reactor technology and the promotion of commercial fuel reprocessing were proposed. The re-establishment of the United States as the reliable supplier of atomic energy service is the final aim. (Kako, I.)

  2. ABB.-Combustion Engineering's Experience in Nuclear Power Plant Engineering and Construction in Korea

    International Nuclear Information System (INIS)

    Veris, James W.

    1992-01-01

    The Yonggwang Nuclear Project is a milestone project for the Korean Nuclear Industry. The Project has the two objectives of obtaining self-reliance in all aspects of nuclear technology and of constructing two modern nuclear power plants under the leadership of Korean companies acting as prime contractors. ABB.-Combustion Engineering 1000 MW System 80+ TM was chosen in 1987 as the NSLS design to meet these two objectives. This paper summarizers the significant experiences and lessons learned through the first four years of the Project as well as identifying implications for such future projects. The unique challenges of the project are identified and an evaluation of the experiences in the technology, self-reliance program and in the design and manufacturing processes will be made

  3. Architecture of nuclear power units

    International Nuclear Information System (INIS)

    Malaniuk, B.

    1981-01-01

    Nuclear units with circulation cooling using cooling towers are dominating points of the landscape. The individual cooling towers or pairs of cooling towers should be situated in the axes of double units and should also linearly be arranged, rhythmically in the respective zone. Examples are shown of the architectural designs of several nuclear power plants in the USA, the UK, the USSR, France, the FRG and Italy. (H.S.)

  4. Science, society, and America's nuclear waste: Unit 1, Nuclear waste

    International Nuclear Information System (INIS)

    1992-01-01

    This is unit 1 in a four-unit secondary curriculum. It is intended to provide information about scientific and societal issues related to the management of spent nuclear fuel from generation of electricity at nuclear powerplants and high-level radioactive waste from US national defense activities. The curriculum, supporting classroom activities, and teaching materials present a brief discussion of energy and electricity generation, including that produced at nuclear powerplants; information on sources, amounts, location, and characteristics of spent nuclear fuel and high-level radioactive waste; sources, types and effects of radiation; US policy for managing and disposing of spent nuclear fuel and high-level radioactive waste and what other countries are doing; and the components of the nuclear waste management system

  5. Physical protection of nuclear operational units

    International Nuclear Information System (INIS)

    1981-07-01

    The general principles of and basic requirements for the physical protection of operational units in the nuclear field are established. They concern the operational units whose activities are related with production, utilization, processing, reprocessing, handling, transport or storage of materials of interest for the Brazilian Nuclear Program. (I.C.R.) [pt

  6. The assessment of health effect of Yonggwang site using the MACCS code

    International Nuclear Information System (INIS)

    Jeong, Dognhan Yu; Kim, Seiung Hwan; Han, Byoung Sub; Song, Jong Soon

    1996-12-01

    The health effect assessment near the Yonggwang site by using IPE results and its site data was performed. The health effect assessment is an important part of consequence analysis of a nuclear power plant site. The MACCS code developed by SNL was used in the assessment. The necessary input data are source term data, meteorological data, population data, and detailed information about the release of radionuclides. The core inventory data for end-of-cycle are calculated by ORIGEN2 code for conservatism because fission product buildup is greatest at end-of-cycle conditions. Meteorological and population data was derived from the FSAR and environmental impact statement report, and source term release data was derived from the IPE report. by using the MACCS code, the CCDF is obtained as a result and economic impact analysis is also possible. First of all, the average value of early fatality was estimated by changing the initial value of random numbers. The average value obtained from 10 trials is in the rage between 10 -4 and 10 -3 and have a log-uniform distribution. More than 10 data are necessary in order to have a meaningful value statistically. And the calculations about early fatality, early injury, risks of early fatality, population dose within 16.0km, population risk for early fatality within 8.0km are performed. In all cases, STC-3 is the dominant contributor (about 70%), and STC-14 is the next important contributor. Therefore, in case of consequence analysis resulting from internal events, the analysis based on STC-3 which is the failure of early containment isolation is very important. Based on the calculation of CCDF for each risk measure, it is shown that CCDF has a slow slope and thus wide probability distribution in cases of early fatality, early injury, total early fatality risk, and total weighted early fatality risk, And in cases of cancer fatality and population dose within 48 km and 80km, the CCDF curve have a steep slope and thus narrow

  7. Status of Korean nuclear industry and Romania-Korea cooperation in nuclear field

    International Nuclear Information System (INIS)

    Myung-Key, Lee

    2005-01-01

    Current status of electric power in Korea is characterized by the end of August 2004 by a total installed capacity of about 62,000 MW while the total electricity generation is about 342,000 GWh. The installed capacity of nuclear power is 17,716 MW, sharing 29% of total installed capacity and presenting 38% of total electricity generation in Korea. In accordance with the provisions of the Long Term Energy Plan during the past 40 years, the installed capacity in Korea has been drastically increased. In the 1960's, major sources of electricity generation were locally-mined anthracite coal and hydro, but in the 1970's it was the imported oil. However, through diversification policy the dependence of the imported oil has been rapidly reduced and the share of coal , gas and nuclear generation has been steadily increased. According to the long-term power development plan updated last year, which is extended to 2017, the installed capacity in the year 2017 will be about 88,000 MW. At that time nuclear power will become the largest, sharing 30% and the shares of coal and gas fired power will be steadily decreased. Concerning the Nuclear Power Projects, there are four different nuclear power sites along the coast of Korean peninsula, Yonggwang, Kori, Wolsong and Ulchin. In addition to the currently operating 20 nuclear power plants, there are 6 more nuclear power plants under construction at Shin-Wolsong and Shin-Kori sites. Our efforts to enhance the technology, economy and safety of the nuclear power plants will be continuously pursued. Wolsong unclear power units 1, 2, 3 and 4 are CANDU type reactors which are same type as Romanian Cernavoda nuclear power plants. Operational performance, in terms of capacity factor of NPPs, has remained well above the world average and recorded 91.4% last year. Also, last year, the frequency of unplanned trip was 0.6 time per reactor. In 2004, ten NPPs achieved OCTF, which stands for One Cycle Trouble Free in 2004. Wolsong unit 1

  8. Assessment of PASS Effectiveness under Severe Accidents in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Choi, Yu Jung; Lee, Sung Bok; Kim, Hyeong Taek; Lee, Jin Yong

    2008-01-01

    Following the accident at Three Mile Island Unit 2 (TMI-2) on March 28, 1979, the USNRC formed a lessons-learned Task Force to identify and evaluate safety concerns originating with the TMI-2 accident. NUREG-0578 documented the results of the task force effort. One of the recommendations of the task force was for licensees to upgrade the capability to obtain samples from the reactor coolant system and containment atmosphere under high radioactivity conditions and to provide the capability for chemical and spectral analyses of high-level samples on site. NUREG-0737 contained the details of the TMI recommendations that were to be implemented by the licensees. Additional criteria for post accident sampling system(PASS) were issued by Regulatory Guide 1.97. As the results, PASS has been installed on nuclear power plants(NPPs) in Korea as well as United States. However, significant improvements have been achieved since the TMI-2 accident in the areas of understanding risks associated with nuclear plant operations and developing better strategies for managing the response to potential severe accidents at NPPs. Thus, the requirements for PASS have been re-evaluated in some reports. According to the reports, the samples and measurements from PASS do not contribute significantly to emergency management response to severe accidents due to the long analyzing time, 3 hours. Hence, this paper focused on the development of the quantitative analysis methodology to analyze the sequence of the severe accident in Yonggwang nuclear power plants (YGN) and presented the results of the analysis according to the developed methodology

  9. Snapshot analysis for rhodium fixed incore detector using BEACON methodology

    International Nuclear Information System (INIS)

    Cha, Kyoon Ho; Choi, Yu Sun; Lee, Eun Ki; Park, Moon Ghu; Morita, Toshio; Heibel, Michael D.

    2004-01-01

    The purpose of this report is to process the rhodium detector data of the Yonggwang nuclear unit 4 cycle 5 core for the measured power distribution by using the BEACON methodology. Rhodium snapshots of the YGN 4 cycle 5 have been analyzed by both BEACON/SPINOVA and CECOR to compare the results of both codes. By analyzing a large number of snapshots obtained during normal plant operation. Reviewing the results of this analysis, the BEACON/SPNOVA can be used for the snapshot analysis of Korean Standard Nuclear Power (KSNP) plants

  10. Nuclear Data Unit correspondents for the exchange of nuclear data information

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1968-04-15

    This list serves as a basis for the distribution of documents originated by or for the International Nuclear Data Committee, and includes the names of all INDC members, liaison officers and correspondents of the Nuclear Data Unit. The IAEA Nuclear Data Unit tries to maintain this list up-to-date in order to facilitate an efficient interchange of information on nuclear data topics. The recipients of this list are encouraged to inform the Nuclear Data Unit of any corrections, additions and deletions deemed necessary. Because of the variety of document origins and functions, and the number of countries served by this list, each addressee is assigned a seven-letter distribution code, shown to the left of each name, which indicates the categories of documents he receives. The names appear under three categories, member states, international organizations and non-member states, and are listed in alphabetical order within each state or organization. The main list is followed by seven shorter lists, indicating the names of individuals in each distribution category, and the total number of individuals in each category.

  11. Nuclear Data Unit correspondents for the exchange of nuclear data information

    International Nuclear Information System (INIS)

    1968-04-01

    This list serves as a basis for the distribution of documents originated by or for the International Nuclear Data Committee, and includes the names of all INDC members, liaison officers and correspondents of the Nuclear Data Unit. The IAEA Nuclear Data Unit tries to maintain this list up-to-date in order to facilitate an efficient interchange of information on nuclear data topics. The recipients of this list are encouraged to inform the Nuclear Data Unit of any corrections, additions and deletions deemed necessary. Because of the variety of document origins and functions, and the number of countries served by this list, each addressee is assigned a seven-letter distribution code, shown to the left of each name, which indicates the categories of documents he receives. The names appear under three categories, member states, international organizations and non-member states, and are listed in alphabetical order within each state or organization. The main list is followed by seven shorter lists, indicating the names of individuals in each distribution category, and the total number of individuals in each category

  12. United Campuses to Prevent Nuclear War: Nuclear War Course Summaries.

    Science.gov (United States)

    Journal of College Science Teaching, 1983

    1983-01-01

    Briefly describes 46 courses on nuclear war available from United Campuses to Prevent Nuclear War (UCAM). These courses are currently being or have been taught at colleges/universities, addressing effects of nuclear war, arms race history, new weapons, and past arms control efforts. Syllabi (with assignments/reading lists) are available from UCAM.…

  13. Status of nuclear engineering education in the United States

    International Nuclear Information System (INIS)

    Brown, G.J.

    2000-01-01

    Nuclear engineering education in the United States is reflective of the perceived health of the nuclear electric power industry within the country. Just as new commercial reactor orders have vanished and some power plants have shut down, so too have university enrollments shrunk and research reactors closed. This decline in nuclear trained specialists and the disappearance of the nuclear infrastructure is a trend that must be arrested and reversed if the United States is to have a workforce capable of caring for a nuclear power industry to not only meet future electric demand but to ensure that the over 100 existing plants, their supporting facilities and their legacy in the form of high level waste and facility clean-up are addressed. Additionally, the United States has an obligation to support and maintain its nuclear navy and other defence needs. And, lastly, if the United States is to have a meaningful role in the international use of nuclear power with regard to safety, non-proliferation and the environment, then it is imperative that the country continues to produce world-class nuclear engineers and scientists by supporting nuclear engineering education at its universities. The continued support of the federal government. and industry for university nuclear engineering and nuclear energy research and development is essential to sustain the nuclear infrastructure in the United States. Even with this support, and the continued excellent operation of the existing fleet of nuclear electric power plants, it is conceivable that nuclear engineering as an academic discipline may fall victim to poor communications and a tarnished public image. What is needed is a combination of federal and industrial support along with the creativity of the universities to expand their offerings to include more than power production. The objective is a positive message on careers in nuclear related fields, and recognition of the important role of nuclear energy in meeting the country

  14. Estimation of the Power Peaking Factor in a Nuclear Reactor Using Support Vector Machines and Uncertainty Analysis

    International Nuclear Information System (INIS)

    Bae, In Ho; Na, Man Gyun; Lee, Yoon Joon; Park, Goon Cherl

    2009-01-01

    Knowing more about the Local Power Density (LPD) at the hottest part of a nuclear reactor core can provide more important information than knowledge of the LPD at any other position. The LPD at the hottest part needs to be estimated accurately in order to prevent the fuel rod from melting in a nuclear reactor. Support Vector Machines (SVMs) have successfully been applied in classification and regression problems. Therefore, in this paper, the power peaking factor, which is defined as the highest LPD to the average power density in a reactor core, was estimated by SVMs which use numerous measured signals of the reactor coolant system. The SVM models were developed by using a training data set and validated by an independent test data set. The SVM models' uncertainty was analyzed by using 100 sampled training data sets and verification data sets. The prediction intervals were very small, which means that the predicted values were very accurate. The predicted values were then applied to the first fuel cycle of the Yonggwang Nuclear Power Plant Unit 3. The root mean squared error was approximately 0.15%, which is accurate enough for use in LPD monitoring and for core protection that uses LPD estimation

  15. Science, society, and America's nuclear waste: Unit 3, The Nuclear Waste Policy Act

    International Nuclear Information System (INIS)

    1992-01-01

    This is the 3rd unit, (The Nuclear Waste Policy Act) a four-unit secondary curriculum. It is intended to provide information about scientific and societal issues related to the management of spent nuclear fuel from generation of electricity at nuclear powerplants and high-level radioactive waste from US national defense activities. The curriculum, supporting classroom activities, and teaching materials present a brief discussion of energy and electricity generation, including that produced at nuclear powerplants; information on sources, amounts, location, and characteristics of spent nuclear fuel and high-level radioactive waste; sources, types and effects of radiation; US policy for managing and disposing of spent nuclear fuel and high-level radioactive waste and what other countries are doing; and the components of the nuclear waste management system

  16. Science, society, and America's nuclear waste: Unit 3, The Nuclear Waste Policy Act

    International Nuclear Information System (INIS)

    1992-01-01

    This teachers guide is unit 3, the nuclear waste policy act, in a four-unit secondary curriculum. It is intended to provide information about scientific and societal issues related to the management of spent nuclear fuel from generation of electricity at nuclear powerplants and high-level radioactive waste from US national defense activities. The curriculum, supporting classroom activities, and teaching materials present a brief discussion of energy and electricity generation, including that produced at nuclear power plants; information on sources, amounts, location, and characteristics of spent nuclear fuel and high-level radioactive waste; sources, types and effects of radiation; US policy for managing and disposing of spent nuclear fuel and high-level radioactive waste and what other countries are doing; and the components of the nuclear waste management system

  17. IAEA Completes Nuclear Security Review Mission in United States

    International Nuclear Information System (INIS)

    2013-01-01

    Full text: A team of nuclear security experts led by the International Atomic Energy Agency (IAEA) today completed a mission to review nuclear security practices of civil nuclear facilities licensed by the United States Nuclear Regulatory Commission (NRC). Conducted at the U.S. Government's request, the two-week International Physical Protection Advisory Service (IPPAS) mission reviewed the United States' nuclear security-related legislative and regulatory framework. As part of this work, the IPPAS team, led by John O'Dacre of Canada and comprising nine experts from eight IAEA Member States, met with NRC officials and reviewed the physical protection systems at the Center for Neutron Research (NCNR) at the National Institute of Standards and Technology. The IPPAS team concluded that nuclear security within the U.S. civil nuclear sector is robust and sustainable and has been significantly enhanced in recent years. The team identified a number of good practices in the nation's nuclear security regime and at the NCNR. The IPPAS team also made a recommendation and some suggestions for the continuing improvement of nuclear security overall. The mission in the United States was the 60th IPPAS mission organized by the IAEA. 'Independent international peer reviews such as IAEA IPPAS missions are increasingly being recognized for their value as a key component for exchanges of views and advice on nuclear security measures', said Khammar Mrabit, Director of the IAEA Office of Nuclear Security. 'The good practices identified during this mission will contribute to the continuous improvements of nuclear security in other Member States'. The IPPAS team provided a draft report to the NRC and will submit a final report soon. Because it contains security-related information about a specific nuclear site, IPPAS reports are not made public. 'The IPPAS programme gives us a chance to learn from the experience and perspective of our international partners', said NRC Chairman Allison M

  18. United States - Japanese nuclear relations: implications for the pacific region

    International Nuclear Information System (INIS)

    Suttmeier, R.P.

    1980-01-01

    The initiation of a new approach to non-proliferation policy by the United States in 1977 was the most upsetting development in the history of US-Japanese nuclear relations. The policy has seemingly altered Japanese views of its own nuclear future very little, yet it has altered the tone of the nuclear relationship with the United States. Recent Japanese nuclear power developments, both technical and administrative, are outlined and the prospects for the future of the United States-Japanese nuclear relationship and for Pacific regional cooperation assessed. Issues of importance in the relationship include reprocessing - enrichment, plutonium management, spent fuel and waste management and uranium supplies

  19. 76 FR 24538 - Duke Energy Carolinas, LLC; Catawba Nuclear Station, Units 1 and 2; McGuire Nuclear Station...

    Science.gov (United States)

    2011-05-02

    ... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-413 and 50-414; NRC-2011-0100; Docket Nos. 50-369 and 50-370; Docket Nos. 50-269, 50-270, and 50-287] Duke Energy Carolinas, LLC; Catawba Nuclear Station, Units 1 and 2; McGuire Nuclear Station, Units 1 and 2; Oconee Nuclear Station, Units 1, 2, and 3...

  20. The nuclear energy in the United Kingdom

    International Nuclear Information System (INIS)

    2006-02-01

    With challenges like the climatic change, the hydrocarbons prices increase and the energy supply security, the nuclear park is becoming a decisive and an urgent question in the United Kingdom. The author proposes an historical aspect of the nuclear energy in UK, the actors of the today nuclear industry and the technologies used in 2006, the radioactive wastes management, the programs of the future and the british opinion on the nuclear. (A.L.B.)

  1. Fuqing nuclear power of nuclear steam turbine generating unit No.1 at the implementation and feedback

    International Nuclear Information System (INIS)

    Cao Yuhua; Xiao Bo; He Liu; Huang Min

    2014-01-01

    The article introduces the Fuqing nuclear power of nuclear steam turbine generating unit no.l purpose, range of experience, experiment preparation, implementation, feedback and response. Turn of nuclear steam turbo-generator set flush, using the main reactor coolant pump and regulator of the heat generated by the electric heating element and the total heat capacity in secondary circuit of reactor coolant system (steam generator secondary side) of saturated steam turbine rushed to 1500 RPM, Fuqing nuclear power of nuclear steam turbine generating unit no.1 implementation of the performance of the inspection of steam turbine and its auxiliary system, through the test problems found in the clean up in time, the nuclear steam sweep turn smooth realization has accumulated experience. At the same time, Fuqing nuclear power of nuclear steam turbine generating unit no.1 at turn is half speed steam turbine generator non-nuclear turn at the first, with its smooth realization of other nuclear power steam turbine generator set in the field of non-nuclear turn play a reference role. (authors)

  2. Reload safety evaluation report for Yonggwang nuclear power plant unit 1, cycle 8

    International Nuclear Information System (INIS)

    Lee, Won Jae; Yoon, Kyung Ho; Cho, Young Chul; Kim, Jae Hak; Um, Kil Sup; Choi, Han Rim; Kim, Ki Hang; Sung, Kang Sik

    1993-09-01

    This report presents a reload safety evaluation for YGN-1, cycle 8 and demonstrates that the core being entirely composed of KOFA as described in the report will not adversely affect the safety of the public and the plant. All of the accidents comprising the licensing bases which could potentially be affected by the fuel reload have been reviewed for the cycle 8 core and results are described in the report. (Author) 1 ref., 4 figs., 5 tabs

  3. Reload safety evaluation report for yonggwang nuclear power plant unit 2 cycle 7

    International Nuclear Information System (INIS)

    Zee, Sung Kyun; Choi, Gyoo Hwan; Lee, Ki Bog; Park, Sang Yoon

    1993-01-01

    This report presents the reload safety evaluation for YGN-2, Cycle 7 and demonstrates that the reactor core being entirely composed of KOFA as described below will not adversely affect the safety of the public and the plant. All of the accidents comprising the licensing bases which would potentially be affected by the reload fuel assemblies have been reviewed for the Cycle 7 core design described herein. (Author)

  4. Reload safety evaluation report for yonggwang nuclear power plant unit 1 cycle 7

    International Nuclear Information System (INIS)

    Park, Chan Oh; Kwon, Tae Je; Park, Sang Yoon; Sung, Kang Sik; Kim, Ki Hang; Yim, Jeong Sik; Kim, Du Ill; Choi, Han Rim; Bae, Hoo Gun

    1992-06-01

    This report presents the reload safety evaluation for YGN-1, Cycle 7 and demonstrates that the reactor core being entirely composed of KOFA as discribed below will not adversely affect the safety of the public and the plant. All of the accidents comprising the licensing bases which could potentially be affected by the reload fuel assemblies have been reviewed for the Cycle 7 core and results are described in this report. (Author)

  5. Reload safety evaluation report for Yonggwang nuclear power plant unit 1, cycle 9

    International Nuclear Information System (INIS)

    Cho, Young Chul; Nam, Kee Il; Kim, Ki Hang; Suh, Jung Min; Um, Kil Sup; Ban, Chang Hwan; Bae, Hoo Gun

    1995-02-01

    This report presents a reload safety evaluation for YGN-1, Cycle 9 and demonstrates that the core being entirely composed of KOFA as described in the report will not adversely affect the safety of the public and the plant. All of the accidents comprising the licensing bases which could potentially be affected by the fuel reload have been reviewed for the Cycle 9 core and results are described in this report. (Author) 1 refs., 3 figs., 6 tabs

  6. Science, Society, and America's Nuclear Waste: The Nuclear Waste Policy Act, Unit 3. Teacher Guide. Second Edition.

    Science.gov (United States)

    Department of Energy, Washington, DC. Office of Civilian Radioactive Waste Management, Washington, DC.

    This guide is Unit 3 of the four-part series, Science, Society, and America's Nuclear Waste, produced by the U.S. Department of Energy's Office of Civilian Radioactive Waste Management. The goal of this unit is to identify the key elements of the United States' nuclear waste dilemma and introduce the Nuclear Waste Policy Act and the role of the…

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

    International Nuclear Information System (INIS)

    He Liu; Xiao Bo; Song Yumeng

    2014-01-01

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

  8. Margin benefit assessment of the YGN 3 cycle 1 fxy error files for COLSS and CPC overall uncertainty analyses

    International Nuclear Information System (INIS)

    Yoon, Rae Young; In, Wang Kee; Auh, Geun Sun; Kim, Hee Cheol; Lee, Sang Keun

    1994-01-01

    Margin benefits are quantitatively assessed for the Yonggwang Unit 3 (YGN 3) Cycle 1 planar radial peaking factor (Fxy) error files for each time-in-life, i.e., BOC, IOC, MOC and EOC. The generic Fxy error file (FXYMEQO) is presently used for Yonggwang Unit 3 Cycle 1 COLSS (Core Operating Limit Supervisory System) and CPC (Core Protection Calculator) Overall Uncertainty Analyses (OUA). However, because this file is more conservative than the plant/cycle specific Fxy error files, COLSS and CPC thermal margins (DNB-OPM) for the generic Fxy error file are less than those of the plant/cycle specific Fxy error file. Therefore, the YGN 3 Cycle 1 Fxy error files were generated and analyzed by the modified codes for Yonggwang Plants. The YGN 3 Cycle 1 Fxy error files gave the increased thermal margin by about 1% for COLSS and CPC, respectively

  9. Operating performance of LWR nuclear generating units

    International Nuclear Information System (INIS)

    Pia, S.

    1984-01-01

    This work aims at reviewing, on the basis of historical data, the operational problem areas which explain the degree of availability and productivity achieved up to now by nuclear power plants in commercial operation in the world. The operating performance data of nuclear power plants area analysed with respect to plant type, size and other significant reference parameters and they are evaluated also by comparison with fossil generating unit data. Major performance indices data are presented for both nuclear and fossil units type and distribution of outage causes. Unplanned full outages caused by nuclear power plant equipment and components failure are particulary emphasized. The trend for unplanned full outages due to the failure of components shows decreasing numerical values in 1981 with respect to the previous years. But this result should be weighed with the increasing plant unavailability hours needed for maintenance and repair action (chiefly preventive maintenance on critical components). This means that the number and downtime of forced outage must be drastically reduced for economic reasons (production losses and problems associated with the unavailable unit unplanned replacement) as well as for plant safe and reliable operation (sudden unavailability of key components and frequency of transients associated with plant shutdown and routine startup operation)

  10. Science, Society, and America's Nuclear Waste: Nuclear Waste, Unit 1. Teacher Guide. Second Edition.

    Science.gov (United States)

    Department of Energy, Washington, DC. Office of Civilian Radioactive Waste Management, Washington, DC.

    This guide is Unit 1 of the four-part series Science, Society, and America's Nuclear Waste produced by the U.S. Department of Energy's Office of Civilian Radioactive Waste Management. The goal of this unit is to help students establish the relevance of the topic of nuclear waste to their everyday lives and activities. Particular attention is…

  11. Nuclear instrument maintenance and technical training in Nuclear Energy Unit

    International Nuclear Information System (INIS)

    Mohamad Nasir Abdul Wahid

    1987-01-01

    Instrument maintenance service is a necessity in a Nuclear Research Institute, such as the Nuclear Energy Unit (NEU) to ensure the smooth running of our research activities. However, realising that maintenance back-up service for either nuclear or other scientific equipment is a major problem in developing countries such as Malaysia, NEU has set up an Instrumentation and Control Department to assist in rectifying the maintenance problem. Beside supporting in house activities in NEU, the Instrumentation and Control Department (I and C) is also geared into providing services to other organisations in Malaysia. This paper will briefly outline the activities of NEU in nuclear instrument maintenance as well as in technical training. (author)

  12. The future of nuclear power in the United Kingdom

    International Nuclear Information System (INIS)

    Jones, P.M.S.

    1990-01-01

    The arguments that have been put forward in the United Kingdom to justify the contention by its opponents that nuclear power should not be seen as a safe, economic, strategically desirable and environmentally attractive energy source are examined. Counter arguments are presented to support the belief that these are wholly wrong. In the short to medium term, however, economic and political considerations suggest that the prospects for nuclear power in the United Kingdom are not optimistic. The long term evolution of nuclear power is uncertain but it is possible that the security of energy supply, comparative economics and environmental attractions associated with nuclear power will become more apparent and work in its favour eventually. The conviction is expressed that, by the middle of the next century, the United Kingdom will be reaping the benefits of the fast reactor on a significant scale. (UK)

  13. Role and services of the Nuclear Energy Unit

    International Nuclear Information System (INIS)

    Ahmad Tajuddin bin Ali

    1985-01-01

    This article contains the research and development activities planned to be undertaken, and the services to be provided by the Nuclear Energy Unit. The fields of research have been selected to aid the development in the use of Nuclear Science and Technology, whilst the proposed services are geared towards widening the use to this technology in socio-economic development. Objectives in the research fields have been identified following a number of consultations with IAEA, foreign and local experts, and involved careful study of local requirements. The services provided will cater for all, especially institutions involved in nuclear technology both from the public and private sectors. This effort is in line with the role of the Unit as the national promoter and coordinator in the utilization of nuclear technology in the country

  14. 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

    ... Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 Environmental Assessment... Plant, LLC, the licensee, for operation of the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2... Impact Statement for License Renewal of Nuclear Plants, Calvert Cliffs Nuclear Power Plant (NUREG-1437...

  15. Nuclear safety philosophy in the United Kingdom

    International Nuclear Information System (INIS)

    Anthony, R.D.

    1986-01-01

    Development of the United Kingdom (UK) nuclear safety philosophy is described in the context of the UK nuclear power program since 1959 and of its legislative framework. Basic to the philosophy is that the licensee is wholly responsible for nuclear safety. The licensing process and safety assessment principles used by the Nuclear Installations Inspectorate are discussed, and examples from the assessment of the proposed UK pressurized-water reactor are used to illustrate how the approach works in practice. The UK siting policy and regulatory developments since 1979 are also discussed. Recent, current, and future issues of interest to the regulatory authority are described against the development nuclear scene in the UK

  16. Nuclear fuel element recovery using PEDSCO RMI Unit

    International Nuclear Information System (INIS)

    Martin, D.G.; Pedersen, B.V.

    1984-01-01

    In September 1982, a PEDSCO Remote Mobile Investigation Unit was used to recover damaged irradiated fuel elements from a fueling machine and trolley deck at Bruce Nuclear Generating Station 'A'. This Canadian-made remote controlled vehicle was originally designed for explosive ordinance disposal by law enforcement agencies. This paper describes its adaptation to nuclear service and its first mission, within a nuclear facility

  17. New United States policies regarding international nuclear cooperation

    International Nuclear Information System (INIS)

    Marshall, H.R. Jr.

    1981-10-01

    This paper discusses the United States policy on international nuclear power development in the light of the priorities established by President Reagan in the guidelines for his Administration's nuclear co-operation policy. The aim is to establish a framework allowing for co-operation in peaceful nuclear development while remaining committed to the objective of preventing the further spread of nuclear weapons, in particular by supporting the Non-Proliferation Treaty, the IAEA Safeguards System and the Tlatelolco Treaty (NEA) [fr

  18. 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

    ... Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2; Notice of Withdrawal of...) has granted the request of Calvert Cliffs Nuclear Power Plant, LLC, the licensee, to withdraw its... for the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2, located in Calvert County, MD. The...

  19. Second unit scheduling concerns on a dual-unit nuclear project

    International Nuclear Information System (INIS)

    Block, H.R.; Mazzini, R.A.

    1978-01-01

    This paper explores the planning and scheduling problems of Unit 2 of the Susquehanna steam electric station. The causes of these problems and methods to avoid or mitigate their consequences are discussed. The Susquehanna steam electric station has two boiling water reactors rated at 1,100 MW each. Topics considered include cost factors, structures, equipment, engineering and home office, construction services, completion data phasing, work sequencing, structural dependences, and segregation. Substatial cost and schedule benefits can result if two nuclear units are designed and constructed as one integral station, and if maximum sharing of facilities and services between the units occurs. It is concluded that the cost benefits of highly integrated dual unit construction outweigh the schedule and logistical problems caused by that approach

  20. 78 FR 22347 - GPU Nuclear Inc., Three Mile Island Nuclear Power Station, Unit 2, Exemption From Certain...

    Science.gov (United States)

    2013-04-15

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 50-320; NRC-2013-0065] GPU Nuclear Inc., Three Mile Island Nuclear Power Station, Unit 2, Exemption From Certain Security Requirements AGENCY: Nuclear... and State Materials and Environmental Management Programs, U.S. Nuclear Regulatory Commission...

  1. Experience with HEPA filters at United States nuclear installations

    International Nuclear Information System (INIS)

    Bellamy, R.R.

    1977-01-01

    Part 50 of Title 10 of the United States Code of Federal Regulations requires that a number of atmosphere cleanup systems be included in the design of commercial nuclear power plants to be licensed in the United States. These filtering systems are to contain high efficiency particulate air (HEPA) filters for removal of radioactive particulate matter generated during normal and accident conditions. Recommendations for the design, testing and maintenance of the filtering systems and HEPA filter components are contained in a number of United States Nuclear Regulatory Commission documents and industry standards. This paper will discuss this published guidance available to designers of filtering systems and the plant operators of U.S. commercial nuclear power plants. The paper will also present a survey of published reports of experience with HEPA filters, failures and possible causes for the failures, and other abnormal occurrences pertaining to HEPA filters installed in U.S. nuclear power installations. A discussion will be included of U.S. practices for qualification of HEPA filters before installation, and verification of continued performance capability at scheduled intervals during operation

  2. State nuclear initiatives in the United States

    International Nuclear Information System (INIS)

    Strauss, P.L.; Stoiber, C.R.

    1977-01-01

    The paper deals with State nuclear initiatives regarding the role of nuclear power in the energy future of the United States. The question of whether and under what circumstances nuclear facilities should be used to generate electricity was put to the popular vote in several States in 1976. Some general principles of Federal-State relations are discussed with specific reference to nuclear regulations. The initiative mechanism itself is described as well as its legal form and background. The parallel developments in the State and Federal legislative consideration of nuclear issues is reviewed and the suggested reasons for the defeat of the proposals in the seven States concerned are discussed. Finally, the author draws some conclusions on the effects of the 1976 initiatives on future decision-making in the US on energy policy in general and nuclear power in particular. (NEA) [fr

  3. Collections and Analyses of Common Cause Failure Data for the Korea Standard and Westinghouse Type NPPs

    International Nuclear Information System (INIS)

    Kang, Dae Il; Han, S. H.

    2007-04-01

    The analyses of the CCF events for domestic NPPs were performed to establish the domestic database for the CCF events and to deliver supply them to the operation office of the international common cause failure data exchange (ICDE) project. We collected and analyzed the CCF events of emergency diesel generators, centrifugal pumps, motor-operated valves, check valves, circuit breakers for the Korean Standard Type nuclear power plants (NPPs), Yonggwang Units 3 and 4 and Ulchin Units 3 and 4, and the Westinghouse type NPPs, Kori Unit 3 and 4 and Yonggwang Units 1 and 2. First, the components to be collected and analyzed were classified into the common cause component groups (CCCGs) according to the ICDE coding guidelines. Next, the CCF events were identified based on reviews of the component database for the PSA and its related documents, and consultations with NPP staff. Fourteen CCF events were identified. The ratio of the number of CCF events to that of individual failure events was identified as approximately 10 percentages. However, an in depth review of the CCF events showed that most failure severities of them were identified as partial CCF events, which can be interpreted as some component failures within the CCCGs. Root causes of the CCF events were identified as 9 internal part failures, 2 human errors, 2 design deficiencies, 1 procedure inadequacy. It could be concluded that the major root causes of the CCF events were internal piece part failures

  4. Estimation of the Alpha Factor Parameters Using the ICDE Database

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Dae Il; Hwang, M. J.; Han, S. H

    2007-04-15

    Detailed common cause failure (CCF) analysis generally need for the data for CCF events of other nuclear power plants because the CCF events rarely occur. KAERI has been participated at the international common cause failure data exchange (ICDE) project to get the data for the CCF events. The operation office of the ICDE project sent the CCF event data for EDG to the KAERI at December 2006. As a pilot study, we performed the detailed CCF analysis of EDGs for Yonggwang Units 3 and 4 and Ulchin Units 3 and 4 using the ICDE database. There are two onsite EDGs for each NPP. When an offsite power and the two onsite EDGs are not available, one alternate AC (AAC) diesel generator (hereafter AAC) is provided. Two onsite EDGs and the AAC are manufactured by the same company, but they are designed differently. We estimated the Alpha Factor and the CCF probability for the cases where three EDGs were assumed to be identically designed, and for those were assumed to be not identically designed. For the cases where three EDGs were assumed to be identically designed, double CCF probabilities of Yonggwang Units 3/4 and Ulchin Units 3/4 for 'fails to start' were estimated as 2.20E-4 and 2.10E-4, respectively. Triple CCF probabilities of those were estimated as 2.39E-4 and 2.42E-4, respectively. As each NPP has no experience for 'fails to run', Yonggwang Units 3/4 and Ulchin Units 3/4 have the same CCF probability. The estimated double and triple CCF probabilities for 'fails to run' are 4.21E-4 and 4.61E-4, respectively. Quantification results show that the system unavailability for the cases where the three EDGs are identical is higher than that where the three EDGs are different. The estimated system unavailability of the former case was increased by 3.4% comparing with that of the latter. As a future study, a computerization work for the estimations of the CCF parameters will be performed.

  5. Nuclear safety risk control in the outage of CANDU unit

    International Nuclear Information System (INIS)

    Wu Mingliang; Zheng Jianhua

    2014-01-01

    Nuclear fuel remains in the core during the outage of CANDU unit, but there are still nuclear safety risks such as reactor accidental criticality, fuel element failure due to inability to properly remove residual heat. Furthermore, these risks are aggravated by the weakening plant system configuration and multiple cross operations during the outage. This paper analyzes the phases where there are potential nuclear safety risks on the basis of the typical critical path arrangement of the outage of Qinshan NPP 3 and introduces a series of CANDU-specific risk control measures taken during the past plant outages to ensure nuclear safety during the unit outage. (authors)

  6. Development of the NSSS thermal-hydraulic program for YGN unit 1 simulator

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Kyung Doo; Jeong, Jae Jun; Lee, Won Jae; Chung, Bub Dong; Ha, Kwi Seok; Kang, Kyung Ho

    2000-09-01

    The NSSS thermal-hydraulic programs installed in the domestic full-scope power plant simulators were provided in early 1980s by foreign vendors. Because of limited computational capability at that time, they usually adopt very simplified physical models for a real-time simulation of NSSS thermal-hydraulic phenomena, which entails inaccurate results and the possibility of so-called 'negative training', especially for complicated two-phase flows in the reactor coolant system. To resolve the problem, we developed a realistic NSSS T/H program (named 'ARTS' code) for use in YongGwang Nuclear Unit 1 full-scope simulator. The best-estimate code RETRAN03, developed by EPRI and approved by USNRC, was selected as a reference code of ARTS. For the development of ARTS, the followings have been performed: -Improvement of the robustness of RETRAN - Improvement of the real-time simulation capability of RETRAN - Optimum input data generation for the NSSS simulation - New model development that cannot be efficiently modeled by RETRAN - Assessment of the ARTS code. The systematic assessment of ARTS has been conducted in both personal computers (Windows 98, Visual fortran) and the simulator development environment (Windows NT, GSE simulator development tool). The results were resonable in terms of accuracy, real-time simulation and robustness.

  7. Development of the NSSS thermal-hydraulic program for YGN unit 1 simulator

    International Nuclear Information System (INIS)

    Kim, Kyung Doo; Jeong, Jae Jun; Lee, Won Jae; Chung, Bub Dong; Ha, Kwi Seok; Kang, Kyung Ho

    2000-09-01

    The NSSS thermal-hydraulic programs installed in the domestic full-scope power plant simulators were provided in early 1980s by foreign vendors. Because of limited computational capability at that time, they usually adopt very simplified physical models for a real-time simulation of NSSS thermal-hydraulic phenomena, which entails inaccurate results and the possibility of so-called 'negative training', especially for complicated two-phase flows in the reactor coolant system. To resolve the problem, we developed a realistic NSSS T/H program (named 'ARTS' code) for use in YongGwang Nuclear Unit 1 full-scope simulator. The best-estimate code RETRAN03, developed by EPRI and approved by USNRC, was selected as a reference code of ARTS. For the development of ARTS, the followings have been performed: -Improvement of the robustness of RETRAN - Improvement of the real-time simulation capability of RETRAN - Optimum input data generation for the NSSS simulation - New model development that cannot be efficiently modeled by RETRAN - Assessment of the ARTS code. The systematic assessment of ARTS has been conducted in both personal computers (Windows 98, Visual fortran) and the simulator development environment (Windows NT, GSE simulator development tool). The results were resonable in terms of accuracy, real-time simulation and robustness

  8. Changing Perceptions of Nuclear Power in The United States

    International Nuclear Information System (INIS)

    Taylor, John

    1989-01-01

    Although many new nuclear power plants have been brought on line in that time, resulting in a capacity of 110 plants with operating permits and another twelve in the last stages of completion, all of these plants were authorized before 1978. The fundamental reason for this moratorium in new orders was the precipitous reduction in electricity demand, arising from the OPEC embargo and Iran revolution, which created excess electric capacity throughout the United States. In fact, many nuclear and coal plants were cancelled to minimize the over capacity problem and no large base load generating units have been ordered of any kind in the past decade. So the 'moratorium' is not really unique to nuclear power. Progress, coupled with increased awareness that nuclear power is one of the keys to solving atmospheric environmental problems, will swing political and public acceptance back to being favorable. Successful progress in these matters will be of benefit to public acceptance around the world and, conversely, serious technical difficulties, particularly entailing any major incident with a nuclear power plants anywhere in the world, will adversely affect the improvement in political and public acceptance in the United States. It is vitally important, therefore, that we continue to further enhance international cooperation in nuclear power. We are pleased the Korea Electric power Corporation and the Korea Advanced Energy Research Institute are participating in EPRI development programs, and hope that cooperation will increase in the future. We're most encouraged by the formation of the World Association of Nuclear Operators, which will be initiated in Moscow next month. The nuclear electric utilities and their governments around the world, the International Atomic Energy Agency, and the Nuclear Energy Agency of OECD should be commended for their initiative in international cooperation

  9. The United States nuclear plant reliability data program: Its description and status

    International Nuclear Information System (INIS)

    Wise, M.J.

    1975-01-01

    The American National Standards Institute Subcommittee N18-20 has developed and implemented the United States Nuclear Plant Reliability Data System (NPRDS). The NPRDS is designed to accumulate, store, analyse, and report reliability and failure statistics on systems and components of nuclear power plants related to nuclear safety. Input data to the NPRDS consist of engineering, operating, and failure information submitted on a voluntary basis by participating utilities. Prior to entry into the computerized data base, the data are thoroughly checked for accuracy by both the submitting organizations and the NPRDS operating contractor. The data base is the source of various periodic output reports to the nuclear power industry and is utilized to produce special reports upon request. The present data base represents data accumulated from about thirty nuclear units with additional units expected to begin submitting data immediately. The objective is to have essentially all operating nuclear units in the United States of America participating in the program by the end of 1975. The first NPRDS annual reports containing meaningful reliability and failure statistics are expected to be produced following the end of 1975. (author)

  10. 76 FR 81994 - UniStar Nuclear Energy; Combined License Application for Calvert Cliffs Nuclear Power Plant, Unit...

    Science.gov (United States)

    2011-12-29

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 52-016; NRC-2008-0250] UniStar Nuclear Energy; Combined License Application for Calvert Cliffs Nuclear Power Plant, Unit 3; Exemption 1.0 Background: UniStar Nuclear Energy (UNE) submitted to the U.S. Nuclear Regulatory Commission (NRC or the Commission ) a...

  11. Principles and foundation: national standards on quantities and units in nuclear science field

    International Nuclear Information System (INIS)

    Chen Lishu

    1993-11-01

    The main contents of National Standards on Quantities and units of atomic and nuclear physics (GB 3102.9) and Quantities and Units of nuclear reactions and ionizing radiations (GB 310.10) are presented in which most important quantities with their symbols and definitions in the nuclear scientific field are given. The principles and foundation, including the International System of Units (SI) and its application to the nuclear scientific field, in the setting of the National Standards are explained

  12. New steam generators slated for nuclear units

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    This article is a brief discussion of Duke Power's plans to replace steam generators at its McGuire and Catawba nuclear units. A letter of intent to purchase (from Babcock and Wilcox) the 12 Westinghouse steam generators has been signed, but no constructor has been selected at this time. This action is brought about by the failures of more than 3000 tubes in these units

  13. Unconventional wisdom [Entergy's economic management of five disparate nuclear units

    International Nuclear Information System (INIS)

    Wood, J.

    1996-01-01

    The conventional wisdom is that a competitive nuclear power programme requires standard plants, multi-unit sites and economies of scale. Entergy Operations, Inc (EOI) in the USA has five nuclear units of two reactor types, acquired from five vendors and located on four sites separated by hundreds of miles. EOI set two bench marks in its aim to deliver electricity at the market price from each of its nuclear units while meeting the costs of O and M, fuel, capital investment and overheads. The first was to become the best operator of each type of its differently designed units. The second was to combine the sense of ownership and expertise of single unit operators with the flexibility and efficiency of multi-unit sites. In order to achieve this, EOI aims to operate the five units as though they were on one site. Central to this plan is a set of peer groups, each of which deals with an aspect of plant operation, sharing good practice across all the units. Building on this, increasingly during outages, employees are brought in from other units rather than employing outside contractors. Although EOI employees are more expensive on an hourly basis they are two to three times more efficient than outside contractors. The peer group concept is also leading to rationalisation of expertise as groups become identified with particular specialisations which back-up teams working on other units. (U.K.)

  14. Sweden, United States and nuclear energy. The establishment of a Swedish nuclear materials control 1945-1995

    International Nuclear Information System (INIS)

    Jonter, T.

    1999-05-01

    This report deals mainly with the United States nuclear energy policy towards Sweden 1945-1960. Although Sweden contained rich uranium deposits and retained high competence in the natural sciences and technology, the country had to cooperate with other nations in order to develop the nuclear energy. Besides developing the civil use of nuclear power, the Swedish political elite also had plans to start a nuclear weapons programme. From the beginning of the 1950s up to 1968, when the Swedish parliament decided to sign the non-proliferation treaty, the issue was widely debated. In this report, American policy is analyzed in two periods. In the first period, 1945-1953, the most important aim was to prevent Sweden from acquiring nuclear materials, technical know-how, and advanced equipment which could be used in the production of nuclear weapons. The Swedish research projects were designed to contain both a civil and military use of nuclear energy. The first priority of the American administration was to discourage the Swedes from exploiting their uranium deposits, especially for military purposes. In the next period, 1953-1960, the American policy was characterized by extended aid to the development of the Swedish energy programme. Through the 'Atoms for Peace'-programme, the Swedish actors now received previously classified technical information and nuclear materials. Swedish companies and research centers could now buy enriched uranium and advanced equipment from the United States. This nuclear trade was, however, controlled by the American Atomic Energy Commission (AEC). The American help was shaped to prevent the Swedes from developing nuclear weapons capability. From mid-50s Swedish politicians and defence experts realised that a national production of nuclear bombs would cost much more money than was supposed 4-5 years earlier. As a consequence, Swedish officials started to explore the possibilities of acquiring nuclear weapons from United States. The American

  15. The Evolution of India's Nuclear Program: Implications for the United States

    National Research Council Canada - National Science Library

    Creasman, David J

    2008-01-01

    Since India began developing its nuclear program it has continually encountered issues with the United States and other nuclearized countries over whether India should be able to establish a nuclear...

  16. Choices: A Unit on Conflict and Nuclear War.

    Science.gov (United States)

    Massachusetts Teachers Association, Boston.

    Ten lessons on the evolution of the nuclear arms race, the nature and consequences of using nuclear weapons, and new ways that conflicts among nations might be resolved are presented for the junior high school level. The unit contains age-appropriate materials to equip students with skills and knowledge to understand what choices can be made to…

  17. The United States nuclear liability regime under the Price-Anderson Act

    International Nuclear Information System (INIS)

    Brown, O. F.

    2011-01-01

    The 1958 U. S. Price-Anderson Act created the worlds first national nuclear liability regime. It now provides US $12,6 Billion of nuclear liability coverage for the 104 nuclear power plants in the United States, by far the highest monetary coverage of any nuclear liability regime in the world. Each power plant operator provides nuclear hazards coverage for anyone liable through a combination of private insurance from the American nuclear insurance pool (now US$ 375 million) and a retrospective assessment (now US$111,9 million per power plant per incident plus 5 percent for claims and costs). The United States in 2008 ratified the International Atomic Energy Agency's Convention on Supplementary Compensation for Nuclear Damage (CSC). and is promoting it as the basis for a more global nuclear liability regime uniting States that are party to the Vienna Convention or the Paris Convention, or have a domestic law consistent with the CSC Annex. The CSC Annex was written to grad father the Price-Anderson Acts economic channeling of liability to the installation operator. The omnibus feature of Price-Anderson is similar to the legal channeling of all liability to the installation operator under the international nuclear liability conventions and domestic laws of many other countries. The Price-Anderson system (like the Vienna and Paris Conventions) does not provide liability coverage for nuclear damage to or loss of use of on-site property. (Author)

  18. 78 FR 77726 - Exelon Generation Company, LLC Three Mile Island Nuclear Station, Unit 1

    Science.gov (United States)

    2013-12-24

    ... Three Mile Island Nuclear Station, Unit 1 AGENCY: Nuclear Regulatory Commission. ACTION: Exemption... License No. DPR-50, which authorizes operation of the Three Mile Island Nuclear Station, Unit 1 (TMI-1... Facility Operating License No. DPR-50, which authorizes operation of the Three Mile Island Nuclear Station...

  19. Operational behaviour of WWER nuclear power units after Chernobyl accident

    International Nuclear Information System (INIS)

    Milivojevic, S.; Spasojevic, D.

    2000-01-01

    The indicators of effectiveness of WWER operation, in 1987-1998 were analyzed. For three groups of nuclear units (WWER, NPP Kozloduy, NPP Paks), the trends of Indicators flow were established. The comparative analysis of forced outage rate, and load factor of WWERs and nuclear units all in the world was carried out; it gives the general picture of accident influence on the states and the relations of these indicators in considered period (author)

  20. Simulator of nuclear power plant with WWER-440 units

    International Nuclear Information System (INIS)

    Krcek, V.

    1985-01-01

    The use is discussed of simulators in the training of qualified personnel for the construction and operation of nuclear power plants. Simulators are used for training all activities and thinking processes related to the control of a nuclear reactor in the course of quasi-steady and non-steady states. The development and implementation is summed up of the construction of such a simulator for WWER-440 nuclear power plants. The main parts of the simulator include the unit control room, the computer system, the teacher's workplace and the interface system. The possibility of simulating the functions of the unit for personnel training is based on the description of the behaviour of the simulated object in form of mathematical models of its basic technological subsystems and their interrelations within the range of operating patterns. (J.C.)

  1. Nuclear information and education experience in the United Kingdom

    International Nuclear Information System (INIS)

    Ginniff, M.E.

    1993-01-01

    The presentation discusses the importance of public information and education in the field of energy and particularly in the field of nuclear energy development. The attempt is made to explain some issues connected with the nuclear fuel cycle. Appendix contains comments on the United Kingdom educational materials in this area

  2. 75 FR 36700 - Exelon Generation Company, LLC; Three Mile Island Nuclear Station, Unit 1; Environmental...

    Science.gov (United States)

    2010-06-28

    ...; Three Mile Island Nuclear Station, Unit 1; Environmental Assessment and Finding of No Significant Impact... Company, LLC (the licensee), for operation of Three Mile Island Nuclear Station, Unit 1 (TMI-1), located... Three Mile Island Nuclear Station, Units 1 and 2, NUREG-0552, dated December 1972, and Generic...

  3. 77 FR 29701 - Impact of Construction (Under a Combined License) of New Nuclear Power Plant Units on Operating...

    Science.gov (United States)

    2012-05-18

    ... New Nuclear Power Plant Units on Operating Units at Multi-Unit Sites AGENCY: Nuclear Regulatory... construct and operate new nuclear power plants (NPPs) on multi-unit sites to provide an evaluation of the... License) of New Nuclear Power Plants on Operating Units at Multi-Unit Sites (Package). ML112630039 Federal...

  4. Science, society, and America's nuclear waste: Unit 4, The waste management system

    International Nuclear Information System (INIS)

    1992-01-01

    This is unit 4 (The Waste Management System) in a four-unit secondary curriculum. It is intended to provide information about scientific and societal issues related to the management of spent nuclear fuel from generation of electricity at nuclear powerplants and high-level radioactive waste from US national defense activities. The curriculum, supporting classroom activities, and teaching materials present a brief discussion of energy and electricity generation, including that produced at nuclear powerplants; information on sources, amounts, location, and characteristics of spent nuclear fuel and high-level radioactive waste; sources, types and effects of radiation; US policy for managing and disposing of spent nuclear fuel and high-level radioactive waste and what other countries are doing; and the components of the nuclear waste management system

  5. Nuclear Legislation in OECD and NEA Countries. Regulatory and Institutional Framework for Nuclear Activities - United Kingdom

    International Nuclear Information System (INIS)

    2003-01-01

    This country profile provide comprehensive information on the regulatory and Institutional Framework governing nuclear activities as well as a detailed review of a full range of nuclear law topics, including: mining regime; radioactive substances; nuclear installations; trade in nuclear materials and equipment; radiation protection; radioactive waste management; non-proliferation and physical protection; transport; and nuclear third party liability. The profile is complemented by reproductions of the primary legislation regulating nuclear activities in the country. Content: I. General Regulatory Regime: 1. Introduction; 2. Mining Regime; 3. Radioactive Substances; 4. Nuclear Installations (Licensing and inspection, including nuclear safety; Protection of the environment against radiation effects; Emergency response); 5. Trade in Nuclear Materials and Equipment; 6. Radiation Protection; 7. Radioactive Waste Management; 8. Non-Proliferation and Physical Protection; 9. Transport; 10. Nuclear Third Party Liability; II. Institutional Framework: 1. Regulatory and Supervisory Authorities (Department of Trade and Industry - DTI; Secretary of State for Environment, Food and Rural Affairs and the Secretary of State for Health; Secretary of State for Transport; Secretary of State for Education); 2. Advisory Bodies (Medical Research Council - MRC; Nuclear Safety Advisory Committee; Radioactive Waste Management Advisory Committee); 3. Public and Semi-Public Agencies (United Kingdom Atomic Energy Authority - UKAEA; Health and Safety Commission and Executive - HSC/HSE; National Radiological Protection Board - NRPB; Environment Agencies; British Nuclear Fuels plc. - BNFL; Amersham International plc.; The National Nuclear Corporation Ltd. - NNC; United Kingdom Nirex Ltd.; Magnox Electric plc.; British Energy Generation Ltd.; Scottish Electricity Generator Companies; British Energy Generation Ltd.; Regional Electricity Companies in England and Wales)

  6. Nuclear engineering education in the United States

    International Nuclear Information System (INIS)

    Williamson, T.G.

    1982-01-01

    In discussing nuclear engineering education in the United States it is shown that the most critical issue facing the nuclear engineering education community today is enrolment in a time of increasing demand for graduate engineers. Related to the issue of enrolment is support for graduate students, whether it be fellowships, traineeships, or research assistantships. Other issues are those of maintaining a vital faculty in the face of a competitive job market, of maintaining research facilities and developing new ones, and of determining the directions of educational efforts in the future. (U.K.)

  7. Environmental Impact Assessment for Olkiluoto 4 Nuclear Power Plant Unit in Finland

    International Nuclear Information System (INIS)

    Dersten, Riitta; Gahmberg, Sini; Takala, Jenni

    2008-01-01

    In order to improve its readiness for constructing additional production capacity, Teollisuuden Voima Oyj (TVO) initiated in spring 2007 the environmental impact assessment procedure (EIA procedure) concerning a new nuclear power plant unit that would possibly be located at Olkiluoto. When assessing the environmental impacts of the Olkiluoto nuclear power plant extension project, the present state of the environment was first examined, and after that, the changes caused by the projects as well as their significance were assessed, taking into account the combined impacts of the operations at Olkiluoto. The environmental impact assessment for the planned nuclear power plant unit covers the entire life cycle of the plant unit. (authors)

  8. Environmental Impact Assessment for Olkiluoto 4 Nuclear Power Plant Unit in Finland

    Energy Technology Data Exchange (ETDEWEB)

    Dersten, Riitta; Gahmberg, Sini; Takala, Jenni [Teollisuuden Voima Oyj, Olkiluoto, FI-27160 Eurajoki (Finland)

    2008-07-01

    In order to improve its readiness for constructing additional production capacity, Teollisuuden Voima Oyj (TVO) initiated in spring 2007 the environmental impact assessment procedure (EIA procedure) concerning a new nuclear power plant unit that would possibly be located at Olkiluoto. When assessing the environmental impacts of the Olkiluoto nuclear power plant extension project, the present state of the environment was first examined, and after that, the changes caused by the projects as well as their significance were assessed, taking into account the combined impacts of the operations at Olkiluoto. The environmental impact assessment for the planned nuclear power plant unit covers the entire life cycle of the plant unit. (authors)

  9. 75 FR 6223 - PSEG Nuclear LLC; Hope Creek Generating Station and Salem Nuclear Generating Station, Unit Nos. 1...

    Science.gov (United States)

    2010-02-08

    ... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-272, 50-311 and 50-354; NRC-2010-0043] PSEG Nuclear LLC; Hope Creek Generating Station and Salem Nuclear Generating Station, Unit Nos. 1 and 2...-70, and DPR-75, issued to PSEG Nuclear LLC (PSEG, the licensee), for operation of the Hope Creek...

  10. Site selection and evaluation of nuclear power units in Egypt

    International Nuclear Information System (INIS)

    Bonnefille, R.

    1980-01-01

    The selection of sites for nuclear power units in Egypt by SOFRATOME for Nuclear Plants Authority is carried on using a method based on interaction between different criteria. The method and the main results on criterion 'radio-ecological impact' are sketched briefly [fr

  11. I and C success in Korea past and present projects and a view to the future

    International Nuclear Information System (INIS)

    Ridolfo, Charles F.

    2009-01-01

    Westinghouse Electric Company, LLC (WEC) has been providing advanced Instrumentation and Control (I and C) technology for the C E System 80, Korean Standard Nuclear Power Plant (KSNP), since the early 1990's. I and C equipment and technical support has been provided for a progression of these plants including Yonggwang Units 3,4,5,6, Ulchin Units 3,4,5,6, Shin Kori Units 1 and 2, Shin Wolsong Units 1 and 2, and most recently for Shin Kori Units 3 and 4. These I and C programs have been highly successful and have helped to contribute to the outstanding plant availability for the commissioned units at Yonggwang 3,4,5, and 6 and Ulchin 3,4,5, and 6; which are currently providing power on the grid. WEC has also recently delivered I and C equipment for Shin Kori Units 1 and 2 and Shin Wolsong Units 1 and 2 and is supporting the installation and startup of the equipment. In addition, WEC is in the initial design stages for providing an integrated protection system that will be deployed at Shin Kori Units 3 and 4 which are the first units to implement the APR1400; an advanced reactor of indigenous Korean design, which is based on the previous generation Optimized Power Reactor OPR1000. The success of the I and C programs has been the result of careful consideration of the appropriate technology to employ, applying comprehensive quality assurance measures, providing appropriate technical support and consultation services, implementation of a program of continued I and C logistic support, maintaining a professional and experienced I and C work force, and maintaining a strong and mutually supportive partnership with the Korea Power Engineering Company (KOPEC) and with Korea Hydro and Nuclear Power (KHNP). WEC takes great pride in its on going I and C partnership with Korea, which has included not only providing equipment and technical support services, but also completion of a comprehensive Technology Transfer program. This program was implemented to promote local 'elf

  12. Science, society, and America's nuclear waste: Unit 4, The waste management system

    International Nuclear Information System (INIS)

    1992-01-01

    This is the teachers guide to unit 4, (The Waste Management System), of a four-unit secondary curriculum. It is intended to provide information about scientific and societal issues related to the management of spent nuclear fuel from generation of electricity at nuclear powerplants and high-level radioactive waste from US national defense activities. The curriculum, supporting classroom activities, and teaching materials present a brief discussion of energy and electricity generation, including that produced at nuclear powerplants; information on sources, amounts, location, and characteristics of spent nuclear fuel and high-level radioactive waste; sources, types and effects of radiation; US policy for managing and disposing of spent nuclear fuel and high-level radioactive waste and what other countries are doing; and the components of the nuclear waste management system

  13. Evaluation of Watts Bar Nuclear Plant Unit 1 Technical Specifications

    International Nuclear Information System (INIS)

    Baxter, D.E.; Bruske, S.J.

    1985-08-01

    This document was prepared for the Nuclear Regulatory Commission (NRC) to assist them in determining whether the Watts Bar Nuclear Plant Unit 1 Technical Specifications (T/S), which govern plant systems configurations and operations, are in conformance with the assumption of the Final Safety Analysis Report (FSAR) as amended, and the requirements of the Safety Evaluation Report (SER) as supplemented. A comparative audit of the FSAR as amended, and the SER as supplemented was performed with the Watts Bar T/S. Several discrepancies were identified and subsequently resolved through discussions with the cognizant NRC reviewer, NRC staff reviewers and/or utility representatives. The Watts Bar Nuclear Plant Unit 1 T/S, to the extent reviewed, are in conformance with the FSAR and SER

  14. Evaluation of Shoreham Nuclear Power Station, Unit 1 technical specifications

    International Nuclear Information System (INIS)

    Baxter, D.E.; Bruske, S.J.

    1985-08-01

    This document was prepared for the Nuclear Regulatory Commission (NRC) to assist them in determining whether the Shoreham Nuclear Power Station Unit 1 Technical Specifications (T/S), which govern plant systems configurations and operations, are in conformance with the assumptions of the Final Safety Analysis Report (FSAR) as amended, and the requirements of the Safety Evaluation Report (SER) as supplemented. A comparative audit of the FSAR as amended, and the SER as supplemented was performed with the Shoreham T/S. Several discrepancies were identified and subsequently resolved through discussions with the cognizant NRC reviewer, NRC staff reviewers and/or utility representatives. The Shoreham Nuclear Power Station Unit 1 T/S, to the extent reviewed, are in conformance with the FSAR and SER

  15. Development of Thermal Performance Analysis Computer Program on Turbine Cycle of Yoggwang 3,4 Units

    Energy Technology Data Exchange (ETDEWEB)

    Hong, S.Y.; Choi, K.H.; Jee, M.H.; Chung, S.I. [Korea Electric Power Research Institute, Taejon (Korea)

    2002-07-01

    The objective of the study ''Development of Thermal Performance Analysis Computer Program on Turbine Cycle of Yonggwang 3,4 Units'' is to utilize computerized program to the performance test of the turbine cycle or the analysis of the operational status of the thermal plants. In addition, the result can be applicable to the analysis of the thermal output at the abnormal status and be a powerful tool to find out the main problems for such cases. As a results, the output of this study can supply the way to confirm the technical capability to operate the plants efficiently and to obtain the economic gains remarkably. (author). 27 refs., 73 figs., 6 tabs.

  16. 76 FR 19148 - PSEG Nuclear, LLC, Hope Creek Generating Station and Salem Nuclear Generating Station, Units 1...

    Science.gov (United States)

    2011-04-06

    ... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-272, 50-311, 50-354; NRC-2009-0390 and NRC-2009-0391] PSEG Nuclear, LLC, Hope Creek Generating Station and Salem Nuclear Generating Station, Units 1 and 2..., DPR-70, and DPR-75 for an additional 20 years of operation for the Hope Creek Generating Station (HCGS...

  17. Inspection of licensed nuclear power plants in the United States

    International Nuclear Information System (INIS)

    Thornburg, H. D.

    1977-01-01

    Inspection of licensed nuclear power plants in the United States is performed by the Office of Inspection and Enforcement (IE), United States Nuclear Regulatory Commission. IE has several key functions : a) Inspection of licensees and investigation of incidents, occurrences and allegations. b) Detection and correction of safety and security problems. c) Enforcement of rules, regulations, and Commission orders. d) Feedback to the industry and others regarding safety experience. e) Informing the public and others. Major enforcement actions and events involving operating power reactors for the past several years will be summarized. (author)

  18. Outline of construction and facility features of Onagawa nuclear power station Unit No. 2

    International Nuclear Information System (INIS)

    Umimura, Yoshiharu; Tsunoda, Ryohei; Watanabe, Kazunori

    1996-01-01

    Tohoku Electric Power Company promotes development of various power sources to provide a stable supply of electricity in the future, and nuclear power takes a leading part. In August 1989, construction of Onagawa nuclear power plant Unit No. 2 (825MW) was started, following Unit No. 1 (524MW) which went on line in 1984 as Tohoku Electric's first nuclear power plant unit. Unit No. 2 began commercial operation in July 1995 through satisfactory construction work such as RPV hydraulic test in March 1994, fuel loading in October 1994, and various startup tests in each power stage. The design and construction of Unit No. 2 reflect construction and operation experience gained from Unit No. 1, and the latest technology, including that of the LWR Improvement and Standardization Program, was adopted to enhance facility reliability, improve operation and maintenance performance, and reduce worker dosage. Features of the facility, construction techniques, and a description of preoperation of Onagawa nuclear power plant Unit No. 2 are described in this paper. (author)

  19. CINDU: Catalogue of Numerical Neutron Data Available from the IAEA Nuclear Data Unit

    Energy Technology Data Exchange (ETDEWEB)

    Good, W. K.; Attrae, P. M.; Ekberg, K.; Lemmel, H. D.; Lorenz, A.; Otstavnov, P. [IAEA, Nuclear Data Unit, Vienna (Austria)

    1967-08-15

    As a consequence of the progress in the field of international data exchange, and in compliance with the recommendations of the International Nuclear Data Committee (INDC) to the Director General of the IAEA, the Nuclear Data Unit has established a neutron data compilation center for the purpose of promoting international acquisition and exchange of basic neutron data. A specific orientation was given to this activity last year with the adoption of Operation Post-Box, according to which other major data centers submit either voluntarily or on request contributions of data to a fund held by the IAEA Nuclear Data Unit, which is in turn freely distributed to the remaining major data centers and to individuals. In the course of the last 12 months, this fund of data, embodied in the Nuclear Data Unit DASTAR file, has increased considerably as a result of the contributions by the data centers of Brookhaven, Obninsk and Saclay, as well as from collections from the IAEA Nuclear Data Unit service area. The CINDU catalog, submitted herewith, is an index of the current data holdings of the IAEA Nuclear Data Unit as of first August 1967. It serves a dual function: firstly, to act as an essential aid in the operation of the Post-Box concept, and secondly to inform data users within the IAEA Nuclear Data Unit service area of the current holdings in Vienna. A method to locate available data at any one of the data centers, including the IAEA Nuclear Data Unit, exists now in CINDA in the form of an indicator at the right hand side of the page. In addition to the external reference function filled by CINDA, the present CINDU catalog serves an internal function as the bibliographic part of DASTAR as well. This internal function required slight modifications of the CINDA format, in order to provide more comprehensive information and retrieval capabilities in the overall operation of the DASTAR system. The present form of the CINDU catalog is working satisfactorily; however

  20. United States nuclear tests, July 1945 through September 1992

    Energy Technology Data Exchange (ETDEWEB)

    1994-12-01

    This document lists chronologically and alphabetically by name all nuclear tests and simultaneous detonations conducted by the United States from July 1945 through September 1992. Several tests conducted during Operation Dominic involved missile launches from Johnston Atoll. Several of these missile launches were aborted, resulting in the destruction of the missile and nuclear device either on the pad or in the air.

  1. United Kingdom: Procurement Related Nuclear Experience (Operating Experience)

    International Nuclear Information System (INIS)

    2016-01-01

    Procurement of nuclear facilities in the United Kingdom is subject to nuclear site licence conditions issued by the Government through the Office for Nuclear Regulation (ONR). Each nuclear facility in the United Kingdom must have a nuclear site licence and must comply with the 36 general conditions that are set out in the Licence Condition Handbook (October 2014). In addition, the ONR has published a technical assessment guide for the procurement of nuclear safety related items or services; a guide on intelligent customers and a guide on records management also apply to the procurement phase, and ONR interventions look across all three of these documents. Procurement governance arrangements need to be developed (including a policy, manual, procedures and template documents) and approved within the utility company. The ONR monitors the arrangements via interventions and deems the arrangements to be ‘adequate’. Some procurement contracts become lifetime records for nuclear safety related systems and need to be retained while the plant is in place. A formal record retention schedule needs to be created and managed by the procurement organization. The utility company may elect to set hold points during the various procurement stages and, importantly, obtain approval for the contract and its content from all technical stakeholders (with particular emphasis on the engineering, project management and design authority quality functions before contract award). For contracts with high nuclear safety significance, the ONR may enforce additional hold points before and/or after contract award. There is a general requirement that the utility puts in place adequate arrangements to ensure that suitably qualified and experienced personnel are employed to implement adequate management arrangements and to act as an intelligent customer. This includes being able to demonstrate that any contractor or supplier is suitable, capable and experienced, and has the necessary processes and

  2. Advances in multi-unit nuclear power plant probabilistic risk assessment

    International Nuclear Information System (INIS)

    Modarres, Mohammad; Zhou, Taotao; Massoud, Mahmoud

    2017-01-01

    The Fukushima Dai-ichi accident highlighted the importance of risks from multiple nuclear reactor unit accidents at a site. As a result, there has been considerable interest in Multi-Unit Probabilistic Risk Assessment (MUPRA) in the past few years. For considerations in nuclear safety, the MUPRA estimates measures of risk and identifies contributors to risk representing the entire site rather than the individual units in the site. In doing so, possible unit-to-unit interactions and dependencies should be modeled and accounted for in the MUPRA. In order to effectively account for these risks, six main commonality classifications—initiating events, shared connections, identical components, proximity dependencies, human dependencies, and organizational dependencies—may be used. This paper examines advances in MUPRA, offers formal definitions of multi-unit site risk measures and proposes quantitative approaches and data to account for unit-to-unit dependencies. Finally, a parametric approach for the multi-unit dependencies has been discussed and a simple example illustrates application of the proposed methodology. - Highlights: • This paper will discuss the technical aspects of an integrated MUPRA, including consideration of dependencies and assessment of the multi-unit dependency data and models for quantifying such dependencies. • The paper also provides discussions on formal definitions and metrics for multi-unit site risks. • The parametric methods are used to address multi-unit dependency situations. • A conceptual two-unit logic example is used to demonstrate the application of proposed methodology.

  3. Knowledge acquisition for nuclear power plant unit diagnostic system

    International Nuclear Information System (INIS)

    Li Xiaodong; Xi Shuren

    2003-01-01

    The process of acquiring knowledge and building a knowledge base is critical to realize fault diagnostic system at unit level in a nuclear power plant. It directly determines whether the diagnostic system can be applied eventually in a commercial plant. A means to acquire knowledge and its procedures was presented in this paper for fault diagnostic system in a nuclear power plant. The work can be carried out step by step and it is feasible in a commercial nuclear power plant. The knowledge base of the fault diagnostic system for a nuclear power plant can be built after the staff finish the tasks according to the framework presented in this paper

  4. A study of the public opinion concerning nuclear power generation in the United States

    International Nuclear Information System (INIS)

    Oiso, Shinichi

    2008-01-01

    In this study, I surveyed the outcome of opinion poll about people's attitude toward nuclear power and analysed their awareness of nuclear power generation in the United States. As a result, it was found that percentage of the people who have positive attitude toward nuclear power has been over 60% since 1998. This result corresponds to the fact that people's preference is tending more toward nuclear power generation which is called the nuclear power Renaissance in the United States. Furthermore, analysis of the outcome of the opinion poll in power stations site region was also conducted and it was found that attitude of the people in the site region was more positive than that of average level in the United States. (author)

  5. Evaluation of Perry Nuclear Power Plant Unit 1 technical specifications

    International Nuclear Information System (INIS)

    Baxter, D.E.; Bruske, S.J.

    1985-11-01

    This document was prepared for the Nuclear Regulatory Commission (NRC) to assist them in determining whether the Perry Nuclear Power Plant Unit 1 Technical Specifications (T/S), which govern plant systems configurations and operations, are in conformance with the requirements of the Final Safety Analysis Report (FSAR) as amended, and the requirements of the Safety Evaluation Report (SER) as supplemented. A comparative audit of the FSAR as amended, and the SER as supplemented was performed with the Perry T/S. Several discrepancies were identified and subsequently resolved through telephone conversations with the staff reviewer and the utility representative. Pending completion of the resolutions noted in Parts 3 and 4 of this report, the Perry Nuclear Power Plant Unit 1 T/S, to the extent reviewed, are in conformance with the FSAR and SER

  6. Second periodic safety review of Angra Nuclear Power Station, unit 1

    Energy Technology Data Exchange (ETDEWEB)

    Martins, Carlos F.O.; Crepaldi, Roberto; Freire, Enio M., E-mail: ottoncf@tecnatom.com.br, E-mail: emfreire46@gmail.com, E-mail: robcrepaldi@hotmail.com [Tecnatom do Brasil Engenharia e Servicos Ltda, Rio de Janeiro, RJ (Brazil); Campello, Sergio A., E-mail: sacampe@eletronuclear.gov.br [Eletrobras Termonuclear S.A. (ELETRONUCLEAR), Rio de Janeiro, RJ (Brazil)

    2015-07-01

    This paper describes the second Periodic Safety Review (PSR2-A1) of Angra Nuclear Power Station, Unit 1, prepared by Eletrobras Eletronuclear S.A. and Tecnatom do Brasil Engenharia e Servicos Ltda., during Jul.2013-Aug.2014, covering the period of 2004-2013. The site, in Angra dos Reis-RJ, Brazil, comprises: Unit 1, (640 MWe, Westinghouse PWR, operating), Unit 2 (1300 MWe, KWU/Areva, operating) and Unit 3 (1405 MWe, KWU/Areva, construction). The PSR2-A1 attends the Standards 1.26-Safety in Operation of Nuclear Power Plants, Brazilian Nuclear Regulatory Commission (CNEN), and IAEA.SSG.25-Periodic Safety Review of Nuclear Power Plants. Within 18 months after each 10 years operation, the operating organization shall perform a plant safety review, to investigate the evolution consequences of safety code and standards, regarding: Plant design; structure, systems and components behavior; equipment qualification; plant ageing management; deterministic and probabilistic safety analysis; risk analysis; safety performance; operating experience; organization and administration; procedures; human factors; emergency planning; radiation protection and environmental radiological impacts. The Review included 6 Areas and 14 Safety Parameters, covered by 33 Evaluations.After document evaluations and discussions with plant staff, it was generated one General and 33 Specific Guide Procedures, 33 Specific and one Final Report, including: Description, Strengths, Deficiencies, Areas for Improvement and Conclusions. An Action Plan was prepared by Electronuclear for the recommendations. It was concluded that the Unit was operated within safety standards and will attend its designed operational lifetime, including possible life extensions. The Final Report was submitted to CNEN, as one requisite for renewal of the Unit Permanent Operation License. (author)

  7. Second periodic safety review of Angra Nuclear Power Station, unit 1

    International Nuclear Information System (INIS)

    Martins, Carlos F.O.; Crepaldi, Roberto; Freire, Enio M.; Campello, Sergio A.

    2015-01-01

    This paper describes the second Periodic Safety Review (PSR2-A1) of Angra Nuclear Power Station, Unit 1, prepared by Eletrobras Eletronuclear S.A. and Tecnatom do Brasil Engenharia e Servicos Ltda., during Jul.2013-Aug.2014, covering the period of 2004-2013. The site, in Angra dos Reis-RJ, Brazil, comprises: Unit 1, (640 MWe, Westinghouse PWR, operating), Unit 2 (1300 MWe, KWU/Areva, operating) and Unit 3 (1405 MWe, KWU/Areva, construction). The PSR2-A1 attends the Standards 1.26-Safety in Operation of Nuclear Power Plants, Brazilian Nuclear Regulatory Commission (CNEN), and IAEA.SSG.25-Periodic Safety Review of Nuclear Power Plants. Within 18 months after each 10 years operation, the operating organization shall perform a plant safety review, to investigate the evolution consequences of safety code and standards, regarding: Plant design; structure, systems and components behavior; equipment qualification; plant ageing management; deterministic and probabilistic safety analysis; risk analysis; safety performance; operating experience; organization and administration; procedures; human factors; emergency planning; radiation protection and environmental radiological impacts. The Review included 6 Areas and 14 Safety Parameters, covered by 33 Evaluations.After document evaluations and discussions with plant staff, it was generated one General and 33 Specific Guide Procedures, 33 Specific and one Final Report, including: Description, Strengths, Deficiencies, Areas for Improvement and Conclusions. An Action Plan was prepared by Electronuclear for the recommendations. It was concluded that the Unit was operated within safety standards and will attend its designed operational lifetime, including possible life extensions. The Final Report was submitted to CNEN, as one requisite for renewal of the Unit Permanent Operation License. (author)

  8. 75 FR 8757 - Nebraska Public Power District, Cooper Nuclear Station, Unit 1; Notice of Availability of the...

    Science.gov (United States)

    2010-02-25

    ..., Cooper Nuclear Station, Unit 1; Notice of Availability of the Draft Supplement 41 to the Generic... Renewal of Cooper Nuclear Station, Unit 1 Notice is hereby given that the U.S. Nuclear Regulatory... operating license DPR-46 for an additional 20 years of operation for Cooper Nuclear Station, Unit 1 (CNS-1...

  9. United Kingdom procedures in case of nuclear accidents

    International Nuclear Information System (INIS)

    Chalfont, L.

    1988-01-01

    From the United Kingdom experience, general principles for establishing emergency plans are drawn. Every country with nuclear plant should have such emergency arrangements capable of dealing with the largest scale that can be envisaged as a practical possibility. While the effects of accidents cannot be anticipated in detail these plans should form a good flexible basis for providing the resources, communications and procedures that are likely to be needed. They encompass the administrative infrastructure of the area surrounding the nuclear installation and involve co-ordination with the police, fire services and ambulance services, the local and county authorities, the authorities responsible for food, agriculture, fisheries and water, and the health authorities including hospitals and medical services. Special training and procedures have to be established for the personnel that are involved and exercises graduating from the exercising of special procedures to large scale simulated accidents need to be carried out periodically. Good communication systems have to be established between the nuclear installations, the operational support centres or equivalent, the field and headquarters units of the relevant organizations, and the central government departments so that whatever additional resources and support are needed can be marshalled quickly and efficiently. (author)

  10. Effects of the accident at Mihama Nuclear Power Plant Unit 3 on the public's attitude to nuclear power generation

    International Nuclear Information System (INIS)

    Kitada, Atsuko

    2005-01-01

    As part of an ongoing public opinion survey regarding nuclear power generation, which started in 1993, a survey was carried out in the Kansai and Kanto regions two months after the accident at Unit 3 of the Mihama Nuclear Power Plant. In addition to analyzing the statistically significant changes that have taken place since the previous survey (taken in 2003), increase and decrease of the ratio of answers to all the questions related to nuclear power before and after the two accidents were compared in the case of the accidents which occurred in the Mihama Unit 3 and the JCO company's nuclear-fuel plant. In the Kansai region, a feeling of uneasiness about the risky character of nuclear power generation increased to some extent, while the public's trust in the safety of nuclear power plants decreased somewhat. After a safety-related explanation on ''Early detection of troubles'' and Accident prevention'' was given from a managerial standpoint, people felt a little less at ease than they had before. Uneasiness, however, did not increase in relation to the overall safety explanation given about the engineering and technical functioning of the plant. There was no significant negative effect on the respondents' evaluation of or attitude toward nuclear power generation. It was found that the people's awareness about the Mihama Unit 3 accident was lower and the effect of the accident on their awareness of nuclear power generation was more limited and smaller when compared with the case of the JCO accident. In the Kanto region, people knew less about the Mihama Unit 3 accident than those living in the Kansai region, and they remembered the JCO accident, the subsequent cover-up by Tokyo Electric Power Company, and the resulting power shortage better than those living in Kansai. This suggested that there was a little difference in terms of psychological distance in relation to the accidents an incidents depending on the place where the events occurred and the company which

  11. Science, society, and America's nuclear waste: Unit 2, Ionizing radiation

    International Nuclear Information System (INIS)

    1992-01-01

    ''Science, Society and America's Nuclear Waste'' is a four-unit secondary curriculum. It is intended to provide information about scientific and societal issues related to the management of spent nuclear fuel from generation of electricity at nuclear powerplants and high-level radioactive waste from US national defense activities. The curriculum, supporting classroom activities, and teaching materials present a brief discussion of energy and electricity generation, including that produced at nuclear powerplants; information on sources, amounts, location, and characteristics of spent nuclear fuel and high-level radioactive waste; sources, types and effects of radiation; US policy for managing and disposing of spent nuclear fuel and high-level radioactive waste and what other countries are doing; and the components of the nuclear waste management system

  12. The independent nuclear state. The United States, Britain and the military atom

    International Nuclear Information System (INIS)

    Simpson, J.

    1983-01-01

    A chronological account and overview are presented of the 40-year history of British military research, development and production work in atomic energy. The United Kingdom's efforts in this field have always had close links with equivalent activities in the United States, and have often been conducted on a mutually co-operative basis. This book contains descriptions of the technical evolution of British nuclear weapon designs and production models, estimates of annual output figures for fissile material and weapon types, and indications of the nature of the weapon-testing programme. Decision-points are charted. The impact of the agreements with the United States, both upon weapon development and production programmes and upon stockpiling, is analysed, as well as their effects upon the nuclear submarine programme. The impact of later events upon Anglo-American relations is identified, together with the recent British attempts to move to a closer political association with Europe. The study concludes by evaluating the essential nature of four decades of United Kingdom military nuclear development, and identifying the practical limits imposed by past policies upon any attempt by a British government to implement a policy of unilateral nuclear disarmament. (author)

  13. Nuclear engineering education in the United States: a status report

    International Nuclear Information System (INIS)

    Miller, D.W.; Spinrad, B.I.

    1986-01-01

    The executive summary of the White Paper entitled The Revitalization of Nuclear Energy Education in the United States is the major component of this paper. The White Paper was completed under the auspices of the Nuclear Engineering Department Heads Organization (NEDHO). The presentation highlights events and program changes that have occurred in 1985-1986 following publication of the NEDHO White Paper. Many of these events provide optimism for the revitalization of nuclear engineering education

  14. Standardization of nuclear power plants in the United States: recent regulatory developments

    International Nuclear Information System (INIS)

    Cowan, B.Z.; Tourtellotte, J.R.

    1992-01-01

    On April 18, 1989, the United States (U.S.) Nuclear Regulatory Commission (NRC) amended the regulations governing the process for licensing nuclear power plants in the United States to provide for issuance of early site permits, standard design certifications and combined construction permits and operating licenses for nuclear power reactors. The new regulations are designed to achieve early resolution of licensing issues and facilitate standardization of nuclear power plants in the United States. The program for design standardization is central to efforts mounted by the U.S. government and industry to ensure that there will be a next generation of nuclear power facilities in the U.S. The most significant changes are provisions for certification of standard designs and for issuance prior to start of construction of combined licenses which incorporate a construction permit and an operating license with conditions. Such certifications and combined licenses must contain tests, inspections and analyses, and acceptance criteria, which are necessary and sufficient to provide reasonable assurance that the facility has been constructed and will operate in accordance with the combined license. A number of significant implementation issues have arisen. In addition a major court case brought by several anti-nuclear groups is pending, challenging NRC authority to issue combined licenses. It is the goal of the U.S. nuclear industry to have the first of the next generation of standardized nuclear power plants ordered, licensed, constructed and on-line by the year 2000. (author)

  15. Preoperation of Hamaoka Nuclear Power Station Unit No. 4

    International Nuclear Information System (INIS)

    Fukuyo, Tadashi; Kurata, Satoshi

    1994-01-01

    Chubu Electric Power Co. finished preoperation of Hamaoka Nuclear Power Station Unit No. 4 in September, 1993. Although unit 4 has the same reactor design as unit 3, its rated electrical output (1,137MW) is 37MW more than that of unit 3. This increase was achieved mainly by adopting a Moisture Separater Heater in the turbine system. We started preoperation of unit 4 in November 1992 and performed various tests at electrical outputs of 20%, 50%, 75%, and 100%. We finished preoperation without any scram or other major problems and obtained satisfactory results for the functions and performance of the plant. This paper describes the major results of unit 4 preoperation. (author)

  16. Minimum DNBR Prediction Using Artificial Intelligence

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Dong Su; Kim, Ju Hyun; Na, Man Gyun [Chosun University, Gwangju (Korea, Republic of)

    2011-05-15

    The minimum DNBR (MDNBR) for prevention of the boiling crisis and the fuel clad melting is very important factor that should be consistently monitored in safety aspects. Artificial intelligence methods have been extensively and successfully applied to nonlinear function approximation such as the problem in question for predicting DNBR values. In this paper, support vector regression (SVR) model and fuzzy neural network (FNN) model are developed to predict the MDNBR using a number of measured signals from the reactor coolant system. Also, two models are trained using a training data set and verified against test data set, which does not include training data. The proposed MDNBR estimation algorithms were verified by using nuclear and thermal data acquired from many numerical simulations of the Yonggwang Nuclear Power Plant Unit 3 (YGN-3)

  17. Cernavoda NPP Unit 2 and Romanian nuclear industry

    International Nuclear Information System (INIS)

    Mocanu Horia

    2001-01-01

    On 18 May 2001, in the presence of Mr. Adrian Nastase, the Prime-Minister of Romania, the presidents of AECL, ANSALDO and Director General of SN Nuclearelectrica, the commercial and management contract for completing the Cernavoda NPP Unit 2 was signed. This document stipulates the goal and the partners' commitments, leadership organization, the SN Nuclearelectrica's control of the Budget, costs for the technical assistance (around 180 specialists from abroad), as well as the costs of equipment supplied from Canada and Italy. Services and equipment supplied by Canada and Italy amounts up to around USD 300 millions. Efforts are currently undertaken to obtain a loan of USD 300 millions from EURATOM, beginning from 2003. An auction process, implying around 10 companies, is underway and by the completion of the process, in February 2002, the practical delivery of equipment will start. The so-far invested capital amounts around USD 650 millions while the capital funds remaining to be invested amounts up to about USD 689 millions. From the latter figure, around USD 100 millions represent the costs for heavy water and the initial nuclear fuel charging. The personnel dynamics is presented as well as problems relating with recruitment and salary policy. Romanian nuclear industry is engaged for supply of a series of important components. General Turbo SA, supplied already components of some tens USD millions for the turbogenerator complex. PETROTUB company from Roman, Romania supplied already one thousand tones of non-nuclear carbon steel tubing valued at about USD 300 millions. ARIO, Bistrita, Romania, has signed contracts valued at about USD 400,000 for non-nuclear reinforcing materials. Other companies like AVERSA SA and Ventilatorul SA supplied reliable equipment for Unit 1 and will continue to do the same for Unit 2. Contracts of over one million USD are carried on with VULCAN for carbon steel fittings and with TITAN Nuclear Equipment for components of the fueling

  18. Designing a nuclear power plant with 1000 MW WWER-type units

    Energy Technology Data Exchange (ETDEWEB)

    Berkovich, V; Kaloshin, J; Tatarnikov, V; Shenderovich, A

    1977-06-01

    A brief description is presented of a WWER-1000 nuclear power plant also considering its environmental impact and the problem of core poisoning. The following indicators are graphically shown in relation to the reactor output: turbogenerator unit outputs, efficiency, specific capital costs and own costs of electric power generated by the Voronezh nuclear power plant. Also listed are the specific consumption of metal and concrete, specific equipment weight and the specific volume of the buildings of the main generating unit as well as the cross section thereof.

  19. Situation and development trend of nuclear power and uranium industry in the united states and Russia

    International Nuclear Information System (INIS)

    Tan Chenglong

    2005-01-01

    This paper introduces the situation, trend of nuclear electrical and uranium industry in the United States and Russia. The United States and Russia are the two biggest countries in the world which generated nuclear power earliest. After 40 years' development, nuclear power in the United States and Russia are approximately 20%, 11% respectively of the total generation capacity in 2001. In the United States, only 6% of the nuclear power consumed uranium resource is domestic, in Russia about half of its uranium production is for export. Due to the collision between the energy development and environment protection, nuclear power in USA is still strong, but the uranium industry declines. In the future, uranium production for nuclear power in the United States will depend on the international market and the uranium storage of different levels. On the basis of pacifying people and making the country prosper, Russia has established their great plans for nuclear power with their substantial uranium resources. The author considers the supply and demand of uranium industry will remain balanced in the future decade on the whole, despite the United States and Russia's trend of uranium industry could take a major effect on uranium industry to the world. (authors)

  20. New generation nuclear power units of PWR type integral reactors

    International Nuclear Information System (INIS)

    Mitenkov, F.M.; Kurachen Kov, A.V.; Malamud, V.A.; Panov, Yu.K.; Runov, B.I.; Flerov, L.N.

    1997-01-01

    Design bases of new generation nuclear power units (nuclear power plants - NPP, nuclear co-generation plants - NCP, nuclear distract heating plants - NDHP), using integral type PWPS, developed in OKBM, Nizhny Novgorod and trends of design decisions optimization are considered in this report. The problems of diagnostics, servicing and repair of the integral reactor components in course of operation are discussed. The results of safety analysis, including the problems of several accident localization with postulated core melting and keeping corium in the reactor vessel and guard vessel are presented. Information on experimental substantiation of the suggested plant design decisions is presented. (author)

  1. The role of Nuclear Energy Unit in gathering, organizing and disseminating of nuclear information

    International Nuclear Information System (INIS)

    Samsurdin Ahamad

    1986-01-01

    The Nuclear Energy Unit (UTN) was established with an aim to promote the application of Nuclear Science and Technology in industries, agriculture and medicine in Malaysia. Therefore UTN represents Malaysia in INIS so as to share the available information for collection, merging and dissemination of information. In UTN a variety of activities are being carried out, especially by the Information Science Department whereby a library, equipped with reading materials and a computerized information system (SMBK) is set up as the information centre. A number of publications have also been made so as to keep the technical officers and other staff aware of the developments in Nuclear Science and Technology. To provide a better understanding of the latest techniques and nuclear technological procedures, courses, seminars and workshops for officers involved are carried out. Talks and exhibitions are also organized in order to promote Nuclear Science and Technology amongst the layman. (author)

  2. Designing a nuclear power plant with 1000 MW WWER-type units

    International Nuclear Information System (INIS)

    Berkovich, V.; Kaloshin, J.; Tatarnikov, V.; Shenderovich, A.

    1977-01-01

    A brief description is presented of a WWER-1000 nuclear power plant also considering its environmental impact and the problem of core poisoning. The following indicators are graphically shown in relation to the reactor output: turbogenerator unit outputs, efficiency, specific capital costs and own costs of electric power generated by the Voronezh nuclear power plant. Also listed are the specific consumption of metal and concrete, specific equipment weight and the specific volume of the buildings of the main generating unit as well as the cross section thereof. (J.B.)

  3. Replacement energy costs for nuclear electricity-generating units in the United States: 1997--2001. Volume 4

    International Nuclear Information System (INIS)

    VanKuiken, J.C.; Guziel, K.A.; Tompkins, M.M.; Buehring, W.A.

    1997-09-01

    This report updates previous estimates of replacement energy costs for potential short-term shutdowns of 109 US nuclear electricity-generating units. This information was developed to assist the US Nuclear Regulatory Commission (NRC) in its regulatory impact analyses, specifically those that examine the impacts of proposed regulations requiring retrofitting of or safety modifications to nuclear reactors. Such actions might necessitate shutdowns of nuclear power plants while these changes are being implemented. The change in energy cost represents one factor that the NRC must consider when deciding to require a particular modification. Cost estimates were derived from probabilistic production cost simulations of pooled utility system operations. Factors affecting replacement energy costs, such as random unit failures, maintenance and refueling requirements, and load variations, are treated in the analysis. This report describes an abbreviated analytical approach as it was adopted to update the cost estimates published in NUREG/CR-4012, Vol. 3. The updates were made to extend the time frame of cost estimates and to account for recent changes in utility system conditions, such as change in fuel prices, construction and retirement schedules, and system demand projects

  4. Public acceptance of nuclear power generation in the United States

    International Nuclear Information System (INIS)

    Liverman, J.L.; Thorne, R.D.

    1977-01-01

    Within the United States environmental awareness has spread and matured since the early 1960's. Evidence of this is found in cautious attitudes toward the installation of nuclear power reactors and other components of the nuclear fuel cycle. Hazards associated with nuclear energy technologies appear to attract a greater share of public attention than the hazards of nonnuclear counterparts. The association of nuclear power with nuclear weapons may be at the root of this concern. The explicit identification of increased incidences of cancer and genetic effects in humans as potential consequences of exposure to ionizing radiation and knowledge that radiation exposures and health consequences arising from nuclear power operations might occur many generations after operations cease also underlie this concern. Based in large part on these concerns, a number of actions have been taken in the United States to prevent and to delay installation and development of nuclear technology. These actions are reviewed and analyzed with emphasis on the 1976 California nuclear moratorium referendum and other more recent actions at state and national levels. They are compared with the status and outcome of similar actions in other nations as is possible. Additionally, ERDA's current approaches to public involvement in the decision making process is discussed, including the value of comprehensive analyses of health, environmental, and socioeconomic aspects of alternative energy sources in responding to public needs. U.S. plans for providing such analyses for all installed and developing energy technologies are presented with special reference to areas which require international cooperation for implementation. The value of international analysis and internationally accepted environmental control strategies for all energy technologies is also addressed

  5. Main messages for the new nuclear unit in Finland

    International Nuclear Information System (INIS)

    Nikula, Anneli

    2001-01-01

    Teollisuuden Voima Oy (TVO) submitted last year, on 15th November, to the Council of State an application for a decision in principle concerning the construction of additional nuclear capacity. In this presentation, the main messages to decision makers for the new unit are discussed. Also the studies, which the messages are based on, are described. According to the Finnish Nuclear Energy Act, a company considering a nuclear plant project must apply for a decision in principle from the Government beforehand. The Government then decides whether the project is in accordance with the overall good of the society. If the decision is positive, it needs ratification by the Parliament. Before the Government decision, various interested parties are heard, including the municipality of location and the Radiation and Nuclear Safety Authority. The phase of statements is underway and they all will be ready by the end of March 2001. The entire application process takes approximately 1-2 years. The main messages arguing for more nuclear power in Finland were as follows. The new nuclear power plant unit replaces old fossil power plants and satisfies the need for additional demand of electricity; makes possible to meet the requirements of the Kyoto agreement; reduces the dependence on the imported energy and assures a stable and predictable electricity price. Messaging concerning a new nuclear power plant unit is made in co-operation with several organisations. The most important of them, in addition to the company shareholders, are the companies which have shown interested in the new project as well as the Finnish Energy Industries Federation (Finergy) and the Confederation of Finnish Industry and Employers. A transparency folder 'Nuclear electricity 2000' was put together of the messages in collaboration with the organisations. The folder was distributed to about 400 opinion leaders in the energy field. To ensure the consistency of the messages, several interest group meetings

  6. Prospects of Nuclear Energy in the United States in the 21st Century

    International Nuclear Information System (INIS)

    Newman, R. E.

    1988-01-01

    The Nuclear Industry is now over 40 years old and a proven, mature product has been developed. That proven mature product has evolve into a small set of standardized designs - designs based on evolution of the best and safest features, not revolutionary changes. Just as the product design must be standardized, the regulatory process must also be standardized. With a predictable regulatory environment and rate structure the economic advantages of Nuclear Power will be self-evident. The Nuclear Industry in the United States has had a history of cycles as the economy and need for power has changed. The need for electricity to support growth is a given. With a strong focus on the standardization of the process and the product, a competent engineering approach to safety, and improved economies, the 21st century will see nuclear power assume its appropriate role as a key source in the energy mix in the United States. Presenting a discussion dealing with the future is always a risky thing. One man's prognosis is another mans wild guess. Today, I would like to talk briefly on my views of the future, and especially my views on the Prospects for Nuclear Energy in the U. S. in that future. Though it is clear that nuclear energy will play a key role in fulfilling the energy needs of the world, the future of nuclear energy in the United States is not as clear. A discussion of the future of the U. S. Nuclear Industry is especially appropriate here today because I am firmly confident that the Republic of Korea will play a major role in that future. The world energy situation and the role of nuclear power has undergone a number of upsets in the last decade. Often we tend to dwell on the gloom of the past and overlook the strengths that the Nuclear Industry has developed. Presently over 437 gigawatts of electricity in the world is planned to be produced by 564 nuclear units. There are over 32 countries with commercial nuclear programs. One of the brightest of these being here in

  7. Proposal for broader United States-Russian transparency of nuclear arms reductions

    International Nuclear Information System (INIS)

    Percival, C.M.; Ingle, T.H.; Bieniawski, A.J.

    1995-01-01

    During the January 1994 Summit Presidents Clinton and Yeltsin agreed on the goal of ensuring the ''transparency and irreversibility'' of the nuclear arms reduction process. As a result, negotiations are presently underway between the United States Government and the Russian Federation to confirm the stockpiles of plutonium and highly enriched uranium removed from nuclear weapons. In December 1994 the United States presented a paper to the Russian Federation proposing additional measures to provide broader transparency of nuclear arms reduction. The US Department of Energy is studying the implementation of these broader transparency measures at appropriate DOE facilities. The results of the studies include draft protocols for implementation, assessments of the implementation procedures and the impacts on the facilities and estimates of the cost to implement these measures at various facilities

  8. An operating nuclear utility's experience with the ALARA design of a new nuclear unit

    International Nuclear Information System (INIS)

    Rodgers, R.C.

    1985-01-01

    This talk presents a review of how operating experience at Northeast Utilities has been factored into the design of a new nuclear unit and the development and management of the radiation protection program. Their operational experience has indicated that there are two facets to keeping radiation exposures ALARA. The first is the proper ALARA design of the unit. The other facet is the design of a comprehensive radiation protection program. The author discusses these facets in some detail

  9. A Study on Improvement of Test Method of Nuclear Power Plant ESF ACS by applying Regulatory Guide 1.52 (Rev.3)

    International Nuclear Information System (INIS)

    Lee, Sook Kyung; Kim, Kwang Sin; Sohn, Soon Hwan; Song, Kyu Min; Lee, Kae Woo; Cho, Byoung Ho; Park, Jeong Seo; Yoo, Byeang Jea; Hong, Soon Joon; Kang, Sun Haeng

    2010-01-01

    U. S. NRC Regulation Guide 1.52 regulating ESF ACS in nuclear power plants has been revised to revision 3. To apply reduction of operability test time, allowance of alternative challenge agents for in-place leak test of HEPA filters, and upgrade of Methyl Iodide penetration acceptance criterion in activated carbon performance test suggested in Reg. Guide 1.52(Rev.3) on Yonggwang units 5 and 6 ESF ACSes, technical feasibility study was carried out with on-site experiments as well as experiments with a lab-scale model. It was confirmed that the moisture in the system returned to the level before the test in 1 or 4 days even though the moisture was removed during the operability test lasting more than 10 hours. Therefore, it is appropriate to perform monthly operability test in 15 minutes just long enough to check the operability of equipment. To change challenge material for in-place HEPA filter leak test, size of aerosol, production rate, and leak detection capability were compared for DOP and PAO. It was concluded that PAO can be substituted for DOP in nuclear power plants. The upgrade of Methyl Iodide penetration acceptance criterion from 0.175 % to 0.5 % in active carbon filter bed deeper than 4 inches was to conform to the change of activated carbon performance test method to ASTM D3803(1989). It was confirmed that Methyl Iodide penetration acceptance criterion of 0.5 % under 30 .deg. C

  10. 75 FR 80547 - Carolina Power & Light Company, Shearon Harris Nuclear Power Plant, Unit No. 1; Exemption

    Science.gov (United States)

    2010-12-22

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

  11. Summary revaluation of energetic start-up of the unit 1 of nuclear power plant Mochovce

    International Nuclear Information System (INIS)

    Sarvaic, I.; Miskolci, M.

    1998-01-01

    The document contents stage revaluation of energetic start-up of the unit 1 of nuclear power plant Mochovce. Test results of the stage of energetic start-up are summarized in the document, valuation of important systems and block devices as well as fulfilling the operation limits and conditions has been performed. On that base conclusions and recommendations for start-up the unit 2 and for commercial operation of the unit 1 are elaborated. The valuation has been elaborated by a scientific management for start-up nuclear power plant Mochovce of nuclear safety of nuclear power facilities. Scientific management for start-up of nuclear power plant Mochovce performed continuous valuation of individual power levels after ending of each individual level and it gave its valuation to energy power level with recommendations and conditions for further start-up process and operation. Scientific management finished its activity at the unit 1 of nuclear power plant Mochovce according to a statute of scientific management for start-up after successful completion of conclusive block run. Scientific management group was founded in February 1998 at nuclear power plant Mochovce. Its members are experts from Slovak, Czech, Russian and French organizations which are participating in power plant completion. Members are listed in a supplement No. 2

  12. A comparison of the nuclear options for greenhouse gas mitigation in China and in the United States

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Chi-Jen, E-mail: cj.y@duke.edu [Center on Global Change, Box 90658, Duke University, Durham, NC 27708 (United States)

    2011-06-15

    China is quickly building up its nuclear power capacity while the hailed nuclear renaissance in the United States has been largely stagnant. The political and industrial structures explain the divergent paths. This paper draws lessons from the French experiences in deploying nuclear power and uses the lessons in comparing Chinese and U.S. policies. An authoritative political system and state-owned utility industry allow China to emulate the French approaches such as government-backed financing and broad-scale deployment with standardized design. The democratic political system and fragmented utility industry, and the laissez-faire ideology in the United States, on the other hand, are unfavorable to a nuclear renaissance. The prospect of a nuclear revival in the United States remains highly uncertain. As China builds up its nuclear industry, it will be able to reduce carbon emissions without a carbon price through a national plan to deploy low-carbon nuclear electricity, while the United States cannot implement a climate policy without a carbon price. American politicians should stop using China's lack of carbon cap as an excuse for postponing the legislation of a carbon price. - Highlights: > The Chinese government and Chinese state-owned companies are indigenizing nuclear power technologies, establishing nuclear manufacturing capacity, and gradually scaling up nuclear power deployment. > China is likely on a path to the biggest nuclear buildup in human history. > The hailed nuclear renaissance in the United States has been largely stagnant. > The underlying causes of U.S. Nuclear stagnation is rooted in the democratic political system and fragmented utility industry, and the laissez-faire ideology, which are unlikely to change in the foreseeable future. > China can move toward a low-carbon electricity system without a carbon price. The United States needs a carbon price to implement a climate policy.

  13. A comparison of the nuclear options for greenhouse gas mitigation in China and in the United States

    International Nuclear Information System (INIS)

    Yang, Chi-Jen

    2011-01-01

    China is quickly building up its nuclear power capacity while the hailed nuclear renaissance in the United States has been largely stagnant. The political and industrial structures explain the divergent paths. This paper draws lessons from the French experiences in deploying nuclear power and uses the lessons in comparing Chinese and U.S. policies. An authoritative political system and state-owned utility industry allow China to emulate the French approaches such as government-backed financing and broad-scale deployment with standardized design. The democratic political system and fragmented utility industry, and the laissez-faire ideology in the United States, on the other hand, are unfavorable to a nuclear renaissance. The prospect of a nuclear revival in the United States remains highly uncertain. As China builds up its nuclear industry, it will be able to reduce carbon emissions without a carbon price through a national plan to deploy low-carbon nuclear electricity, while the United States cannot implement a climate policy without a carbon price. American politicians should stop using China's lack of carbon cap as an excuse for postponing the legislation of a carbon price. - Highlights: → The Chinese government and Chinese state-owned companies are indigenizing nuclear power technologies, establishing nuclear manufacturing capacity, and gradually scaling up nuclear power deployment. → China is likely on a path to the biggest nuclear buildup in human history. → The hailed nuclear renaissance in the United States has been largely stagnant. → The underlying causes of U.S. Nuclear stagnation is rooted in the democratic political system and fragmented utility industry, and the laissez-faire ideology, which are unlikely to change in the foreseeable future. → China can move toward a low-carbon electricity system without a carbon price. The United States needs a carbon price to implement a climate policy.

  14. Mobile Unit and Its Role in the Case of Nuclear Emergencies

    International Nuclear Information System (INIS)

    Franic, Z.

    1998-01-01

    Emergency response mobile units play a significant role in the case of nuclear emergencies. The functioning and practice of such teams depend on the nature and phase of the nuclear emergency. In the acute phase, several teams with good navigational and communication abilities performing simple measurements can provide essential data for characterization of plume location and its magnitude. Therefore, such activities are complemental with the network of telemetric radiation monitors. However, in the late phase of an accident, in order to gather reliable data needed for utilization of remedial and recovery measures, a better equipped mobile units are necessary. (author)

  15. New nuclear power plant unit in Finland accepted by the Finnish Parliament

    International Nuclear Information System (INIS)

    Kaetkae, M.

    2002-01-01

    The nuclear option has been included in Finland's energy strategy since late 1990's. Based on TVO's application the Finnish Parliament accepted in May 2002 the decision in principle to build a new nuclear power plant unit. The main arguments were the growth of electricity demand, reduction of CO 2 emissions, security of energy supply and reasonable as well as predictable electricity price. TVO's intention is to get the new power plant unit into commercial operation at the end of this decade.(author)

  16. International Convention for the Suppression of Acts of Nuclear Terrorism. United Nations 2005: International Convention for the Suppression of Acts of Nuclear Terrorism

    International Nuclear Information System (INIS)

    Anon.

    2005-01-01

    The International Convention for the Suppression of Acts of Nuclear Terrorism is a 2005 United Nations treaty designed to criminalize acts of nuclear terrorism and to promote police and judicial cooperation to prevent, investigate and punish those acts. As of September 2016, the convention has 115 signatories and 106 state parties, including the nuclear powers China, France, India, Russia, the United Kingdom, and the United States. The Convention covers a broad range of acts and possible targets, including nuclear power plants and nuclear reactors; covers threats and attempts to commit such crimes or to participate in them, as an accomplice; stipulates that offenders shall be either extradited or prosecuted; encourages States to cooperate in preventing terrorist attacks by sharing information and assisting each other in connection with criminal investigations and extradition proceedings; and, deals with both crisis situations, assisting States to solve the situations and post-crisis situations by rendering nuclear material safe through the International Atomic Energy Agency (IAEA)

  17. Nuclear power generation costs in the United States of America

    International Nuclear Information System (INIS)

    Willis, W.F.

    1983-01-01

    Increasing world energy prices and shortages of fuel resources make the utilization of nuclear power extremely important. The United States nuclear power industry represents the largest body of nuclear power experience in the world. Analysis of the recent United States experience of substantial increases in the cost of nuclear power generation provides good insight into the interdependence of technological, financial, and institutional influences and their combined impact on the economic viability of nuclear power generation. The various factors influencing ultimate generation costs, including construction cost, fuel cost, regulatory reviews, and siting considerations are discussed, and their relative impacts are explored, including discussion of design complexity and related regulatory response. A closer look into the recent relatively high escalation of nuclear plant construction costs shows how differing economic conditions can affect the relative cost effectiveness of various methods of power generation. The vulnerability of capital-intensive, long-lead-time projects to changes in economic conditions and uncertainty in future power demands is discussed. Likewise, the pitfalls of new designs and increased sophistication are contrasted to the advantages which result from proven designs, reliable engineering, and shorter lead times. The value of reliable architect-engineers experienced in the design and construction of the plant is discussed. A discussion is presented of additional regulatory requirements stemming from public safety aspects of nuclear power. These include recognition of requirements for the very large effort for quality assurance of materials and workmanship during plant construction and operation. Likewise, a discussion is included of the demanding nature of operations, maintenance, and modification of plants during the operational phase because of the need for highly qualified operations and maintenance personnel and strict quality assurance

  18. The Nuclear Decommissioning Authority (United Kingdom) Nuclear Archive: The importance of stakeholder engagement

    International Nuclear Information System (INIS)

    Tucker, Simon; Wisbey, Simon

    2015-01-01

    This presentation sketched how the United Kingdom's Nuclear Decommissioning Authority (NDA) deals with its obligation of identification, storage, preservation, sharing and destruction of records related to the memory of the UK civilian nuclear industry. Based on the experience of the ongoing establishment of a National Nuclear Archive, the speaker reflected on who the main actors are and how they could contribute; to what extent their work should be co-ordinated; whether there are guidelines; whether 'stories' are being generated out of these archives for the benefits of all readerships; and whether there are issues of secrecy. It was highlighted that to successfully maintain the interest and the knowledge, it will be necessary to go beyond the technical and legislative areas and reach out to the wider society, for instance to the fields of education and culture

  19. Job creation due to nuclear power resurgence in the United States

    International Nuclear Information System (INIS)

    Kenley, C.R.; Klingler, R.D.; Plowman, C.M.; Soto, R.; Turk, R.J.; Baker, R.L.; Close, S.A.; McDonnell, V.L.; Paul, S.W.; Rabideau, L.R.; Rao, S.S.; Reilly, B.P.

    2009-01-01

    The recent revival of global interest in the next generation of nuclear power reactors is causing a re-examination of the role of nuclear power in the United States. This renewed interest has led to questions regarding the capability and capacity of current US industries to support a renewal of nuclear power plant deployment. Key among the many questions currently being asked is what potential exists for the creation of new jobs as a result of developing and operating these new plants? Idaho National Laboratory and Bechtel Power Corporation collaborated to perform a Department of Energy-sponsored study that evaluated the potential for job creation in the United States should these new next generation nuclear power plants be built. The study focused primarily on providing an initial estimate of the numbers of new manufacturing jobs that could be created, including those that could be repatriated from overseas, resulting from the construction of these new reactors. In addition to the growth in the manufacturing sector, the study attempted to estimate the potential increase in construction trades necessary to accomplish the new construction. (author)

  20. 76 FR 69120 - Regulatory Changes To Implement the United States/Australian Agreement for Peaceful Nuclear...

    Science.gov (United States)

    2011-11-08

    ... Government of the United States of America Concerning Peaceful Uses of Nuclear Energy'' (the Agreement). The... applicable requirements. Environmental Assessment: Finding of No Significant Environmental Impact The NRC has... and the Government of the United States of America Concerning Peaceful Uses of Nuclear Energy, dated...

  1. Evaluating Russian space nuclear reactor technology for United States applications

    International Nuclear Information System (INIS)

    Polansky, G.F.; Schmidt, G.L.; Voss, S.S.; Reynolds, E.L.

    1994-01-01

    Space nuclear power and nuclear electric propulsion are considered important technologies for planetary exploration, as well as selected earth orbit applications. The Nuclear Electric Propulsion Space Test Program (NEPSTP) was intended to provide an early flight demonstration of these technologies at relatively low cost through extensive use of existing Russian technology. The key element of Russian technology employed in the program was the Topaz II reactor. Refocusing of the activities of the Ballistic Missile Defense Organization (BMDO), combined with budgetary pressures, forced the cancellation of the NEPSTP at the end of the 1993 fiscal year. The NEPSTP was faced with many unique flight qualification issues. In general, the launch of a spacecraft employing a nuclear reactor power system complicates many spacecraft qualification activities. However, the NEPSTP activities were further complicated because the reactor power system was a Russian design. Therefore, this program considered not only the unique flight qualification issues associated with space nuclear power, but also with differences between Russian and United States flight qualification procedures. This paper presents an overview of the NEPSTP. The program goals, the proposed mission, the spacecraft, and the Topaz II space nuclear power system are described. The subject of flight qualification is examined and the inherent difficulties of qualifying a space reactor are described. The differences between United States and Russian flight qualification procedures are explored. A plan is then described that was developed to determine an appropriate flight qualification program for the Topaz II reactor to support a possible NEPSTP launch

  2. CINDU-8 catalogue of numerical neutron data available from the IAEA Nuclear Data Unit

    Energy Technology Data Exchange (ETDEWEB)

    Qood, W M; Attree, P M; Byer, T A; Hjarne, L; Konshin, V A; Lemmel, H D; Lorenz, A [Nuclear Data Unit, International Atomic Energy Agency, Vienna (Austria)

    1969-01-15

    This catalogue is the index to DASTAR, the DAta STorage And Retrieval System of the IAEA Nuclear Data Unit. For the first time, this issue indexes also some parts of evaluated data libraries held at the Nuclear Data Unit. CINDU is written in a slightly modified CINDA format and should be read with the help of the introduction to CINDA. Tables of abbreviations for references and laboratories mentioned in this issue are given on the verso of the front cover. The catalogue serves as a reference to all the experimental and calculated numerical data which are stored at the IAEA Nuclear Data Unit, and each set of data is referred to by an index-number, e.g. DASTAR-00896. The bibliographic references for each experiment are blocked together with the relevant data index entry. All of the indexed data are available to anyone on request. Data should be ordered by their index number. This issue of CINDU is distributed to data centres, members of the International Nuclear Data Committee, correspondents to the IAEA Nuclear Data Unit, and others who have expressed their interest. Entries which have been added or changed since the issue of CINDU-7 are marked with an asterisk following the entry date.

  3. A comparative study of Japan and United States nuclear enterprise: Industry structure and construction experience

    International Nuclear Information System (INIS)

    Hinman, G.W.; Lowinger, T.C.

    1987-01-01

    Both Japan and the United States have undertaken major programs to utilize nuclear power for central station electricity generation. Over the past 20 years, the Japanese have developed their own construction and government regulatory institutions and now have an essentially independent domestic nuclear power program. Nuclear construction and government oversight of nuclear power have developed somewhat differently in Japan and the United States, reflecting to some extent the two countries' different business and social cultures. In the United States the vendor and utility industries are much more fragmented than those in Japan, and construction projects are carried out on a more competitive basis. The Japanese industry operates through a few well-established consortia while the U.S. industry does not. Relations among the national government, the vendors, and the electric utilities tend to be cooperative in Japan while they are more adversarial in the Untied States. This paper discusses these topics in a framework of a comparative study of the countries' nuclear industries. Whether because of the factors mentioned above or for other reasons the success of nuclear power in Japan and the United States has differed dramatically in recent years. This paper compares the performance of the nuclear enterprise in these two countries in terms of the physical attributes of the plants themselves, the labor required to build them, and the construction times required. It also discusses the relationship between initial estimates of costs and schedules and actual results achieved. On all counts, recent Japanese performance has been better than in the United States

  4. Development of the MARS input model for Kori nuclear units 1 transient analyzer

    International Nuclear Information System (INIS)

    Hwang, M.; Kim, K. D.; Lee, S. W.; Lee, Y. J.; Lee, W. J.; Chung, B. D.; Jeong, J. J.

    2004-11-01

    KAERI has been developing the 'NSSS transient analyzer' based on best-estimate codes for Kori Nuclear Units 1 plants. The MARS and RETRAN codes have been used as the best-estimate codes for the NSSS transient analyzer. Among these codes, the MARS code is adopted for realistic analysis of small- and large-break loss-of-coolant accidents, of which break size is greater than 2 inch diameter. So it is necessary to develop the MARS input model for Kori Nuclear Units 1 plants. This report includes the input model (hydrodynamic component and heat structure models) requirements and the calculation note for the MARS input data generation for Kori Nuclear Units 1 plant analyzer (see the Appendix). In order to confirm the validity of the input data, we performed the calculations for a steady state at 100 % power operation condition and a double-ended cold leg break LOCA. The results of the steady-state calculation agree well with the design data. The results of the LOCA calculation seem to be reasonable and consistent with those of other best-estimate calculations. Therefore, the MARS input data can be used as a base input deck for the MARS transient analyzer for Kori Nuclear Units 1

  5. Renovation of the 'old' NPP units as an economically effective way of nuclear power development

    International Nuclear Information System (INIS)

    Zrodnikov, A.V.; Toshinsky, G.I.; Komlev, O.G.; Dragunov, Yu.G.; Stepanov, V.S.; Klimov, N.N.; Kopytov, I.I.; Krushelnitsky, V.N.

    2005-01-01

    In the process of nuclear power development there comes a phase when the old' power-units, which reactor installations have expired the designed and extended service lifetime are withdrawn from operating. At this phase in the case of the same annual investments into nuclear power, the increase of the total set up capacity of the nuclear power will be terminated because introduction of capacities due to construction of 'new' power-units only compensates for the reduction of capacities caused by withdrawing from operating the 'old' power-units. Along with this, taking into account a sizeable difference in the service lifetime of the nuclear steam supplying systems and the rest infrastructure of the nuclear power plants, it is an opportunity to find the solution to the problem of compensating for the withdrawn capacities without considerable increasing the annual investments. This opportunity is connected with use of the innovative nuclear power technology based on multipurpose small power modular fast reactors with lead-bismuth coolant for replacement of the withdrawn capacities (renovation of power-units). The features of the innovative nuclear power technology based on the SVBR-76/100 reactor installations, the results of the technical and economical investigations that demonstrate the high economical efficiency of use of the renovation technology using the SVBR-75/100 reactor modules are presented in the Paper. (author)

  6. Nuclear power reactor licensing and regulation in the United States

    International Nuclear Information System (INIS)

    Shapar, H.K.

    1979-01-01

    The report is devoted to four subjects: an explanation of the origins, statutory basis and development of the present regulatory system in the United States; a description of the various actions which must be taken by a license applicant and by the Nuclear Regulatory Commission before a nuclear power plant can be constructed and placed on-line, an account of the current regulatory practices followed by the US NRC in licensing nuclear power reactors; an identification of some of the 'lessons learned' from the Three Mile Island accident and some proposed regulatory and legislative solutions. (NEA) [fr

  7. Some considerations regarding the reforms of nuclear liability legislation in the United States

    International Nuclear Information System (INIS)

    Welck, S. von

    1980-01-01

    In the United States, as in the Federal Republic of Germany and in Switzerland, some thought is presently being given to reforms of nuclear liability legislation. In each case it was either triggered or influenced by the Three Mile Island incident of March 28, 1979. Some of the current thinking in the United States has already been incorporated in a number of draft bills now before Congress for deliberation and decision. Other draft bills on reforms of U.S. nuclear liability law have been announced. It is certain that this reform of nuclear liability legislation in the United States will be carried out not only with determination and the political will to improve the present situation, but also with the required caution and prudence, and that it will keep Congress busy not only for this term, but also next year. (orig.) [de

  8. An advanced NSSS integrity monitoring system for Shin-Kori nuclear units 3 and 4

    International Nuclear Information System (INIS)

    Oh, Y. G.; Kim, H. B.; Galin, S. R.; Kim, S. H.; Lee, S. J.

    2009-01-01

    The advanced design features of NSSS (Nuclear Steam Supply System) Integrity Monitoring System for Shin-Kori Nuclear Units 3 and 4 are summarized herein. During the overall system design and detailed component design processes, many design improvements have been made for the system. The major design changes are: 1) the application of a common software platform for all subsystems, 2) the implementation of remote access, control and monitoring capabilities, and 3) the equipment redesign and rearrangement that has simplified the system architecture. Changes give an effect on cabinet size, number of cables, cyber-security, graphic user interfaces, and interfaces with other monitoring systems. The system installation and operation for Shin-Kori Nuclear Units 3 and 4 will be more convenient than those for previous Korean nuclear units in view of its remote control capability, automated test functions, improved user interface functions, and much less cabling. (authors)

  9. An Advanced NSSS Integrity Monitoring System for Shin-Kori Nuclear Units 3 and 4

    Science.gov (United States)

    Oh, Yang Gyun; Galin, Scott R.; Lee, Sang Jeong

    2010-12-01

    The advanced design features of NSSS (Nuclear Steam Supply System) Integrity Monitoring System for Shin-Kori Nuclear Units 3 and 4 are summarized herein. During the overall system design and detailed component design processes, many design improvements have been made for the system. The major design changes are: 1) the application of a common software platform for all subsystems, 2) the implementation of remote access, control and monitoring capabilities, and 3) the equipment redesign and rearrangement that has simplified the system architecture. Changes give an effect on cabinet size, number of cables, cyber-security, graphic user interfaces, and interfaces with other monitoring systems. The system installation and operation for Shin-Kori Nuclear Units 3 and 4 will be more convenient than those for previous Korean nuclear units in view of its remote control capability, automated test functions, improved user interface functions, and much less cabling.

  10. The United States nuclear merchant ship program

    International Nuclear Information System (INIS)

    Maynard, E.V.

    1978-01-01

    The issues of financial protection contemplate appropriate financing to permit construction of the involved vessels. In addition, the licensing process will require a demonstrated ability for financial response in the event of injury to persons or damage to property. Since the thrust in the United States is to use the Price-Anderson framework for Insurance and Indemnity, much attention is devoted to this legislation. The pre-existing regime is related to the distinguishing requirements of the Maritime field with proposals being advanced to more nearly parallel the insurance coverage philosophy of Europe, i.e., to utilize insurance pools for the nuclear risks and utilize the conventional insurance market for non-nuclear risks. Public affairs issues impact heavily on legislation efforts and thusly become significant in developing a program for Financial Protection

  11. The Department of Energy's nuclear R and D programmes [United Kingdom

    International Nuclear Information System (INIS)

    1991-08-01

    This Consultation Document reviews how the United Kingdom Department of Energy's nuclear R and D programmes support the Government's nuclear policy and reaches preliminary conclusions about their future direction. It describes the changes the Department has adopted, and is proposing, to ensure that it is better informed about the nuclear R and D it commissions and that the work is carried out cost-effectively. The areas of research reviewed are: safety; radiological protection; safeguards; reactor technology; fusion; decommissioning and waste management. (author)

  12. The Iranian nuclear deal. Caught between centrifuge and separative working unit?

    Energy Technology Data Exchange (ETDEWEB)

    Ghoshal, Debalina

    2017-11-15

    In November 2013, a historic nuclear deal, the Joint Plan of Action (JPA) was struck between Iran and the P5+1 Countries, United States, Russia, China, Britain, France and Germany. Under this deal, Iran agreed to restrict its nuclear program that would close the doors for Iran to develop nuclear weapons. This indeed was historic as for over a decade, ever since the Iranian nuclear program attracted international attention and criticism, several arrangements were made to curtail the Iranian nuclear program, but none reached the desired success. In exchange for abiding by the JPA, Iran was promised partial relief of sanctions. The paper tracks the development and identifies the scope of Iran's centrifuge program.

  13. 75 FR 43571 - Duke Energy Carolinas, LLC; Catawba Nuclear Station, Units 1 and 2; Environmental Assessment And...

    Science.gov (United States)

    2010-07-26

    ... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-413 and 50-414; NRC-2010-0260] Duke Energy Carolinas, LLC; Catawba Nuclear Station, Units 1 and 2; Environmental Assessment And Finding of No Significant... Energy Carolinas, LLC (the licensee), for operation of the Catawba Nuclear Station, Units 1 and 2...

  14. Commerical electric power cost studies. Capital cost addendum multi-unit coal and nuclear stations

    International Nuclear Information System (INIS)

    1977-09-01

    This report is the culmination of a study performed to develop designs and associated capital cost estimates for multi-unit nuclear and coal commercial electric power stations, and to determine the distribution of these costs among the individual units. This report addresses six different types of 2400 MWe (nominal) multi-unit stations as follows: Two Unit PWR Station-1139 MWe Each, Two Unit BWR Station-1190 MWe Each, Two Unit High Sulfur Coal-Fired Station-1232 MWe Each, Two Unit Low Sulfur Coal-Fired Station-1243 MWe Each, Three Unit High Sulfur Coal-Fired Station-794 MWe Each, Three Unit Low Sulfur Coal-Fired Station-801 MWe Each. Recent capital cost studies performed for ERDA/NRC of single unit nuclear and coal stations are used as the basis for developing the designs and costs of the multi-unit stations. This report includes the major study groundrules, a summary of single and multi-unit stations total base cost estimates, details of cost estimates at the three digit account level and plot plan drawings for each multi-unit station identified

  15. Data acquisition and treatment unit for use in nuclear medicine

    Energy Technology Data Exchange (ETDEWEB)

    Annaix, C; Prieur, G; Vilayleck, S; Jallet, P [C.H.R., Angers (France)

    1981-01-01

    Here is below a one-channel data acquisition unit piloted through a minicomputer programmed by means of an advanced language of the Basic type. This unit allows, especially in nuclear medicine, pulse counts from a spectrometer according to a programmed sequence. Moreover, it provides treatment of measures as well as printing and filing of interpreted results. The acquisition unit is linked to the minicomputer through a RS 232 C serial mode, which ensures both easy operation and universal use of the system here described. Accuracy of measurement is also examined.

  16. Start up and commercial operation of Laguna Verde nuclear power plant. Unit 1

    International Nuclear Information System (INIS)

    Torres Ramirez, J.F.

    1991-01-01

    Prior to start up of Laguna Verde nuclear power plant preoperational tests and start tests were performed and they are described in its more eminent aspects. In relation to commercial operation of nuclear station a series of indicator were set to which allow the measurement of performance in unit 1, in areas of plant efficiency and personal safety. Antecedents. Laguna Verde station is located in Alto Lucero municipality in Veracruz state, 70 kilometers north-northeast from port of Veracruz and a 290 kilometers east-northeast from Mexico city. The station consist of two units manufactured by General Electric, with a nuclear system of vapor supply also called boiling water (BWR/5), and with a system turbine-generator manufactured by Mitsubishi. Each unit has a nominal power of 1931 MWt and a level design power of 675 Mwe and a net power of 654 Electric Megawatts

  17. Project for construction of a new nuclear unit in Armenia

    International Nuclear Information System (INIS)

    2010-01-01

    WorleyParsons Project Description Scope of work: Management Services for Implementation of the Project on Construction of New Nuclear Unit(s) in the Republic of Armenia. Client: Ministry of Energy and Natural Resources (MENR), Republic of Armenia •Contract signed on 29 of May 2009 •Project divided into 4 Phases. Addendum 1 covers phase I and II signed on 27 of July. Contract entered into force 7 of August

  18. Emergency operating instruction improvements at San Onofre Nuclear Generating Station Units 2 and 3

    International Nuclear Information System (INIS)

    Trillo, M.W.; Smith, B.H.

    1989-01-01

    In late 1987, San Onofre nuclear generating station (SONGS) began an extensive upgrade of the units 2 and 3 emergency operating instructions (EOIs). The original intent of this program was to incorporate revised generic guidance and to correct problems that were identified by operators. While this program was in progress, the US Nuclear Regulatory Commission (NRC) conducted a series of audits of emergency operating procedure (EOP) development and maintenance programs as 16 commercial nuclear facilities in the United States. These audits included four stations with Combustion Engineering-designed nuclear steam supply systems. (One of these audits included a review of preupgrade SONGS units 2 and 3 EOIs.) Significant industrywide comments resulted from these audits. The NRC has stated its intent to continue the review and audit of EOIs and the associated maintenance programs at all US commercial nuclear facilities. The units 2 and 3 EOI upgrade program developed procedural improvements and procedural program maintenance improvements that address many of the existing audit comments that have been received by the industry. Other resulting improvements may be useful in minimizing NRC comments in future such audits. Specific improvements are discussed. The upgrade program resulted in benefits that were not originally anticipated. The results of this program can be of significant use by other utilities in addressing the industrywide concerns that have been raised in recent NRC audits of EOP development and maintenance programs

  19. 77 FR 50533 - Dominion Nuclear Connecticut, Inc.; Millstone Power Station, Unit 3

    Science.gov (United States)

    2012-08-21

    ....; Millstone Power Station, Unit 3 AGENCY: Nuclear Regulatory Commission. ACTION: Environmental assessment and... search, select ``ADAMS Public Documents'' and then select ``Begin Web- based ADAMS Search.'' For problems... Optimized ZIRLO\\TM\\ fuel rod cladding in future core reload applications for Millstone Power Station, Unit 3...

  20. 78 FR 49305 - Luminant Generation Company LLC, Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2...

    Science.gov (United States)

    2013-08-13

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

  1. Radioactive residues at nuclear sites in the United States of America

    International Nuclear Information System (INIS)

    Fiore, J.; Rampertaap, A.; Greeves, J.; MacKinney, J.; Raguso, M.; Selstrom, J.

    2000-01-01

    The United States of America has a large number of sites where radioactive materials have been mined, processed, produced, or used. Upon completion of activities at these sites, some will be cleaned up completely and released for unrestricted future use. However, at other sites, contamination will remain on the site following cleanup, requiring long term institutional controls. Depending on the purpose or the activity conducted at a specific site, these locations are generally under the jurisdiction of a federal agency: the United States Department of Energy, the United States Nuclear Regulatory Commission, the United States Environmental Protection Agency, or the United States Department of Defense. However, under certain conditions, the Nuclear Regulatory Commission relinquishes regulatory authority to individual states to regulate the commercial uses of radioactive materials (except for nuclear reactors), so some locations with radioactive materials are under the jurisdiction of individual states. Other sites with naturally occurring radioactive contamination may also be controlled by individual states. One or two sites under the jurisdiction of each agency are discussed where radioactive materials either existed in the past or exist today, and the source of contamination, the anticipated end state, and the process by which the responsible agency did or will conduct cleanup and site closure are described. Several issues are reviewed that must be addressed in order to design and implement remediations that will ensure long term protection for the environment and future inhabitants. The role of citizens in environmental cleanups is examined, and how institutional controls may be applied to ensure long term protection of remediations that leave some contaminants in place. (author)

  2. United Nuclear Industries, Inc. reactor and fuel production facilities 1975 environmental release report

    International Nuclear Information System (INIS)

    Cucchiara, A.L.

    1976-01-01

    During calendar year 1975, an estimated total of 3,000,000 pounds of waste materials and approximately 150 curies of radionuclides were discharged to the environs in liquid effluent streams emanating from United Nuclear Industries, Inc., operated facilities. During the same period, approximately 1,700,000 pounds of reported waste materials, including 34,000 curies of reported radionuclides, were discharged to the atmosphere from United Nuclear Industries, Inc., operated facilities. Superscript numbers reference explanatory notes contained at the end of the report

  3. Nuclear power in the United Arab Emirates: Legal framework and regulatory cooperation

    International Nuclear Information System (INIS)

    Vasquez-Maignan, X.

    2012-01-01

    As part of a decision to diversify its energy mix, the United Arab Emirates (UAE) has begun construction of its first nuclear power plant. In that context, it has also taken a number of important steps to integrate itself into the international regime for nuclear safety: adoption of the UAE's Federal Law No. 6 of 2009 on the peaceful uses of nuclear energy, establishment of the Federal Authority for Nuclear Regulation (FANR), establishment of the Emirates Nuclear Energy Corporation (ENEC), awarding of the first contract for nuclear power plants in the UAE, etc. The UAE nuclear liability regime is then presented, with details on the basic principles that form the foundation of the nuclear liability conventions, followed by the participation of the FANR in the Multinational Design Evaluation Programme (MDEP) in September 2012

  4. Licensing the first nuclear power plant in the United Arab Emirates

    International Nuclear Information System (INIS)

    Grant, I.

    2013-01-01

    United Arab Emirates (UAE) has established a comprehensive legal & regulatory framework conforming to IAEA standards/guidance to regulate the nuclear sector. Federal Authority for Nuclear Regulation (FANR) is a functioning independent nuclear regulator providing controls on safety, security and non-proliferation. UAE benefits from strong international support, incl. IAEA and access to Korean organizations and practices. UAE has an active capacity building programme both human and technical. Peer reviews show UAE regulatory system is aligned with good international practices. UAE has long term commitment to develop and maintain safety culture.

  5. United States nuclear regulatory commission program for inspection of decommissioning nuclear power plants

    International Nuclear Information System (INIS)

    Harris, P.W.

    2001-01-01

    The United States Nuclear Regulatory Commission (USNRC or Commission) has been inspecting decommissioning commercial nuclear power plants in the United States (U.S.) since the first such facility permanently shutdown in September 1967. Decommissioning inspections have principally focused on the safe storage and maintenance of spent reactor fuel; occupational radiation exposure; environmental radiological releases; the dismantlement and decontamination of structures, systems, and components identified to contain or potentially contain licensed radioactive material; and the performance of final radiological survey of the site and remaining structures to support termination of the USNRC-issued operating license. Over the last 5 years, USNRC inspection effort in these areas has been assessed and found to provide reasonable confidence that decommissioning can be conducted safely and in accordance with Commission rules and regulations. Recently, the staff has achieved a better understanding of the risks associated with particular decommissioning accidents 1 and plans to apply these insights to amendments proposed to enhance decommissioning rules and regulations. The probabilities, scenarios, and conclusions resulting from this effort are being assessed as to their applicability to the inspection of decommissioning commercial power reactors. (author)

  6. United States nuclear regulatory commission program for inspection of decommissioning nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Harris, P.W. [U.S. Nuclear Regulatory Commission, Washington, DC (United States)

    2001-07-01

    The United States Nuclear Regulatory Commission (USNRC or Commission) has been inspecting decommissioning commercial nuclear power plants in the United States (U.S.) since the first such facility permanently shutdown in September 1967. Decommissioning inspections have principally focused on the safe storage and maintenance of spent reactor fuel; occupational radiation exposure; environmental radiological releases; the dismantlement and decontamination of structures, systems, and components identified to contain or potentially contain licensed radioactive material; and the performance of final radiological survey of the site and remaining structures to support termination of the USNRC-issued operating license. Over the last 5 years, USNRC inspection effort in these areas has been assessed and found to provide reasonable confidence that decommissioning can be conducted safely and in accordance with Commission rules and regulations. Recently, the staff has achieved a better understanding of the risks associated with particular decommissioning accidents 1 and plans to apply these insights to amendments proposed to enhance decommissioning rules and regulations. The probabilities, scenarios, and conclusions resulting from this effort are being assessed as to their applicability to the inspection of decommissioning commercial power reactors. (author)

  7. Pressurized thermal shock evaluation of the Calvert Cliffs Unit 1 Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Abbott, L [ed.

    1985-09-01

    An evaluation of the risk to the Calvert Cliffs Unit 1 nuclear power plant due to pressurized thermal shock (PTS) has been completed by Oak Ridge National Laboratory (ORNL) with the assistance of several other organizations. This evaluation was part of a Nuclear Regulatory Commission program designed to study the PTS risk to three nuclear plants, the other two plants being Oconee Unit 1 and H.B. Robinson Unit 2. The specific objectives of the program were to (1) provide a best estimate of the frequency of a through-the-wall crack in the pressure vessel at each of the three plants, together with the uncertainty in the estimated frequency and its sensitivity to the variables used in the evaluation; (2) determine the dominant overcooling sequences contributing to the estimated frequency and the associated failures in the plant systems or in operator actions; and (3) evaluate the effectiveness of potential corrective measures.

  8. Pressurized thermal shock evaluation of the Calvert Cliffs Unit 1 Nuclear Power Plant

    International Nuclear Information System (INIS)

    Abbott, L.

    1985-09-01

    An evaluation of the risk to the Calvert Cliffs Unit 1 nuclear power plant due to pressurized thermal shock (PTS) has been completed by Oak Ridge National Laboratory (ORNL) with the assistance of several other organizations. This evaluation was part of a Nuclear Regulatory Commission program designed to study the PTS risk to three nuclear plants, the other two plants being Oconee Unit 1 and H.B. Robinson Unit 2. The specific objectives of the program were to (1) provide a best estimate of the frequency of a through-the-wall crack in the pressure vessel at each of the three plants, together with the uncertainty in the estimated frequency and its sensitivity to the variables used in the evaluation; (2) determine the dominant overcooling sequences contributing to the estimated frequency and the associated failures in the plant systems or in operator actions; and (3) evaluate the effectiveness of potential corrective measures

  9. A Study on Performance Evaluation of Safety-Related Protective Coating for Yonggwang Unit 1 and 2

    International Nuclear Information System (INIS)

    Kim, Sung Young; Kim, Young Bum; Lee, Won Sang

    2010-01-01

    Protective coating inside nuclear power plants could find its origin from NRC Reg. Guide 1.82(Rev. 3) regarding current issue for the regulation of foreign materials inside containment building. The current issue for the regulation of foreign materials inside containment considered/determined the current issues only regarding the blockage of sump screen by foreign materials such as coating material, insulator, and other materials, while safety-related coating is separately managed by NRC Reg. Guide 1.54(Rev. 1). In this study, we performed field walk-down to evaluate the as-is condition of protective coating inside containment building which was classified as for structure and for equipment with applying the requirement for safety-related coating

  10. Safety Culture Improvement Activities of YGN 3 and 4

    International Nuclear Information System (INIS)

    Cho, Il Hoon

    2006-01-01

    In nuclear power industry all over the world, we can never overemphasize the importance of nuclear safety. After the Chernobyl accident occurred in 1986, Korean nuclear energy industry had made every effort to enhance nuclear safety culture further. And, as a result of the efforts, Korean government declared the five principles for the nuclear energy safety regulation, which were included in the Nuclear Energy Safety Policy Statement published in 1994. In 2001, through the announcement of Nuclear Safety Charter for the peaceful use of nuclear energy, the Ministry of Science and Technology proclaimed at home and abroad that the protection of citizens and environment by securing nuclear safety should be the highest priority in nuclear energy industry. Occupying almost 40% share of domestic electricity generation, Korea Hydro and Nuclear Power Co. decided 'Safety Top Priority Management' as president's management policy, and clearly presented the safety goal to the personnel. By this, the management can effectively place stress on securing safety, which is our highest priority and the only way to win public confidence toward nuclear energy industry. This is prepared to shortly introduce the activities for improving safety culture in Yonggwang Nuclear Power unit 3 and 4 (YGN 3 and 4)

  11. 76 FR 24064 - Arizona Public Service Company, Palo Verde Nuclear Generating Station, Units 1, 2, and 3, Notice...

    Science.gov (United States)

    2011-04-29

    ... Service Company, Palo Verde Nuclear Generating Station, Units 1, 2, and 3, Notice of Issuance of Renewed... Company (licensee), the operator of the Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (PVNGS... Plants: Supplement 43, Regarding Palo Verde Nuclear Generating Station,'' issued January 2011, discusses...

  12. United States Nuclear Tests, July 1945 through September 1992, December 2000

    Energy Technology Data Exchange (ETDEWEB)

    U.S. Department of Energy, Nevada Operations Office

    2000-12-01

    This document list chronologically and alphabetically by name all nuclear tests and simultaneous detonations conducted by the United States from July 1945 through September 1992. Revision 15, dated December 2000.

  13. Nuclear Electricity in the United States : Providing Energy For The Nation's Security and Well-Being

    International Nuclear Information System (INIS)

    Finger, Harold B.

    1988-01-01

    Nuclear energy in the United States has made major contributions since the small Shippingport prototype power plant began operating in 1957. Recent legislative and regulatory actions, as well as research an development, are indicating that additional nuclear capacity can be available in the years ahead. These actions reflect the public's recognition of the importance of nuclear energy. In addition, recent regulatory actions are reaffirming the health and safety of our current nuclear plants, as well as of those being completed. The performance of our current plants is being improved through the conscious dedication of the entire industry to excellence. There is increasing discussion in the United States of the importance of advanced reactor concepts development. The next generation of nuclear plants is already being ordered outside of the United States for example, here in Korea, in Japan, in the United Kingdom and those plants all use light water reactors. We are pleased that U. S. companies are working with you on these new plants. That continues to mean that we never let up on our drive for excellence. Excellence in operations must continue to be the conscious target of all operators. Excellence in communications to the public of the need for electrical capacity, of the benefits of nuclear energy, and of the excellence being achieved in operations is also essential. And excellence in communication to decision makers at all levels of government is also required to assure that sound legalisation and regulation is established and implemented

  14. Rewriting the history: a new future for the nuclear energy in United Kingdom?

    International Nuclear Information System (INIS)

    Woodman, B.

    2009-01-01

    From ends of the ninety, the new nuclear energy has been rejected three times like an option of viable energy generation for United Kingdom: once during the privatization of the electric supply industry and twice during the subsequent revisions to the energy politicians carried out in 2003. Nevertheless, three years more late, a new debate around the energy politics gave an unusual turning in the industry destination, characterized by the firm consideration in the political calendar about the new reactors development, as well as of governmental politicians guided to impel it. This recent interest arises of restlessness regarding the future security of the supply and to the necessity of reducing the carbon dioxide emissions of United Kingdom. With the purpose of obtaining the sufficient support of civil politicians and investors for the new construction project, the industry will have to devise convincing arguments to prove that it has already solved those problems that it suffered in the past and, also that deserves to receive a special treatment in the liberated market of the electricity. This document synthesizes the structure of the nuclear industry in United Kingdom, some recent historical data and the reasons for those that the new nuclear reactors were not very received in the past. It also indicates the measures that have taken in recent times to modify that perspective. Finally, it analyzes the possible future of the nuclear energy at long term in United Kingdom. (Author)

  15. 76 FR 72007 - ZionSolutions, LLC; Zion Nuclear Power Station, Units 1 and 2; Exemption From Certain Security...

    Science.gov (United States)

    2011-11-21

    ... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-295 and 50-304; NRC-2011-0244] ZionSolutions, LLC; Zion Nuclear Power Station, Units 1 and 2; Exemption From Certain Security Requirements 1.0 Background Zion Nuclear Power Station (ZNPS or Zion), Unit 1, is a Westinghouse 3250 MWt Pressurized Water Reactor...

  16. 75 FR 43572 - Duke Energy Carolinas, LLC, McGuire Nuclear Station, Units 1 and 2; Environmental Assessment and...

    Science.gov (United States)

    2010-07-26

    ... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-369 and 50-370; NRC-2010-0259] Duke Energy Carolinas, LLC, McGuire Nuclear Station, Units 1 and 2; Environmental Assessment and Finding of No Significant... Energy Carolinas, LLC (the licensee), for operation of the McGuire Nuclear Station, Units 1 and 2...

  17. Commercial nuclear power 1988: Prospects for the United States and the world

    International Nuclear Information System (INIS)

    1988-01-01

    This report presents historical data on commercial nuclear power in the United States, with projections of domestic nuclear capacity and generation through the year 2020. The report also gives country-specific projections of nuclear capacity and generation through the year 2010 for other countries in the world outside centrally planned economic areas (WOCA). Information is also presented regarding operable reactors and those under construction in countries with centrally planned economies. This report presents three different nuclear supply scenarios. The Optimistic-case scenario, included in previous issues of this report, has been deleted. 7 figs; 36 tabs

  18. Calculating the Unit Cost Factors for Decommissioning Cost Estimation of the Nuclear Research Reactor

    International Nuclear Information System (INIS)

    Jeong, Kwan Seong; Lee, Dong Gyu; Jung, Chong Hun; Lee, Kune Woo

    2006-01-01

    The estimated decommissioning cost of nuclear research reactor is calculated by applying a unit cost factor-based engineering cost calculation method on which classification of decommissioning works fitted with the features and specifications of decommissioning objects and establishment of composition factors are based. Decommissioning cost of nuclear research reactor is composed of labor cost, equipment and materials cost. Labor cost of decommissioning costs in decommissioning works are calculated on the basis of working time consumed in decommissioning objects. In this paper, the unit cost factors and work difficulty factors which are needed to calculate the labor cost in estimating decommissioning cost of nuclear research reactor are derived and figured out.

  19. Multi-unit Operations in Non-Nuclear Systems: Lessons Learned for Small Modular Reactors

    Energy Technology Data Exchange (ETDEWEB)

    OHara J. M.; Higgins, J.; DAgostino, A.

    2012-01-17

    The nuclear-power community has reached the stage of proposing advanced reactor designs to support power generation for decades to come. Small modular reactors (SMRs) are one approach to meet these energy needs. While the power output of individual reactor modules is relatively small, they can be grouped to produce reactor sites with different outputs. Also, they can be designed to generate hydrogen, or to process heat. Many characteristics of SMRs are quite different from those of current plants and may be operated quite differently. One difference is that multiple units may be operated by a single crew (or a single operator) from one control room. The U.S. Nuclear Regulatory Commission (NRC) is examining the human factors engineering (HFE) aspects of SMRs to support licensing reviews. While we reviewed information on SMR designs to obtain information, the designs are not completed and all of the design and operational information is not yet available. Nor is there information on multi-unit operations as envisioned for SMRs available in operating experience. Thus, to gain a better understanding of multi-unit operations we sought the lesson learned from non-nuclear systems that have experience in multi-unit operations, specifically refineries, unmanned aerial vehicles and tele-intensive care units. In this paper we report the lessons learned from these systems and the implications for SMRs.

  20. Notice to exporters on products prohibited from export (nuclear material, equipment and large nuclear units)

    International Nuclear Information System (INIS)

    1988-01-01

    In order to ensure that the policy to avoid the proliferation of nuclear weapons is complied with, the French Administration applies stricter controls over the export of certain sensitive products, materials and equipment. To this effect, lists of such products, materials and equipment are published in the form of Notices to exporters and periodically revised. This Notice repeals and replaces the previous Notice published in the Official Gazette of 21 January 1986. Annex I contains the list of materials whose export is subject to nuclear non-proliferation controls. Annex II lists the equipment whose export is subject to the same controls. Annex III includes the list of large nuclear units for which an application for prior approval of export must be submitted to the Administrations concerned. (NEA) [fr

  1. Third Party Nuclear Liability: The Case of a Supplier in the United Kingdom

    OpenAIRE

    Thomas, A.; Heffron, R. J.

    2012-01-01

    The law surrounding third party nuclear liability is important to all parties in the nuclear supply chain whether they are providing decommissioning services, project management expertise or a new reactor. This paper examines third party nuclear liability, and in particular, in relation to a Supplier in the nuclear energy sector in the United Kingdom (UK). The term “Supplier” is used in this paper and, depending on the context, is intended to cover all parties in the supply chain providing se...

  2. Safety Evaluation Report on Tennessee Valley Authority: Browns Ferry Nuclear Performance Plan: Browns Ferry Unit 2 restart

    International Nuclear Information System (INIS)

    1989-04-01

    This safety evaluation report (SER) on the information submitted by the Tennessee Valley Authority (TVA) in its Nuclear Performance Plan, through Revision 2, for the Browns Ferry Nuclear Power Station and in supporting documents has been prepared by the US Nuclear Regulatory Commission staff. The plan addresses the plant-specific concerns requiring resolution before startup of Unit 2. The staff will inspect implementation of those programs. Where systems are common to Units 1 and 2 or to Units 2 and 3, the staff safety evaluations of those systems are included herein. 3 refs

  3. United States Nuclear Tests, July 1945 through September 1992, September 2015

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2015-09-01

    This document lists chronologically and alphabetically by name all nuclear tests and simultaneous detonations conducted by the United States from July 1945 through September 1992. This is Revision 16, dated September 2015.

  4. The study on the mechanical characteristics of concrete of nuclear reactor containment structure

    International Nuclear Information System (INIS)

    Jung, W. S.; Kwon, K. J.; Cho, M. S.; Song, Y. C.

    2000-01-01

    Reactor containment structure of nuclear power plant designed by prestressed concrete causes time-dependent prestress loss due to the mechanical characteristics of concrete. Prestress loss strongly affects to the safety factor of structure under the circumstances of designing, construction and inspection. Thus, this study is to investigate the mechanical characteristics of reactor containment concrete structure of Yonggwang No. 5 and 6. In this study, the compressive strength, modulus of elasticity, poisson's ratio and creep test followed by ASTM code are performed to investigate the mechanical characteristics of concrete made by V type cement. Additionally, since creep causes more time-dependent prestress loss than the other, the measurement value from the creep test is compared with the results from the creep prediction equations by KSCE, JSCE, Hansen, ACI and CEB-FIP model for the effective application. Hereafter, the results of this study may enable to assist the calculation effective stress considering time-dependent prestress loss of the prestressed concrete structures

  5. Interaction of science and diplomacy: Latin American, the United States and nuclear energy, 1945-1955

    International Nuclear Information System (INIS)

    Cabral, R.

    1986-01-01

    Nuclear programs in Argentina and Brazil can be traced to August 1945 when their scientific communities articulated responses to the atomic bombings of Japan. They culminated in attempts to develop independent nuclear programs, sharply opposed by the United States, during the nationalist governments of Juan Peron and Getulio Vargas. This dissertation, based on primary sources from the three nations, analyzes these programs and the American responses. Latin America entered the nuclear age attempting to control natural resources, to improve scientific establishments, and to appraise Latin American-United States relations. Despite some clear warnings about nuclear dangers, the new form of energy was seen as the solution to industrial problems, poverty, and outside political interference. International opposition, which may have included nuclear threats from the United States, blocked Argentina's first attempt in 1947. After 1948, Peron wanted a nuclear program for cheap energy and prestige. The qualifications of the Brazilian scientists gave more substance to their program. The program originated in August, 1945, but assumed national proportion with the government of Vargas in 1951. Lack of American cooperation forced Vargas to establish a secret program with Germany. American troops intervened taking over the German equipment already completed. The final collapse came about with Vargas' suicide in August, 1954

  6. Nuclear material control in the United States

    International Nuclear Information System (INIS)

    Jaeger, C.; Waddoups, I.

    1995-01-01

    The Department of Energy has defined a safeguards system to be an integrated system of physical protection, material accounting and material control subsystems designed to deter, prevent, detect, and respond to unauthorized possession, use, or sabotage of SNM. In practice, safeguards involve the development and application of techniques and procedures dealing with the establishment and continued maintenance of a system of activities. The system must also include administrative controls and surveillance to assure that the procedures and techniques of the system are effective and are being carried out. The control of nuclear material is critical to the safeguarding of nuclear materials within the United States. The U.S. Department of Energy includes as part of material control four functional performance areas. They include access controls, material surveillance, material containment and detection/assessment. This paper will address not only these areas but also the relationship between material control and other safeguards and security functions

  7. Development of regulatory requirements/guides for desalination unit coupled with nuclear plant

    International Nuclear Information System (INIS)

    Jo, Jong Chull; Yune, Young Gill; Kim, Woong Sik

    2005-10-01

    The basic design of System-integrated Modular Advanced Reactor (SMART), a small-to-medium sized integral type pressurized water reactor (PWR) with the capacity of 330MWth, has been developed in Korea. In order to demonstrate the safety and performance of the SMART design, 'Development Project of SMART-P (SMART-Pilot Plant)' has been being performed as one of the 'National Mid and Long-term Atomic Energy R and D Programs', which includes design, construction, and start-up operation of the SMART-P with the capacity of 65MWth, a 1/5 scaled-down design of the SMART. At the same time, a study on the development of regulatory requirements/guides for the desalination unit coupled with nuclear plant has been carried out by KINS in order to prepare for the forthcoming SMART-P licensing. The results of this study performed from August of 2002 to October of 2005 can be summarized as follows: (1) The general status of desalination technologies has been survey. (2) The design of the desalination plant coupled with the SMART-P has been investigated. (3) The regulatory requirements/guides relevant to a desalination unit coupled with a nuclear plant have been surveyed. (4) A direction on the development of domestic regulatory requirements/guides for a desalination unit has been established. (5) A draft of regulatory requirements/guides for a desalination unit has been developed. (6) Expert technical reviews have been performed for the draft regulatory requirements/guides for a desalination unit. The draft regulatory requirements/guides developed in this study will be finalized and can be applied directly to the licensing of the SMART-P and SMART. Furthermore, it will be also applied to the licensing of the desalination unit coupled with the nuclear plant

  8. Nuclear units operating improvement by using operating experience

    International Nuclear Information System (INIS)

    Rotaru, I.; Bilegan, I.C.

    1997-01-01

    The paper presents how the information experience can be used to improve the operation of nuclear units. This areas include the following items: conservative decision making; supervisory oversight; teamwork; control room distraction; communications; expectations and standards; operator training and fundamental knowledge, procedure quality and adherence; plant status awareness. For each of these topics, the information illustrate which are the principles, the lessons learned from operating experience and the most appropriate exemplifying documents. (authors)

  9. Progress of the United States foreign research reactor spent nuclear fuel acceptance program

    International Nuclear Information System (INIS)

    Huizenga, D.G.; Clapper, M.; Thrower, A.W.

    2002-01-01

    The United States Department of Energy (DOE), in consultation with the Department of State (DOS), adopted the Nuclear Weapons Nonproliferation Policy Concerning Foreign Research Reactor Spent Nuclear Fuel in May 1996. To date, the Foreign Research Reactor (FRR) Spent Nuclear Fuel (SNF) Acceptance Program has completed 23 shipments. Almost 5000 spent fuel assemblies from eligible research reactors throughout the world have been accepted into the United States under this program. Over the past year, another cross-country shipment of fuel was accomplished, as well as two additional shipments in the fourth quarter of calendar year 2001. These shipments attracted considerable safeguards oversight since they occurred post September 11. Recent guidance from the Nuclear Regulatory Commission (NRC) pertaining to security and safeguards issues deals directly with the transport of nuclear material. Since the Acceptance Program has consistently applied above regulatory safety enhancements in transport of spent nuclear fuel, this guidance did not adversely effect the Program. As the Program draws closer to its termination date, an increased number of requests for program extension are received. Currently, there are no plans to extend the policy beyond its current expiration date; therefore, eligible reactor operators interested in participating in this program are strongly encouraged to evaluate their inventory and plan for future shipments as soon as possible. (author)

  10. Comparative costs of coal and nuclear-generated electricity in the united states

    International Nuclear Information System (INIS)

    Brandfon, W.W.

    1987-01-01

    This paper compares the future first-year operating costs and lifetime levelized costs of producing baseload coal- and nuclear-generated electricity under schedules shorter than those recently experienced at U.S. plants. Nuclear appears to have a clear economic advantage. Coal is favorable only when it is assumed that the units will operate at very low capacity factors and/or when the capital cost differential between nuclear and coal is increased far above the recent historical level. Nuclear is therefore a cost-competitive electric energy option for utilities and should be considered as an alternative to coal when large baseload capacity is required. (author)

  11. The nuclear energy in the United Kingdom; L'energie nucleaire au Royaume-Uni

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-02-15

    With challenges like the climatic change, the hydrocarbons prices increase and the energy supply security, the nuclear park is becoming a decisive and an urgent question in the United Kingdom. The author proposes an historical aspect of the nuclear energy in UK, the actors of the today nuclear industry and the technologies used in 2006, the radioactive wastes management, the programs of the future and the british opinion on the nuclear. (A.L.B.)

  12. Use of a tangential filtration unit for processing liquid waste from nuclear laundries

    International Nuclear Information System (INIS)

    Augustin, X.; Buzonniere, A. de; Barnier, H.

    1993-01-01

    Nuclear laundries produce large quantities of weakly contaminated effluents charged with insoluble and soluble products. In collaboration with CEA, TECHNICATOME has developed an ultrafiltration process for liquid waste from nuclear laundries, associated with prior in-solubilization of the radiochemical activity. This process 'seeded ultrafiltration' is based on the use of decloggable mineral filter media and combines very high separation efficiency with long membrane life. The efficiency of the tangential filtration unit which has been processing effluents from the Cadarache Nuclear Research Center (CEA-France) nuclear laundry since mid-1988, has been confirmed on several sites

  13. United Kingdom Nuclear Science Forum Progress Report. Data Studies during 2008

    Energy Technology Data Exchange (ETDEWEB)

    Hawkes, N.P. (ed.) [National Physical Laboratory, Acoustics and Ionising Radiation Division, Middlesex (United Kingdom)

    2010-02-15

    The United Kingdom Nuclear Science Forum (UKNSF) meets twice a year to discuss issues relating to the measurement and evaluation of nuclear data. Topics cover a wide range of applications in the UK nuclear industry. Links between members are maintained throughout the year, mainly through e-mail and the UKNSF website (www.uknsf.ofg.uk). Work of primary interest includes the measurement and evaluation of decay data (e.g. half-lives and gamma ray emission probabilities), fission yields, and neutron cross sections for fission and fusion. All known studies within the UK are summarised in this report. Specific applications and international links of relevance are also described. (author)

  14. United Kingdom Nuclear Science Forum Progress Report. Data Studies during 2008

    International Nuclear Information System (INIS)

    Hawkes, N.P.

    2010-02-01

    The United Kingdom Nuclear Science Forum (UKNSF) meets twice a year to discuss issues relating to the measurement and evaluation of nuclear data. Topics cover a wide range of applications in the UK nuclear industry. Links between members are maintained throughout the year, mainly through e-mail and the UKNSF website (www.uknsf.ofg.uk). Work of primary interest includes the measurement and evaluation of decay data (e.g. half-lives and gamma ray emission probabilities), fission yields, and neutron cross sections for fission and fusion. All known studies within the UK are summarised in this report. Specific applications and international links of relevance are also described. (author)

  15. The political economy of nuclear energy in the United States

    International Nuclear Information System (INIS)

    Nivola, P.S.

    2004-05-01

    A tendency among commentators, even experts like the author of the sentence above, is to regard the complicated story of nuclear energy in the United States as exceptionally troubled and frustrating. The root cause of the troubles and frustrations, moreover, is commonly thought to be more political than economic. The promise of nuclear power in this country is said to have been dimmed primarily by an eccentrically risk-averse public and an unusually hostile regulatory climate. Practically nowhere else, it is said, have political and legal institutions been so uncooperative. Supposedly the central governments of most other advanced countries have lent far more support to their nuclear industries. And because those governments are assumed to be more aggressive in combating pollution, including greenhouse gas emissions from burning fossil fuels, surely 'the rest of the world' has been doing much more than America to level the playing field for the development of nuclear energy. The following paper challenges this conventional picture. (author)

  16. 78 FR 4467 - UniStar Nuclear Energy, Combined License Application for Calvert Cliffs Power Plant, Unit 3...

    Science.gov (United States)

    2013-01-22

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 52-016; NRC-2008-0250] UniStar Nuclear Energy, Combined License Application for Calvert Cliffs Power Plant, Unit 3, Exemption 1.0 Background UniStar Nuclear Energy (UNE), on behalf of Calvert Cliffs Nuclear Project, LLC and UniStar Nuclear Operating Services...

  17. The comparison of license management procedure for nuclear power plant in China and United States

    International Nuclear Information System (INIS)

    Yu Zusheng

    2006-01-01

    'Tow steps' license management procedure for nuclear power plant has been performed bas- ted on the requirement of 10CFR Part50-DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES in United States since last century fifties. In order to ulterior reduce the risk of investment and technical for new construction nuclear power plants, new regulations 'One step' license management procedure-10CFR Part52-EARLY SITE PERMITS; STANDARD DESIGN CERTIFICATIONS; AND COMBINED LICENSES FOR NUCLEAR POWER PLANTS issued in 1989. The new regulations has been adopted by new design of nuclear power plant, for example AP1000. ‘The similar tow steps’ license management procedure for nuclear power plant has been performed basted on the requirement of HAFO01/01 Rules for the Implementation of Regulations on the Safety Regulation for Civilian Nuclear Installations of the People's Re- public of China Part One: Application and Issuance of Safety License for Nuclear Power Plant (December 1993) in China since last century nineties. This article introduces and compares the requirements and characteristics of above license management procedure for nuclear power plant in China and United States. (author)

  18. Current status of nuclear power in the United States and around the world.

    Science.gov (United States)

    McKlveen, J W

    1990-09-01

    Nuclear energy's share of the world electricity market has been growing over the past 35 years. In 1989, eight generating units entered commercial operation abroad and three new units were licensed in the U.S. In early 1990, Mexico became the 26th country to produce electricity from nuclear power. Currently the 426 operating reactors supply one sixth of the world's total electrical capacity. Fourteen countries have now operated nuclear plants for 20 or more years. Since 1980, France has been the leader in the use of nuclear power and currently generates three quarters of its electricity from 54 nuclear plants. The U.S. has 112 nuclear plants, the largest number of any country in the world. These plants satisfy almost 20 percent of U.S. electrical energy requirements. Last year Three Mile Island, the would-be icon for everything that is wrong with the nuclear industry was rated as the most efficient nuclear plant in the world. The worldwide trend toward acceptance of nuclear is improving slightly, but many political and societal issues need to be resolved. Whereas recent polls indicate that a majority of the people realize nuclear must be a major contributor to the energy mix of the future, many are reluctant to support the technology until the issue of waste disposal has been resolved. Fears of another Chernobyl, lack of capital, and a new anti-nuclear campaign by Greenpeace will keep the nuclear debate alive in many countries. Additional stumbling blocks in the U.S. include the need to develop a new generation of improved reactor designs which emphasize passive safety features, standardized designs and a stream-lined federal licensing process. Nuclear power is really not dead. Even environmentalists are starting to give it another look. A nuclear renaissance will occur in the U.S. How soon or under what conditions remain to be seen. The next crisis in the U.S. will not be a shortage of energy, rather a shortage of electricity.(ABSTRACT TRUNCATED AT 250 WORDS)

  19. 78 FR 14361 - In the Matter of Luminant Generation Company LLC, Comanche Peak Nuclear Power Plant, Units 1 and...

    Science.gov (United States)

    2013-03-05

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

  20. 78 FR 79709 - Duke Energy Florida, Inc., Crystal River Unit 3 Nuclear Generating Plant Post-Shutdown...

    Science.gov (United States)

    2013-12-31

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 50-302; NRC-2013-0283] Duke Energy Florida, Inc., Crystal River Unit 3 Nuclear Generating Plant Post-Shutdown Decommissioning Activities Report AGENCY: Nuclear Regulatory Commission (NRC). ACTION: Notice of receipt; availability; public meeting; and request...

  1. Nuclear material control and accounting safeguards in the United States

    International Nuclear Information System (INIS)

    Woltermann, H.A.; Rudy, C.R.; Rakel, D.A.; DeVer, E.A.

    1982-01-01

    Material control and accounting (MC and A) of special nuclear material (SNM) must supplement physical security to protect SNM from unlawful use such as terrorist activities. This article reviews MC and A safeguards of SNM in the United States. The following topics are covered: a brief perspective and history of MC and A safeguards, current MC and A practices, measurement methods for SNM, historical MC and A performance, a description of near-real-time MC and A systems, and conclusions on the status of MC and A in the United States

  2. Consistent adoption of the International System of Units (SI) in nuclear science and technology

    Energy Technology Data Exchange (ETDEWEB)

    Klumpar, J; Kovar, Z [Ceskoslovenska Akademie Ved, Prague. Laborator Radiologicke Dozimetrie; Sacha, J [Slovenska Akademia Vied, Bratislava (Czechoslovakia). Fyzikalny Ustav

    1975-11-01

    The principles are stressed behind a consistent introduction of the International System of Units (SI) in Czechoslovakia complying with the latest edition of the Czechoslovak Standard CSN 01 1300 on the prescribed system of national and international units. The use of special and auxiliary units in nuclear physics and technology is discussed, particular attention being devoted to the units of activity and to the time units applied in radiology. Conversion graph and tables are annexed.

  3. FIND: Douglas Point Nuclear Generating Station, Units 1 and 2

    International Nuclear Information System (INIS)

    Moore, M.M.

    1975-12-01

    This index is presented as a guide to microfiche items 1 through 136 in Docket 50448, which was assigned to Potomac Electric Power Company's Application for Licenses to construct and operate Douglas Point Nuclear Generating Station, Units 1 and 2. Information received from August, 1973 through July, 1975 is included

  4. NO global warming = YES nuclear energy. The International Nuclear Forum and the United Nations Framework Convention on Climate Change

    International Nuclear Information System (INIS)

    Cornish, Emma

    2000-01-01

    The nuclear industry sits along side the renewable energy sector in its role as a non carbon emitting technology. But persuading international political leaders of this fact presents a challenge. Generating electricity from nuclear fuel avoids at least 2 billion tonnes of carbon dioxide every year through its 16% share of world wide electricity generation. Nuclear energy is essential to minimising greenhouse gas emissions. This presentation highlights the main issues resulting from the climate change negotiations that are highly relevant to the industry; explains the activities of the International Nuclear Forum and our interaction with the delegates to the process; outlines future activities. The International Nuclear Forum (INF) was formed to provide a collective voice lobbying for nuclear at the climate change negotiations. It's internationally representative of the industry and comprises of: the Uranium Institute; the Nuclear Energy Institute; the Japan Atomic Industry Forum; the Canadian Nuclear Association; the European Nuclear Society, and Foratom. All are accredited non governmental observers to the negotiations of the United Nations Framework Convention on Climate Change

  5. Comprehensive study on nuclear weapons. Summary of a United Nations study

    International Nuclear Information System (INIS)

    1991-01-01

    In December 1988, by resolution 43/75N, the United Nations General Assembly requested the Secretary-General to carry out a comprehensive update of a 1980 study on nuclear weapons. The study was to take into account recent relevant studies, and consider the political, legal and security aspects of: (a) nuclear arsenals and pertinent technological developments; (b) doctrines concerning nuclear weapons; (c) efforts to reduce nuclear weapons; (d) physical, environmental, medical and other effects of the use of nuclear weapons and of nuclear testing; (e) efforts to achieve a comprehensive nuclear-test ban; (f) efforts to prevent the use of nuclear weapons and their horizontal and vertical proliferation; and (g) the question of verification of compliance with nuclear-arms limitation agreements. The Group's report is presented in nine chapters, eight of which are summarized here; chapter 9, entitled ''Conclusions'', is included in its entirety. In his foreword to the report, the Secretary-General observes that the study represents the most comprehensive review of the relevant developments in the field over the last decade and was carried out during a period of ''far-reaching changes in international relations'' and an ''unprecedented evolution in the relationship between East and West''. This period experienced for the first time the initiation of an effective process of reduction of nuclear weapon stockpiles

  6. Station black out of Fukushima Daiichi Nuclear Power Station Unit 1 was not caused by tsunamis

    International Nuclear Information System (INIS)

    Ito, Yoshinori

    2013-01-01

    Station black out (SBO) of Fukushima Daiichi Nuclear Power Station Unit 1 would be concluded to be caused before 15:37 on March 11, 2011 because losses of emergency ac power A system was in 15:36 and ac losses of B system in 15:37 according to the data published by Tokyo Electric Power Co. (TEPCO) in May 10, 2013. Tsunami attacked the site of Fukushima Daiichi Nuclear Power Station passed through the position of wave amplitude meter installed at 1.5 km off the coast after 15:35 and it was also recognized tsunami arrived at the coast of Unit 4 sea side area around in 15:37 judging from a series of photographs taken from the south side of the site and general knowledge of wave propagation. From a series of photographs and witness testimony, tsunami didn't attack Fukushima Daiichi Nuclear Power Station uniformly and tsunami's arrival time at the site of Unit 1 would be far later than arrival time at the coast of Unit 4 sea side area, which suggested it would be around in 15:39. TEPCO insisted tsunami passed through 1.5 km off the coast around in 15:33 and clock of wave amplitude meter was incorrect, which might be wrong. Thus SBO of Fukushima Daiichi Nuclear Power Station Unit 1 occurred before tsunami's arrival at the site of Unit 1 and was not caused by tsunami. (T. Tanaka)

  7. Nuclear power in the United States: public views and industry actions

    International Nuclear Information System (INIS)

    Poncelet, C.G.

    1981-01-01

    The author describes the public policy environment that surround the nuclear power program in the United States and the social implications as an expression of the public opinion, the mass media as a source of information and the organized opposition movements with their socio-political motivations. The political climate after the new Republican government is also analysed as well as the communication efforts of the nuclear industry to ascertain the need of assertive programs and the sense of cooperation and commitment on the part of both the nuclear and electric utility industries. The general situation is characterized on the one hand by the growing acknowledgement of the need for nuclear power development in an economy dominated by the oil crisis; on the other hand, it is the financial crisis faced by electric utilities which directly impacts on this future development. (AF)

  8. United States panel presentations[Nuclear power technology in the United States

    Energy Technology Data Exchange (ETDEWEB)

    Beyea, J [National Audubon Society, New York, NY (United States)

    1990-07-01

    Before I begin I have to make a disclaimer. That is that I am going to be talking about public perception because I think that is very important. But I do not want to give the impression that I think the public is wrong. I happen to agree with the public's perception of nuclear power, and I want to make that clear. I do not like the current generation of nuclear plants as I have made clear in many statements that I have made. On the other hand, in the long term, I feel that we have only two choices on the supply side, and that is nuclear power and solar electricity. And although I think solar electricity has the best chance, I am realistic enough to know that technologies do not always work the way I want. And so I think it is necessary to have at least some kind of nuclear option available. On the other hand, I do not think just any kind of nuclear technology will do. I want to talk to you about the conditions that I think you have to take into account when you try to design reactors that are publicly acceptable. I look at this as an insurance policy. Again, I do not want to be misquoted: I think nuclear power should be considered as an insurance policy, not as our first line of defense. Having made those disclaimers, what we need to do is set out a problem statement. The problem statement I set out is, 'How could one design and demonstrate a nuclear reactor that would regain public confidence in the United States, if one chose to do that?' By regaining confidence, I mean regaining sufficient confidence to site reactors at a number of locations. It is a pretty heavy task because the public cannot judge the technical issues. They have to judge the players by their characters and their histories, just as the way we calibrate anyone that knows things that we do not. I have three theses that I think are crucial. The first is that people do not believe in the claims of advocates, of any point of view, not just nuclear power, once the advocates have been proved wrong on

  9. Potential advantages and disadvantages of sequentially building small nuclear units instead of a large nuclear plant

    International Nuclear Information System (INIS)

    Feretic, D.; Cavlina, N.; Grgic, D.

    2008-01-01

    Renewal of nuclear power programs in countries with modest electricity consumptions and weak electrical grid interconnections has raised the question of optimal nuclear power plants sizes for such countries. The same question would be also valid for isolated or weakly connected regions within a large country. Building large size nuclear power plant could be prevented by technical or financial limits. Research programs have been initiated in the International Atomic Energy Agency and in the USA (within the framework of the Global Nuclear Energy Partnership (GNEP) program) with the aim to inspect under which circumstances small and medium reactors could be the preferred option compared to large nuclear plants. The economy of scale is a clear advantage of large plants. This paper compares, by using probabilistic methods, the net cash flow of large and medium size plants, taking as example a large nuclear plant (around 1200 MW) and four sequentially built smaller plants (300 MW). Potential advantages and disadvantageous of both options have been considered. Main advantages of the sequential construction of several identical small units could be the reduced investor risk and reduced investment costs due to the learning effect. This analysis is a part of studies for the Croatian power generating system development. (orig.)

  10. Nuclear safety improvement activities related to WWER-440 units in Bulgaria

    International Nuclear Information System (INIS)

    Gantchev, T.

    1998-01-01

    The systematic evaluation of the deficiencies of the original design of the WWER reactors brought to the development of a Short Term Programme for Safety Upgrading and Modernisation of Kozloduy WWER-440 units. The implementation of this Programme was completed in 1997. The strive for continuos improvement of Kozloduy Nuclear Power Plant (NPP) safety level, the new requirements of the Bulgarian Nuclear Safety Authority and the public concern initiated the development of new Complex Programme for Safety Improvement (PRG'97), now in a process of implementation. (author)

  11. Design Guidelines of a Spring-Damper System for Emergency Diesel Generator Sets

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Min Kyu; Choun, Young Sun; Seo, Jeong Moon

    2007-05-15

    This guidelines described about the procedure of isolation system design for Emergency Diesel Generator (EDG) of Nuclear Power Plant (NPP). First of all, a vibration concept including the ground vibration was described and vibration control system and seismic isolation system were considered. The behavior characteristics and design consideration of coil spring-viscose damper system were summarized. The material properties of foundation of EDG system and the ground were considered. A design load and seismic load for isolation system design were described and an analysis method was explained. Finally, a design example for an EDG in Yonggwang Nuclear Unit 5 and 6 was attached of Appendix. First of all, this design guideline can apply to design of a vibration and seismic isolation system for EDG system and the design example present a design procedure practically. Moreover, this design guideline can be used for isolation design of other rotational machines and other isolation system except spring-damper system.

  12. A paradigm shift needed for nuclear reactors. From economies of unit scale to economies of production scale

    International Nuclear Information System (INIS)

    Li, Ning

    2009-01-01

    The success and sustainability of the nascent 'Nuclear Renaissance' will depend heavily on the timely development and deployment SMRs (small and modular reactors) as a new paradigm to increase economic competitiveness and broaden markets and applications for nuclear energy. A critical assessment of the historical and current reactor construction cost data reveals a troubling trend of rapid escalation in practically all countries, while showing little or negative economies of (unit) scale. The escalation cannot be fully accounted for by cost inflation in materials and labors, or by ratcheting regulations and other external factors. Rather, it appears that the intrinsic complexity and the associated risks and costs of extremely large systems have offset all returns of (unit) scale in power engineering and learning effects in practice. The construction heavy nature of the nuclear power plants exacerbates the cost problem as compared to that of the manufactured goods. The power markets have evolved away from the very large monolithic generation units toward modular units more amenable for manufacturing and transportation. This is clearly illustrated through the increasingly bi-modal distribution of generation units around a few MWe (wind, micro-turbines etc) and 100-200 MWe (gas turbine and combined cycle). The rapid market adoption and penetration of these units dwarf the addition rates of the very large units. This is not merely an outcome based on economic and financial risk reduction (important in their own right) or better match of applications - the technological and operational performances are equal or even superior in these smaller modular units. This presentation will use the industry, market and application data analyses, and successful examples from other sectors and industries with different organizing principles to demonstrate the benefits and potentials of SMRs. The resultant paradigm shift, from the singular pursuit of economies of unit scale to

  13. Rise and fall of nuclear power in the United States and the limits of regulation

    International Nuclear Information System (INIS)

    Del Sesto, S.L.

    1982-01-01

    This paper documents the rapid growth of nuclear power in the United States and its subsequent decline in the late 1970s. It demonstrates that the increase in numbers of new orders for nuclear plants created pressures for additional licensing complexity to insure safety and provide public intervenors with opportunities to participate in the regulatory process. The resulting protraction of the licensing process combined with increasing political opposition to nuclear power caused construction delays and bureaucratic bottlenecks at a time when soaring interest rates and double-digit inflation have pushed the cost of building new facilities out of the reach of the financially battered utility industry. Together with a downturn in demand for electricity and increasing uncertainty over nuclear power, no reactor orders have been placed since late 1978. It is argued that renewed growth of nuclear power in the United States is unlikely, especially in a regulatory environment which fosters increased costs of electricity to consumers and a simultaneous abrogation of the economies of scale. The consequences of the impending atrophication of the nuclear industry in America and its effects on future energy mixes and long-term national interests must be considered in future nuclear policies and reforms

  14. 78 FR 47011 - Software Unit Testing for Digital Computer Software Used in Safety Systems of Nuclear Power Plants

    Science.gov (United States)

    2013-08-02

    ... NUCLEAR REGULATORY COMMISSION [NRC-2012-0195] Software Unit Testing for Digital Computer Software... revised regulatory guide (RG), revision 1 of RG 1.171, ``Software Unit Testing for Digital Computer Software Used in Safety Systems of Nuclear Power Plants.'' This RG endorses American National Standards...

  15. 77 FR 50722 - Software Unit Testing for Digital Computer Software Used in Safety Systems of Nuclear Power Plants

    Science.gov (United States)

    2012-08-22

    ... NUCLEAR REGULATORY COMMISSION [NRC-2012-0195] Software Unit Testing for Digital Computer Software...) is issuing for public comment draft regulatory guide (DG), DG-1208, ``Software Unit Testing for Digital Computer Software used in Safety Systems of Nuclear Power Plants.'' The DG-1208 is proposed...

  16. Moving into the 21st century - The United States' Research Reactor Spent Nuclear Fuel Acceptance Program

    International Nuclear Information System (INIS)

    Huizenga, David G.; Mustin, Tracy P.; Saris, Elizabeth C.; Reilly, Jill E.

    1999-01-01

    Since 1996, when the United States Department of Energy and the Department of State jointly adopted the Nuclear Weapons Nonproliferation Policy Concerning Foreign Research Reactor Spent Nuclear Fuel, twelve shipments totaling 2,985 MTR and TRIGA spent nuclear fuel assemblies from research reactors around the world have been accepted into the United States. These shipments have contained approximately 1.7 metric tons of HEU and 0.6 metric tons of LEU. Foreign research reactor operators played a significant role in this success. A new milestone in the acceptance program occurred during the summer of 1999 with the arrival of TRIGA spent nuclear fuel from Europe through the Charleston Naval Weapons Station via the Savannah River Site to the Idaho National Engineering and Environmental Laboratory. This shipment consisted of five casks of TRIGA spent nuclear fuel from research reactors in Germany, Italy, Slovenia, and Romania. These casks were transported by truck approximately 2,400 miles across the United States (one cask packaged in an ISO container per truck). Drawing upon lessons learned in previous shipments, significant technical, legal, and political challenges were addressed to complete this cross-country shipment. Other program activities since the last RERTR meeting have included: formulation of a methodology to determine the quantity of spent nuclear fuel in a damaged condition that may be transported in a particular cask (containment analysis for transportation casks); publication of clarification of the fee policy; and continued planning for the outyears of the acceptance policy including review of reactors and eligible material quantities. The United States Foreign Research Reactor Spent Nuclear Fuel Acceptance Program continues to demonstrate success due to the continuing commitment between the United States and the research reactor community to make this program work. We strongly encourage all eligible research reactors to decide as soon as possible to

  17. Overview on advanced nuclear reactors: research and deployment in the United States

    International Nuclear Information System (INIS)

    Sandell, L.; Rohrer, S.

    2004-01-01

    For the United States of America, the electricity requirement is expected to continue to rise at rates of approximately 1.8% over the next few years. This means that some 300,000 MW of additional generating capacity need to be made available by 2025. The Energy Policy Act of 2003 is to minimize this expected future growth of electricity consumption and promote research in favor of a diversified energy mix. As a consequence, the U.S. Senate and the House of Representatives passed legislation on electricity generation, on the promotion of, and research into, specific energy sources, and on energy conservation. Currently, coal-fired power plants contribute the largest share to the overall generating capacity. Considerable additions to the generating capacity have been made in the past ten years in gas-fired plants. In the light of the high present gas prices and market volatilities, the construction of new coal-fired power plants is currently under discussion. 103 out of the 436 nuclear power plants at present in operation worldwide are located in the United States. They represent by far the largest share of emission-free generating capacity in the United States. Considerable capacities have been added over the past few years by, up to now, 99 power increases by 0.4 to 17.8%. The Nuclear Power 2010 Program is a joint initiative by the government and industry seeking to further develop advanced nuclear power plant technologies and elaborate a new licensing procedure for nuclear power plants. The proposed licensing procedure and the Westinghouse AP1000, General Electric ESBWR, and AECL ACR-700 advanced reactor lines are presented. (orig.)

  18. Reactor control and protection of full scope simulator for Qinshan 300 MW Nuclear Power Unit

    International Nuclear Information System (INIS)

    Zhu Jinping; Sun Jiliang

    1996-01-01

    The control and protection simulation of Qinshan 300 MW Nuclear Power Unit, including the nuclear control, the pressurizer pressure control, the pressurizer level control, the rod control, the reactor shutdown protection and engineered safety feature etc are briefly introduced

  19. Human resource development for the new nuclear power plant unit in Armenia

    International Nuclear Information System (INIS)

    Gevorgyan, A.; Galstyan, A.; Donovan, M.

    2008-01-01

    This paper presents a discussion of a study to define the programs for development of the human resource infrastructure needed for a new nuclear power plant unit in the Republic of Armenia. While Armenia has a workforce experienced in operation and regulation of a nuclear power plant (NPP), a significant portion of the current Armenia Nuclear Power Plant (ANPP) workforce is approaching retirement age and will not be available for the new plant. The Government of Armenia is performing a human resource infrastructure study in cooperation with the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO), sponsored by the JAEA. The study of Human Resource Development for Armenia uses the INPRO methodology for assessment of human resources. The results of this study will provide the basis for decisions on human resource development programs for nuclear power in Armenia and provide a model for countries with the limited resources that are working to develop nuclear energy in the future. (authors)

  20. Integrated-plant-safety assessment Systematic Evaluation program. Millstone Nuclear Power Station, Unit 1, Northeast Nuclear Energy Company, Docket No. 50-245

    International Nuclear Information System (INIS)

    1982-11-01

    The Systematic Evaluation Program was initiated in February 1977 to review the designs of older operating nuclear reactor plants to reconfirm and document their safety. The review provides: (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of the Millstone Nuclear Power Station, Unit 1, operated by Northeast Nuclear Energy Company (located in Waterford, Connecticut). Millstone Nuclear Power Station, Unit 1, is one of ten plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review. It is expected that this report will be one of the bases in considering the issuance of a full-term operating license in place of the existing provisional operating license

  1. Emergency plans for civil nuclear installations in the United Kingdom

    International Nuclear Information System (INIS)

    Gronow, W.S.

    1984-01-01

    The operators of nuclear installations in the United Kingdom have plans to deal with accidents or emergencies at their nuclear sites. These plans provide for any necessary action, both on and off the nuclear site, to protect members of the public and are regularly exercised. The off-site actions involve the emergency services and other authorities which may be called upon to implement measures to protect the public in any civil emergency. In a recent review of these plans by Government Departments and agencies and the nuclear site operators, a number of possible improvements were identified. These improvements are concerned mainly with the provisions made for liaison with local and national authorities and for public information and have been incorporated into existing plans. An outline is given of the most likely consequences of an accidental release of radioactive material and the scope of emergency plans. Details are also provided on the responsibilities and functions of the operator and other organizations with duties under the plans and the arrangements made for public information. (author)

  2. Security central processing unit applications in the protection of nuclear facilities

    International Nuclear Information System (INIS)

    Goetzke, R.E.

    1987-01-01

    New or upgraded electronic security systems protecting nuclear facilities or complexes will be heavily computer dependent. Proper planning for new systems and the employment of new state-of-the-art 32 bit processors in the processing of subsystem reports are key elements in effective security systems. The processing of subsystem reports represents only a small segment of system overhead. In selecting a security system to meet the current and future needs for nuclear security applications the central processing unit (CPU) applied in the system architecture is the critical element in system performance. New 32 bit technology eliminates the need for program overlays while providing system programmers with well documented program tools to develop effective systems to operate in all phases of nuclear security applications

  3. Nuclear regulation in the United States : Policy directions and future prospects

    International Nuclear Information System (INIS)

    Shirley, Ann Jackson

    1996-01-01

    Just before leaving the United States to come to Korea, I addressed the U. S. Nuclear Regulatory Commission (NRC) annual regulatory information conference, with which some of you might be familiar. The overall theme this year focused on enhancing and promoting a better understanding of future trends for improving nuclear safety. Specific sessions addressed an array of nuclear safety topics including: dry cask storage of spent fuel; performance-based changes in the inspection program; core performance and reactor fuel issues; the revised decommissioning rule; utility restructuring and NRC licensing activities; steam generators; implementation of the maintenance rule; an update on license renewal; the shutdown rule; and spent fuel pool issues. The number and range of topics addressed tells US that the nuclear field is by no means static. On the contrary. there are numerous areas in which regulatory policy is evolving in response to technological, governmental, and other developments. while not all nations with nuclear programs face the same issues at the same time, there is enough overlap from one nation to another that it may be useful to describe the challenges facing the NRC today. the nuclear regulatory policy is moving. The challenges that we are dealing with at the NRC today may well be those which other nations will be confronting shortly? of they are not doing so already. In addressing the question of my vision for the NRC, I am sometimes asked whether it is possible to have a vision for the agency, given that no new nuclear plants are being built in the U. S. and none are on the immediate horizon. The answer, of course, is that the original licensing of nuclear power plants is only a part of the job of the NRC? an important part, to be sure, be but because safety must be built into nuclear plants from the beginning -- but nevertheless just one part. The task of the nuclear regulator is to ensure not only that plants are designed and constructed safely, but

  4. The outlook for nuclear energy in the United States dark ages, renaissance, or age of enlightenment?

    International Nuclear Information System (INIS)

    Brodman, J.

    2009-01-01

    According to the World Nuclear Association (WNA), today there are some 439 nuclear power reactors operating in 31 countries (including Taiwan), with a combined capacity of over 370 GWe. These reactors provided about 15% of the world's electricity in 2007. Nuclear energy was responsible for more than 25% of the total electricity supply in 16 countries. In kWh, the US, France, Russia and Korea were the largest producers of nuclear energy in 2008. As of August 2009, some 52 nuclear power units were under construction in 14 countries, and most of these were being built in China (16), Russia (9), India (6), and S. Korea (5). After being suspended in 1985, construction of the Tennessee Valley Authority's (TVA) Watts Bar Unit 2 resumed in 2008, making it the only nuclear unit under construction in the US at this time. In addition to those under construction, many more reactors (100 +) have been proposed and are in various stages of the pre-construction planning and licensing process. As of September 1, 2009, this includes 18 construction and operating license (COL) applications that have been filed with the Nuclear Regulatory Commission (NRC) for 28 new units in the US alone. Furthermore, according to the International Atomic Energy Agency (IAEA) and the WNA, approximately 30 additional countries are exploring the possibility of starting nuclear energy programs as an option for meeting their future electricity needs. In a global sense, this certainly looks like a 'renaissance' to a casual observer or to someone who is inclined to see it that way. However, most of the renaissance is occurring elsewhere, and the US and some other countries are still struggling to launch substantial new nuclear build programs. The renaissance is also a cause of concern to some. The growing number of reactors in a growing number of countries, many with relatively limited nuclear experience, also increases the risk of a safety-related accident or terrorist incident. While we have seen from the

  5. The United States nuclear insurance program: an update of recent developments and trends

    International Nuclear Information System (INIS)

    Cummings, L.G.

    1978-01-01

    There are numerous developments concerning nuclear insurance in the United States at present. The debate on the constitutionality of the Price-Anderson Act questions the principle of the limitation of the operators liability. The insurance market is undergoing changes with the reorganisation of the four main pools, NELIA (Nuclear Energy Liability Insurance Association), NEPIA (Nuclear Energy Property Insurance Association), MAELU (Mutual Atomic Energy Liability Underwriters), MAERP (Mutual Atomic Energy Reinsurance Pool). Insurance premiums for damage have been revised on several occasions following industrial demand and the development of the insurance market capacity. (NEA) [fr

  6. 75 FR 52045 - Arizona Public Service Company, Palo Verde Nuclear Generating Station, Unit 3; Environmental...

    Science.gov (United States)

    2010-08-24

    ... Company, Palo Verde Nuclear Generating Station, Unit 3; Environmental Assessment and Finding of No.... NPF-74, issued to Arizona Public Service Company (APS, the licensee), for operation of Palo Verde... Statement for the Palo Verde Nuclear Generating Station, NUREG-0841, dated February 1982. Agencies and...

  7. Reactor units for power supply to the Russian Arctic regions: Priority assessment of nuclear energy sources

    Directory of Open Access Journals (Sweden)

    Mel'nikov N. N.

    2017-03-01

    Full Text Available Under conditions of competitiveness of small nuclear power plants (SNPP and feasibility of their use to supply power to remote and inaccessible regions the competition occurs between nuclear energy sources, which is caused by a wide range of proposals for solving the problem of power supply to different consumers in the decentralized area of the Russian Arctic power complex. The paper suggests a methodological approach for expert assessment of the priority of small power reactor units based on the application of the point system. The priority types of the reactor units have been determined based on evaluation of the unit's conformity to the following criteria: the level of referentiality and readiness degree of reactor units to implementation; duration of the fuel cycle, which largely determines an autonomy level of the nuclear energy source; the possibility of creating a modular block structure of SNPP; the maximum weight of a transported single equipment for the reactor unit; service life of the main equipment. Within the proposed methodological approach the authors have performed a preliminary ranking of the reactor units according to various criteria, which allows quantitatively determining relative difference and priority of the small nuclear power plants projects aimed at energy supply to the Russian Arctic. To assess the sensitivity of the ranking results to the parameters of the point system the authors have observed the five-point and ten-point scales under variations of importance (weights of different criteria. The paper presents the results of preliminary ranking, which have allowed distinguishing the following types of the reactor units in order of their priority: ABV-6E (ABV-6M, "Uniterm" and SVBR-10 in the energy range up to 20 MW; RITM-200 (RITM-200M, KLT-40S and SVBR-100 in the energy range above 20 MW.

  8. 1988 changes to United States law regarding nuclear third party liability

    International Nuclear Information System (INIS)

    Cunningham, G.H.

    1989-09-01

    The Price-Anderson Amendments Act of 1988 has introduced sweeping changes into the nuclear third party liability regime in the United States. The basis principle that a single, assured source of funds for compensation of those injured by a nuclear incident, regardless of the party actually at fault, has been maintained. The amount of such funding has been increased tenfold, to more than $7 billion, with a commitment that even more will be made available by the Congress, if needed. The scope of compensable injury has been broadened to include precautionary evacuations. With respect to contractors carrying out the defense-related nuclear activities of the Government, the changes have been equally momentous. The ceiling on Government idemnification has risen to keep pace with the maximum amount of licensee liability. Provisions designed to provide greater incentive to adherence to all nuclear safety standards have been added, authorizing the imposition of substantial civil and criminal sanctions for violations

  9. Control system for a nuclear power producing unit

    International Nuclear Information System (INIS)

    Durrant, O.W.

    1978-01-01

    The invention provides in a control system for a nuclear power producing unit comprising a pressurized water reactor, a once-through steam generator provided with feedwater supply means, a turbine-generator supplied with steam from the steam generator and means maintaining a flow of pressurized water through the reactor and steam generator. The combination comprising; means generating a feed forward control signal proportional to the desired power output of the power producing unit, a second means for adjusting the reactor heat release, a third means for adjusting the rate of flow of feedwater to the steam generator, the second and third means solely responsive to and operated in parallel from the feed forward control signal whereby the reactor heat release and the rate of flow of feedwater to the steam generator are each maintained in a discrete functional relationship to the feed forward control signal

  10. Nuclear energy in the United States: prospects, designs and implications

    International Nuclear Information System (INIS)

    Olds, F.C.

    1981-01-01

    Only an American, an old observer of the American scene, could make an analysis in depth of so complex a subject. The author bases his arguments on statistics and documents available to the public but, his conclusions only reflect his own personal opinion on the energy future of the United States. He shows the difficulties that the development of the nuclear programme has come up against since 1977 and the predictable economic and political effects. A new policy slows down the technological transfer, brings back into question the 'peaceful atom' and makes the task all the easier for the antinuclear movement. The nuclear future and public opinion after the Three Mile Island accident is an ever burning issue [fr

  11. 78 FR 32278 - Vogtle Electric Generating Station, Units 3 and 4; Southern Nuclear Operating Company; Change to...

    Science.gov (United States)

    2013-05-29

    ... Generating Station, Units 3 and 4; Southern Nuclear Operating Company; Change to Information in Tier 1, Table... Nuclear Operating Company, Inc., and Georgia Power Company, Oglethorpe Power Corporation, Municipal... Table 3.3-1, ``Definition of Wall Thicknesses for Nuclear Island Buildings, Turbine Buildings, and Annex...

  12. Status of spent nuclear fuel management in the United States of America

    International Nuclear Information System (INIS)

    Williams, J.R.

    1998-01-01

    The United States produces approximately 20% of its electricity in nuclear power reactors, currently generating, approximately 2,000 metric tons of uranium (tU) of spent nuclear fuel annually. Over the past half century, the country has amassed 33,000 tU of commercial spent nuclear fuel that is being stored at 119 operating and shutdown reactors located on 73 sites around the nation. The cumulative discharge of the spent fuel from reactors is estimated to total approximately 87,000 tU by 2035. Many sites have reracked the spent fuel in their storage pool to maximize pool capacity, and a number of reactor sites have been forced to add dry storage to accommodate the growing inventory of fuel in storage. In addition, research and defense programme reactors have produced spent fuel that is being stored in pools at Federal sites. Much of this fuel will be transferred to dry storage in the coming years. Under current plans, the commercial and federally owned fuel will remain in storage at the existing sites until the United States Department of Energy (DOE) begins receipt at a federal receiving facility. (author)

  13. Decommissioning of units 1 - 4 at Kozloduy nuclear power plant in Bulgaria

    International Nuclear Information System (INIS)

    Dishkova, Denitsa

    2014-01-01

    Nuclear safety and security are absolute priorities for the European Union countries and this applies not only to nuclear power plants in operation but also to decommissioning. In terms of my technical background and my working experience in the field of licensing and environmental impact assessment during the decommissioning of Units 1 to 4 at Kozloduy Nuclear Power Plant (KNPP) in Bulgaria, I decided to present the strategy for decommissioning of Units 1 to 4 at KNPP which was selected and followed to achieve safe and effective decommissioning process. The selected strategy in each case must meet the legislative framework, to ensure safe management of spent fuel and radioactive waste, to provide adequate funding and to lead to positive socio-economic impact. The activities during the decommissioning generate large volume of waste. In order to minimize their costs and environmental impact it should be given a serious consideration to the choice, the development and the implementation of the most adequate process for treatment and the most appropriate measurement techniques. The licensing process of the decommissioning activities is extremely important and need to cope with all safety concerns and ensure optimal waste management. (authors)

  14. Apparatus for controlling a nuclear reactor by vertical displacement of a unit absorbing neutrons

    International Nuclear Information System (INIS)

    Wiart, A.; Defaucheux, J.; Martin, J.; Pasqualini, G.

    1980-01-01

    Apparatus is described for controlling a nuclear reactor by vertical displacement of a unit absorbing neutrons, comprising, inside a sealed enclosure in communication with the interior of the reactor, a movable magnetic piece connected to a control shaft which is itself connected to the absorbent unit. This magnetic piece has at least two radial projections. The magnetic piece is displaced by an inductor with at least two pole shoes corresponding to the projections on the magnetic piece and allowing magnetic coupling between the inductor and the magnetic piece. The inductor and its displacement device are disposed outside the sealed enclosure. A control means allows the control shaft to be uncoupled from a member assuring its suspension so as to drop the absorbent unit in the event of emergency shutdown. The apparatus is particularly applicable to control rods of pressurized water nuclear reactors

  15. How the United Kingdom seeks to enhance nuclear security with the help of IPPAS

    International Nuclear Information System (INIS)

    Fawaz-Huber, May

    2016-01-01

    In October 2011, an IAEA team of international nuclear security experts conducted an International Physical Protection Service mission (IPPAS) to the United Kingdom. They visited the Sellafield civil nuclear site, as well as Barrow Port, which is used for the transport of nuclear material. The IAEA conducted a follow-up mission in February 2016. IPPAS missions provide advice on how to improve the effectiveness of a State’s physical protection regime, either nationally or at facility level. They do so by comparing it with relevant international legal instruments, guidelines and best practices, particularly the 2005 Amendment to the Convention on the Physical Protection of Nuclear Material and the IAEA Nuclear Security Series guidance publications.

  16. Integrated Plant Safety Assessment: Systematic Evaluation Program. Millstone Nuclear Power Station, Unit 1, Northeast Nuclear Energy Company, Docket No. 50-245. Final report

    International Nuclear Information System (INIS)

    1983-02-01

    This report documents the review of the Millstone Nuclear Power Station, Unit 1, operated by Northeast Nuclear Energy Company (located in Waterford, Connecticut). Millstone Nuclear Power Station, Unit 1, is one of ten plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review. It is expected that this report will be one of the bases in considering the issuance of a full-term operating license in place of the existing provisional operating license. This report also addresses the comments and recommendations made by the Advisory Committee on Reactor Safeguards in connection with its review of the Draft Report, issued in November 1982

  17. 76 FR 78805 - Regulatory Changes To Implement the United States/Australian Agreement for Peaceful Nuclear...

    Science.gov (United States)

    2011-12-20

    ... Implement the United States/Australian Agreement for Peaceful Nuclear Cooperation; Corrections AGENCY... the Government of Australia and the Government of the United States of America Concerning Peaceful... action is unnecessary. List of Subjects in 10 CFR Part 40 Criminal penalties, Government contracts...

  18. Diffusion of nuclear power generation in the United States

    International Nuclear Information System (INIS)

    Sommers, P.E.

    1978-01-01

    This dissertation is a study of nuclear power as an innovation diffusing through the utility industry in the United States. Chapter 1 notes that the industry studied, the innovation and the diffusion process have several characteristics not typical of the classical diffusion of innovations literature in economics. Uncertainty about the true characteristics of the innovation persists well into the diffusion process. The characteristics of the innovation appear to change over time. Thus the classic S-shaped transition path from the old, pre-innovation equilibrium to a new post-diffusion equilibrium is not found for this innovation and this industry. A generalized diffusion model is developed in Chapter 1 which allows these peculiarities of the utility industry and of nuclear power to be taken into account. Chapter 2 traces the development of the innovation, the consequences of the demonstration plant program, and the history of the diffusion process from 1963 to the present. Chapter 3 analyses the structure and sources and consequences of regulation of the industry. Chapter 4 develops a logit discrete choice model of the adoption decision. Chapter 5 investigates the determinants of the proportion of industry output provided by nuclear plants using a modified version of the Baughman--Joskow Regional Electricity Model. Salient aspects of uncertainty shift the expected average cost of nuclear plant output in the modified model

  19. Overview of the United States' nuclear waste repository programme

    International Nuclear Information System (INIS)

    Surles, T.G.

    2002-01-01

    Regardless of the future of civilian or defense-based nuclear materials, the United States will be responsible for a vast array of these materials for generations to come. The cornerstone programme for the disposal of waste materials is the Yucca Mountain Programme. Based on the Nuclear Waste Policy Act of 1982, as amended in 1987, it has been the United States' policy to develop a geological repository for the permanent disposal of radioactive waste materials. This presentation will discuss the process and strategy leading to the present and will include the scientific and management activities required to support the recent Viability Assessment. Also to be discussed are the timeline and milestones leading to the opening of the repository. The focus will be on the scientific and engineering studies required for a successful Site Recommendation, and then for a similarly successful License Application. Both of these activities will require considerable management efforts in addressing legal and regulatory issues. Finally, the presentation will discuss projections for the future operation of the facility, including emplacement projections, coupled with the required locations of nuclear materials. Additional scientific research and engineering studies will also be conducted to determine the longer-term viability of the facility, which is designed, by policy, for permanent storage. Retrievability is currently not an option, although access to the facility will be maintained for several decades. The focus of the discussion will be on the scientific and engineering advances made on understanding the natural systems for preventing migration of radionuclides, coupled with new developments in engineered systems in areas such as cask cladding, drip shields, and related materials engineering developments. The coupling of engineered and natural systems is designed to offer safety factors that are several orders of magnitude greater than what is estimated to be necessary

  20. 75 FR 8149 - Arizona Public Service Company, et al. Palo Verde Nuclear Generating Station, Units 1, 2, and 3...

    Science.gov (United States)

    2010-02-23

    ...] Arizona Public Service Company, et al. Palo Verde Nuclear Generating Station, Units 1, 2, and 3... NPF-74, issued to the Arizona Public Service Company (APS, or the licensee), for operation of the Palo Verde Nuclear Generating Station (PVNGS, the facility), Units 1, 2, and 3, respectively, located in...

  1. CINDU catalogue of numerical neutron data available from the IAEA Nuclear Data Unit

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1968-05-15

    This catalogue is the index to DASTAR, the DAta STorage And Retrieval System of the IAEA Nuclear Data Unit. It is written in a slightly modified CINDA format and should be read with the help of the introduction to CINDA, Tables of abbreviations for references and laboratories mentioned in this issue are given on the verso of the front cover. The catalogue serves as a reference to all the experimental and calculated numerical data which have been entered into DASTAR, and each set of data i s indexed with a DASTAR-number, e.g. DASTAR-00434. The bibliographic references for each experiment are blocked together with the relevant DASTAR-number entry. All of the indexed data are available to anyone on request. Data should be ordered by their DASTAR-number. This issue of CINDU is distributed to data centres, members of the International Nuclear Data Committee, correspondents to the IAEA Nuclear Data Unit, and others who have expressed their interest. Entries which have been added or changed since the issue of CINDU-6 are marked with an asterisk following the entry date.

  2. Spring unit especially intended for a nuclear reactor core

    International Nuclear Information System (INIS)

    Brown, S.J.; Gorholt, Wilhelm.

    1977-01-01

    This invention relates to a spring unit or a group of springs bearing up a sprung mass against an unsprung mass. For instance, a gas cooled high temperature nuclear reactor includes a core of relatively complex structure supported inside a casing or vessel forming a shielded cavity enclosing the reactor core. This core can be assembled from a large number of graphite blocks of different sizes and shapes joined together to form a column. The blocks of each column can be fixed together so as to form together a loose side support. Under the effect of thermal expansion and contraction, shrinkage resulting from irradiation, the effects of pressure and the contraction and creep of the reactor vessel, it is not possible to confine all the columns of the reactor core in a cylindrical rigid structure. Further, the working of the nuclear reactor requires that the reactivity monitoring components may be inserted at any time in the reactor core. A standard process consists in mounting this loosely assembled reactor core in a floating manner by keeping it away from the vessel enclosure around it by means of a number of springs fitted between the lateral surfaces of the core unit and the reactor vessel. The core may be considered as a spring supported mass whereas, relatively, the reactor vessel is a mass that is not flexibly supported [fr

  3. Summary data for U.S. commercial nuclear power plants in the United States

    International Nuclear Information System (INIS)

    Heddleson, F.A.

    1978-01-01

    A compilation of data is presented for all United States commercial nuclear power plants for which a construction permit application was made through the Nuclear Regulatory Commission. The data are compiled in four separate tables with cross-referencing indexes: Table 1--General Data; Table 2--Reactor Data; Table 3--Site Data, and Table 4--Circulating-Water System Data. The power plants are listed in numerical order by docket number in all four tables

  4. 75 FR 18572 - Supplemental Environmental Impact Statement for Sequoyah Nuclear Plant Units 1 and 2 License...

    Science.gov (United States)

    2010-04-12

    ... TENNESSEE VALLEY AUTHORITY Supplemental Environmental Impact Statement for Sequoyah Nuclear Plant... National Environmental Policy Act. TVA will prepare a supplemental environmental impact statement (SEIS) to update information in the 1974 Final Environmental Statement for Sequoyah Nuclear Plant Units 1 and 2...

  5. Final Report of the 2nd Ex-Vessel Neutron Dosimetry Installation And Evaluations for Yonggwang Unit 1 Reactor Pressure Vessel

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Byoung Chul; Yoo, Choon Sung; Lee, Sam Lai; Gong, Un Sik; Choi, Kwon Jae; Chung, Kyoung Ki; Kim, Kwan Hyun; Chang, Jong Hwa; Ha, Jea Ju

    2008-01-15

    This report describes a neutron fluence assessment performed for the Kori Unit 2 pressure vessel belt line region based on the guidance specified in Regulatory Guide 1.190. In this assessment, maximum fast neutron exposures expressed in terms of fast neutron fluence (E>1 MeV) and iron atom displacements (dpa) were established for the belt line region of the pressure vessel. During Cycle 21 of reactor operation, an Ex-Vessel Neutron Dosimetry Program was instituted at Kori Unit 2 to provide continuous monitoring of the belt line region of the reactor vessel. The use of the Ex-Vessel Neutron Dosimetry Program coupled with available surveillance capsule measurements provides a plant specific data base that enables the evaluation of the vessel exposure and the uncertainty associated with that exposure over the service life of the unit. Ex-Vessel Neutron Dosimetry has been evaluated at the conclusion of Cycle 21.

  6. Nuclear energy and education in the United Kingdom

    International Nuclear Information System (INIS)

    Ginniff, M.E.

    1994-01-01

    The thesis of this paper is that sources of energy for a country must be dependable and their use from the production of the basic fuel to the disposal of the wastes should be up to standards which people can understand and accept. In the United Kingdom, the educational system is the source of basic information on sources of energy that are available and which sources are currently being developed to supply present and future energy needs. THe author provides a synopsis of educational techniques and materials which are used to educate the public about nuclear energy production

  7. Liability for injury to the unborn - Recent amendments to the United Kingdom Nuclear Installations Act

    International Nuclear Information System (INIS)

    Coleman, J.E.

    1977-01-01

    The adoption in the United Kingdom in 1976 of an Act to determine liability for injury to the unborn (foetus) has provided the opportunity to amend the Nuclear Installations Act which governs the liability of nuclear operators, which is now extended to such injury. Any 'injury' attributable to a nuclear operator which so affects a mother that her child is born disabled involves the liability of that operator within the meaning of the Nuclear Installations Act whether or not either parent has suffered an injury on that occasion. (NEA) [fr

  8. 78 FR 77508 - Duke Energy Carolinas, LLC; William States Lee III Nuclear Station, Units 1 and 2; Combined...

    Science.gov (United States)

    2013-12-23

    ... NUCLEAR REGULATORY COMMISSION [Docket Nos. 52-018 and 52-019; NRC-2008-0170] Duke Energy Carolinas, LLC; William States Lee III Nuclear Station, Units 1 and 2; Combined Licenses Application Review AGENCY: Nuclear Regulatory Commission. ACTION: Final environmental impact statement; availability...

  9. Nuclear thermal source transfer unit, post-blast soil sample drying system

    Energy Technology Data Exchange (ETDEWEB)

    Wiser, Ralph S. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Valencia, Matthew J [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-01-03

    Los Alamos National Laboratory states that its mission is “To solve national security challenges through scientific excellence.” The Science Undergraduate Laboratory Internship (SULI) programs exists to engage undergraduate students in STEM work by providing opportunity to work at DOE facilities. As an undergraduate mechanical engineering intern under the SULI program at Los Alamos during the fall semester of 2016, I had the opportunity to contribute to the mission of the Laboratory while developing skills in a STEM discipline. I worked with Technology Applications, an engineering group that supports non-proliferation, counter terrorism, and emergency response missions. This group specializes in tool design, weapons engineering, rapid prototyping, and mission training. I assisted with two major projects during my appointment Los Alamos. The first was a thermal source transportation unit, intended to safely contain a nuclear thermal source during transit. The second was a soil drying unit for use in nuclear postblast field sample collection. These projects have given me invaluable experience working alongside a team of professional engineers. Skills developed include modeling, simulation, group design, product and system design, and product testing.

  10. Nuclear thermal source transfer unit, post-blast soil sample drying system

    International Nuclear Information System (INIS)

    Wiser, Ralph S.; Valencia, Matthew J

    2017-01-01

    Los Alamos National Laboratory states that its mission is ''To solve national security challenges through scientific excellence.'' The Science Undergraduate Laboratory Internship (SULI) programs exists to engage undergraduate students in STEM work by providing opportunity to work at DOE facilities. As an undergraduate mechanical engineering intern under the SULI program at Los Alamos during the fall semester of 2016, I had the opportunity to contribute to the mission of the Laboratory while developing skills in a STEM discipline. I worked with Technology Applications, an engineering group that supports non-proliferation, counter terrorism, and emergency response missions. This group specializes in tool design, weapons engineering, rapid prototyping, and mission training. I assisted with two major projects during my appointment Los Alamos. The first was a thermal source transportation unit, intended to safely contain a nuclear thermal source during transit. The second was a soil drying unit for use in nuclear postblast field sample collection. These projects have given me invaluable experience working alongside a team of professional engineers. Skills developed include modeling, simulation, group design, product and system design, and product testing.

  11. The regulatory process, nuclear safety research and the fuel cycle in the United Kingdom

    International Nuclear Information System (INIS)

    Watson, P.

    1996-01-01

    The main legislation governing the safety of nuclear installations in the United Kingdom is the Health and Safety at Work Act 1974 (HSWA) and the associated relevant statutory provisions of the Nuclear Installations Act 1965 (as amended). The HSWA sought to simplify and unify all industrial safety legislation and set in place the Health and Safety Commission (HSC) and its executive arm, the Health and Safety Executive (HSE). The Health and Safety Executive's Nuclear Safety Division (NSD) regulates the nuclear activities on such sites through HM Nuclear Installations Inspectorate (NII). Under the Nuclear Installations Act (NIA) no corporate body may use any site for the purpose of installing or operating any reactor, other than such a reactor comprised in a means of transport, or other prescribed installation unless the operator has been granted a nuclear site licence by the Health and Safety Executive. Nuclear fuel cycle facilities are examples of such prescribed installations. (J.P.N.)

  12. Science, Society, and America's Nuclear Waste: Ionizing Radiation, Unit 2. Teacher Guide. Second Edition.

    Science.gov (United States)

    Department of Energy, Washington, DC. Office of Civilian Radioactive Waste Management, Washington, DC.

    This guide is Unit 2 of the four-part series, Science, Society, and America's Nuclear Waste, produced by the U.S. Department of Energy's Office of Civilian Radioactive Waste Management. The goal of this unit is to convey factual information relevant to radioactivity and radiation and relate that information both to the personal lives of students…

  13. Safety review on unit testing of safety system software of nuclear power plant

    International Nuclear Information System (INIS)

    Liu Le; Zhang Qi

    2013-01-01

    Software unit testing has an important place in the testing of safety system software of nuclear power plants, and in the wider scope of the verification and validation. It is a comprehensive, systematic process, and its documentation shall meet the related requirements. When reviewing software unit testing, attention should be paid to the coverage of software safety requirements, the coverage of software internal structure, and the independence of the work. (authors)

  14. Safety Evaluation Report related to the operation of Nine Mile Point Nuclear Station, Unit No. 2 (Docket No. 50-410)

    International Nuclear Information System (INIS)

    1987-07-01

    This report supplements the Safety Evaluation Report (NUREG-1047, February 1985) for the application filed by Niagara Mohawk Power Corporation, as applicant and co-owner, for the license to operate Nine Mile Point Nuclear Station, Unit 2 (Docket No. 50-410). It has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located near Oswego, New York. This report supports the issuance of the full-power license for Nine Mile Point Nuclear Station, Unit No. 2

  15. The experience in the Cernavoda Unit 1 operation - a stimulating argument for future nuclear power development in Romania

    International Nuclear Information System (INIS)

    Rotaru, I.; Bucur, I.; Galeriu, A.C.; Budan, O.

    1999-01-01

    The Romanian nuclear program has been developed based on the option for CANDU type reactors. At the beginning, this program was unrealistically conceived and its management was inappropriate. The program was reconsidered in 1990 and the management policy and organization structure were also adapted accordingly. The paper presents, in the first part, the actual organization structure, adapted for the execution of the current and future activities, related to the nuclear power program. The performance achieved by Cernavoda Unit 1 constitutes the main part of the paper. The performances described demonstrate that the Cernavoda Unit 1 is a success and the Romania's electricity needs are satisfied in a proportion of about 12% by the nuclear power. The paper also presents a general view on Cernavoda Unit 2 perspectives. The essential conclusion of the paper is that the continuation of the nuclear program appears to be a logical option, generally accepted in Romania, limited only by financial restraints. (author)

  16. Historical overview of domestic spent nuclear fuel shipments in the United States

    International Nuclear Information System (INIS)

    Pope, R.B.; Wankerl, M.W.; Hamberger, C.R.; Schmid, S.P.

    1993-01-01

    The information in this paper summarized historical data on spent nuclear fuel shipments in the United States (U.S.) from the period from 1964 to 1991. Information on shipments has been developed to establish a basis for developing a transportation system in the U.S. for initiating shipments of spent nuclear fuel beginning in 1988. The paper shows that approximately 2700 power spent nuclear fuel rail and truck casks have been shipped within the U.S. during the past 28 years. In total, approximately 2000 metric tonnes of uranium (MTU) have been shipped to date, which compares with projected shipping rates of from 3000 to greater than 6000 MTU per year when the U.S. Civilian Radiation Waste Management System is in full operation. (author)

  17. Historical overview of domestic spent nuclear fuel shipments in the United States

    International Nuclear Information System (INIS)

    Pope, R.B.; Wankerl, M.W.; Hamberger, C.R.; Schmid, S.P.

    1992-01-01

    The information in this paper summarizes historical data on spent nuclear fuel shipments in the United States (US) from the period from 1964 to 1991. Information on shipments has been developed to establish a basis for developing a transportation system in the US for initiating shipments of spent nuclear fuel beginning in 1998. The paper shows that approximately 2700 power reactor spent nuclear fuel rail and truck casks have been shipped within the US during the past 28 years. In total, approximately 2000 metric tonnes of uranium (MTU) have been shipped to date, which compares with projected shipping rates of from 3000 to greater than 6000 MM per year when the US Civilian Radioactive Waste Management System is in full operation

  18. Optimal replacement and inspection periods of safety and control boards in Wolsung nuclear power plant unit 1

    International Nuclear Information System (INIS)

    Mok, Jin Il

    1993-02-01

    In nuclear power plants, the safety and control systems are important for operating and maintaining safety of nuclear power plants. Due to the failure of the instrument and control devices of nuclear power plants caused by aging, nuclear power plants occasionally trip. Since the start of first commercial operation of Kori nuclear power plant (NPP) unit 1, the trips caused by instrument and control systems account for 28% of total trips of NPPs in Korea. Even a single trip of a nuclear power plant causes an extravagant economical loss and deteriorates public acceptance of nuclear power plants. Therefore, the replacement of the instrument and control devices with proper consideration of the aging effect is necessary in order to prevent the inadvertent trip. In this work we investigated the optimal replacement periods of the digital control computer's (DCC) and the programmable digital comparator's (PDC) electronic circuit boards of Wolsung nuclear power plant Unit 1. We first derived mathematical models which calculate optimal replacement periods for electronic circuit boards of digital control computer (DCC) and for those of the programmable digital comparator (PDC) in Wolsung NPP unit 1. And we analytically obtained the optimal replacement periods of electronic circuit boards by using these models. We compared these periods with the replacement periods currently used at Wolsung NPP Unit. The periods used at Wolsung is not based on mathematical analysis, but on empirical knowledge. As a consequence, the optimal replacement periods analytically obtained for the electronic circuit boards of DCC and those used in the field shown small difference : the optimal replacement periods analytically obtained for the electronic circuit boards of PDC are shorter than those used in the field in general. The engineered safeguards of Wolsung nuclear power plant unit 1 contains redundant systems of 2-out-of-3 logic which are not operating under normal conditions but they are called

  19. Nuclear design report for Ulchin nuclear power plant unit 1, cycle 7

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Yong Rae; Park, Yong soo [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-04-01

    This report presents nuclear design calculations for Cycle 7 of Ulchin Unit 1. Information is given on fuel loading, power density distributions, reactivity coefficients, control rod worths and operational limits. In addition, the report contains all necessary data for the startup tests including predicted values for the comparison with the measured data. The reload consists of 56 KOFA`s enriched by nominally 4.00 w/o U{sub 235}. Among the KOFA`s 36 fuel assemblies contain gadolinia rods. The fuel assemblies in the core are arranged in a low leakage loading pattern. The cycle length of Cycle 7 amounts to 355 EFPD corresponding to a cycle burnup of 14280 MWD/MTU. (Author) 8 refs., 55 figs., 21 tabs.

  20. Nuclear design report for Kori nuclear power plant unit 4 cycle 8

    Energy Technology Data Exchange (ETDEWEB)

    Zee, Sung Kyoon; Jung, Yil Sub; Kim, Si Yung [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1993-07-01

    This report presents nuclear design calculations for cycle 8 of Kori unit 4. Information is given on fuel loading, power density distributions, reactivity coefficients, control rod worths and operational limits. In addition, the report contains all necessary data for the startup tests including predicted values for the comparison with the measured data. The reload consists of 76 KOFA`s enriched by nominally 3.70 w/o U{sub 235}. Among the KOFA`s 48 fuel assemblies contain gadolinia rods. The fuel assemblies in the core are arranged in a low leakage loading pattern. The cycle length of cycle 8 amounts to 421 EFPD corresponding to a cycle burnup of 16950 MWD/MTU. (Author) 8 refs., 55 figs., 17 tabs.

  1. Nuclear design report for Kori nuclear power plant unit 1, cycle 13

    Energy Technology Data Exchange (ETDEWEB)

    Zee, Sung Kyun; Moon, Bok Ja; Cho, Byeong Ho; Jung, Yil Sup [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1993-04-01

    This report presents nuclear design calculations for cycle 13 of Kori unit 1. Information is given on fuel loading, power density distributions, reactivity coefficients, control rod worths and operational limits. In addition, the report contains all necessary data for the startup tests including predicted values for the comparison with the measured data. The reload consists of 44 KOFA`s enriched by nominally 3.70 w/o U{sub 235}. Among the KOFA`s, 16 fuel assemblies contain gadolinia rods. The fuel assemblies in the core are arranged in a low leakage loading pattern. The cycle length of cycle 13 amounts to 355 EFPD corresponding to a cycle burnup of 13240 MWD/MTU. (Author) 8 refs., 55 figs., 16 tabs.

  2. Nuclear design report for Ulchin nuclear power plant unit 1, cycle 6

    Energy Technology Data Exchange (ETDEWEB)

    Zee, Sung Kyun; Kim, Yong Rae; Park, Yong Soo; Cho, Byeong Ho; Lee, Sang Keun; Ahn, Dawk Hwan [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1993-12-01

    This report presents nuclear design calculations for cycle 6 of Ulchin unit 1. Information is given on fuel loading, power density distributions, reactivity coefficients, control rod worths and operational limits. In addition, the report contains all necessary data for the startup tests including predicted values for the comparison with the measured data. The reload consists of 64 KOFA`s enriched by nominally 3.70 w/o U{sub 235}. Among the KOFA`s, 32 fuel assemblies contain gadolinia rods. The fuel assemblies in the core are arranged in a low leakage loading pattern. The cycle length of cycle 6 amounts to 369 EFPD corresponding to a cycle burnup of 14850 MWD/MTU. (Author) 8 refs., 55 figs., 17 tabs.

  3. Nuclear design report for Ulchin nuclear power plant unit 2, cycle 6

    Energy Technology Data Exchange (ETDEWEB)

    Park, Chan Oh; Park, Jin Ha; Kim, Yong Rae; Park, Sang Yoon; Lee, Jong Chul; Baik, Joo Hyun [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1994-08-01

    This report presents nuclear design calculations for cycle 6 of Ulchin unit 2. Information is given on fuel loading, power density distributions, reactivity coefficients, control rod worths and operational limits. In addition, the report contains all necessary data for the startup tests including predicted values for the comparison with the measured data. The reload consists of 64 KOFA`s enriched by nominally 3.80 w/o U{sub 235}. Among the KOFA`s, 36 fuel assemblies contain gadolinia rods. The fuel assemblies in the core are arranged in a low leakage loading pattern. The cycle length of cycle 6 amounts to 388 EFPD corresponding to a cycle burnup of 15610 MWD/MTU. (Author) 8 refs., 55 figs., 17 tabs.

  4. Nuclear design report for Ulchin nuclear power plant unit 2 cycle 5

    International Nuclear Information System (INIS)

    Park, Jin Ha; Park, Yong Soo; Cho, Byeong Ho; Zee, Sung Kyun; Lee, Sang Keun; Ahn, Dawk Hwan

    1993-09-01

    This report presents nuclear design calculations for cycle 5 of Ulchin unit it 2. Information is given on fuel loading, power density distributions, reactivity coefficients, control rod worths and operational limits. In addition, the report contains all necessary data for the startup tests including predicted values for the comparison with the measured data. The reload consists of 48 KOFA's enriched by nominally 3.50 w/o U 235 . Among the KOFA's, 20 fuel assemblies contain gadolinia rods. The fuel assemblies in the core are arranged in a low leakage loading pattern. The cycle length of cycle 5 amounts to 293 EFPD corresponding to a cycle burnup of 11780 MWD/MTU. (Author) 8 refs., 55 figs., 16 tabs

  5. Development of the operational information processing platform

    International Nuclear Information System (INIS)

    Shin, Hyun Kook; Park, Jeong Seok; Baek, Seung Min; Kim, Young Jin; Joo, Jae Yoon; Lee, Sang Mok; Jeong, Young Woo; Seo, Ho Jun; Kim, Do Youn; Lee, Tae Hoon

    1996-02-01

    The Operational Information Processing Platform(OIPP) is platform system which was designed to provide the development and operation environments for plant operation and plant monitoring. It is based on the Plant Computer Systems (PCS) of Yonggwang 3 and 4, Ulchin 3 and 4, and Yonggwang 5 and 6 Nuclear Power Plants (NPP). The UNIX based workstation, real time kernel and graphics design tool are selected and installed through the reviewing the function of PCS. In order to construct the development environment for open system architecture and distributed computer system, open computer system architecture was adapted both in hardware and software. For verification of system design and evaluation of technical methodologies, the PCS running under the OIPP is being designed and implemented. In this system, the man-machine interface and system functions are being designed and implemented to evaluate the differences between the UCN 3, 4 PCS and OIPP. 15 tabs., 32 figs., 11 refs. (Author)

  6. 75 FR 16201 - FPL Energy Point Beach, LLC; Point Beach Nuclear Plant, Units 1 and 2; Exemption

    Science.gov (United States)

    2010-03-31

    ... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-266 and 50-301; NRC-2010-0123] FPL Energy Point Beach, LLC; Point Beach Nuclear Plant, Units 1 and 2; Exemption 1.0 Background FPL Energy Point Beach.... Borchardt (NRC) to M. S. Fertel (Nuclear Energy Institute) dated June 4, 2009. The licensee's request for an...

  7. ATWS analysis for Browns Ferry Nuclear Plant Unit 1

    International Nuclear Information System (INIS)

    Dallman, R.J.; Jouse, W.C.

    1985-01-01

    Analyses of postulated Anticipated Transients Without Scram (ATWS) were performed at the Idaho National Engineering Laboratory (INEL). The Browns Ferry Nuclear Plant Unit 1 (BFNP1) was selected as the subject of this work because of the cooperation of the Tennessee Valley Authority (TVA). The work is part of the Severe Accident Sequence Analysis (SASA) Program of the US Nuclear Regulatory Commission (NRC). A Main Steamline Isolation Valve (MSIV) closure served as the transient initiator for these analyses, which proceeded a complete failure to scram. Results from the analyses indicate that operator mitigative actions are required to prevent overpressurization of the primary containment. Uncertainties remain concerning the effectiveness of key mitigative actions. The effectiveness of level control as a power reduction procedure is limited. Power level resulting from level control only reduce the Pressure Suppression Pool (PSP) heatup rate from 6 to 4 0 F/min

  8. Nuclear fuel cycle cost estimation and sensitivity analysis of unit costs on the basis of an equilibrium model

    International Nuclear Information System (INIS)

    Kim, S. K.; Ko, W. I.; You, S. R.; Gao, R. X.

    2015-01-01

    This paper examines the difference in the value of the nuclear fuel cycle cost calculated by the deterministic and probabilistic methods on the basis of an equilibrium model. Calculating using the deterministic method, the direct disposal cost and Pyro-SFR (sodium-cooled fast reactor) nuclear fuel cycle cost, including the reactor cost, were found to be 66.41 mills/kWh and 77.82 mills/kWh, respectively (1 mill = one thousand of a dollar, i.e., 10-3 $). This is because the cost of SFR is considerably expensive. Calculating again using the probabilistic method, however, the direct disposal cost and Pyro-SFR nuclear fuel cycle cost, excluding the reactor cost, were found be 7.47 mills/kWh and 6.40 mills/kWh, respectively, on the basis of the most likely value. This is because the nuclear fuel cycle cost is significantly affected by the standard deviation and the mean of the unit cost that includes uncertainty. Thus, it is judged that not only the deterministic method, but also the probabilistic method, would also be necessary to evaluate the nuclear fuel cycle cost. By analyzing the sensitivity of the unit cost in each phase of the nuclear fuel cycle, it was found that the uranium unit price is the most influential factor in determining nuclear fuel cycle costs.

  9. Interim reliability evaluation program: analysis of the Arkansas Nuclear One. Unit 1 Nuclear Power Plant

    International Nuclear Information System (INIS)

    Kolb, G.J.; Kunsman, D.M.; Bell, B.J.

    1982-06-01

    This report represents the results of the analysis of Arkansas Nuclear One (ANO) Unit 1 nuclear power plant which was performed as part of the Interim Reliability Evaluation Program (IREP). The IREP has several objectives, two of which are achieved by the analysis presented in this report. These objectives are: (1) the identification, in a preliminary way, of those accident sequences which are expected to dominate the public health and safety risks; and (2) the development of state-of-the-art plant system models which can be used as a foundation for subsequent, more intensive applications of probabilistic risk assessment. The primary methodological tools used in the analysis were event trees and fault trees. These tools were used to study core melt accidents initiated by loss of coolant accidents (LOCAs) of six different break size ranges and eight different types of transients

  10. Nuclear reactors built, being built, or planned in the United States

    International Nuclear Information System (INIS)

    1984-08-01

    This booklet contains unclassified information about facilities built, being built, or planned in the United States for domestic use or export as of Apr. 30, 1984, which are capable of sustaining a nuclear chain reaction. Information is presented in five parts, each of which is categorized by primary function or purpose: civilian, military, production, export, and critical assembly facilities

  11. Nuclear reactors built, being built, or planned in the United States

    International Nuclear Information System (INIS)

    Carter, E.P.

    1985-09-01

    This publication contains unclassified information about facilities built, being built, or planned in the United States for domestic use or export as of March 1985, which are capable of sustaining a nuclear chain reaction. Information is presented in five parts, each of which is categorized by primary function or purpose: civilian, production, military, export, and critical assembly facilities

  12. A continuing success - The United States Foreign Research Reactor Spent Nuclear Fuel Acceptance Program

    International Nuclear Information System (INIS)

    Mustin, Tracy P.; Clapper, Maureen; Reilly, Jill E.

    2000-01-01

    The United States Department of Energy, in consultation with the Department of State, adopted the Nuclear Weapons Nonproliferation Policy Concerning Foreign Research Reactor Spent Nuclear Fuel in May 1996. To date, the Foreign Research Reactor (FRR) Spent Nuclear Fuel (SNF) Acceptance Program, established under this policy, has completed 16 spent fuel shipments. 2,651 material test reactor (MTR) assemblies, one Slowpoke core containing less than 1 kilogram of U.S.-origin enriched uranium, 824 Training, Research, Isotope, General Atomic (TRIGA) rods, and 267 TRIGA pins from research reactors around the world have been shipped to the United States so far under this program. As the FRR SNF Acceptance Program progresses into the fifth year of implementation, a second U.S. cross country shipment has been completed, as well as a second overland truck shipment from Canada. Both the cross country shipment and the Canadian shipment were safely and successfully completed, increasing our knowledge and experience in these types of shipments. In addition, two other shipments were completed since last year's RERTR meeting. Other program activities since the last meeting included: taking pre-emptive steps to avoid license amendment pitfalls/showstoppers for spent fuel casks, publication of a revision to the Record of Decision allowing up to 16 casks per ocean going vessel, and the issuance of a cable to 16 of the 41 eligible countries reminding their governments and the reactor operators that the U.S.-origin uranium in their research reactors may be eligible for return to the United States under the Acceptance Program and urging them to begin discussions on shipping schedules. The FRR SNF program has also supported the Department's implementation of the competitive pricing policy for uranium and resumption of shipments of fresh uranium for fabrication into assemblies for research reactors. The United States Foreign Research Reactor Spent Nuclear Fuel Acceptance Program continues

  13. NUMATH: a nuclear-material-holdup estimator for unit operations and chemical processes

    International Nuclear Information System (INIS)

    Krichinsky, A.M.

    1981-01-01

    A computer program, NUMATH (Nuclear Material Holdup Estimator), has been developed to permit inventory estimation in vessels involved in unit operations and chemical processes. This program has been implemented in an operating nuclear fuel processing plant. NUMATH's purpose is to provide steady-state composition estimates for material residing in process vessels until representative samples can be obtained and chemical analyses can be performed. Since these compositions are used for inventory estimation, the results are determined for and cataloged in container-oriented files. The estimated compositions represent material collected in applicable vessels-including consideration for material previously acknowledged in these vessels. The program utilizes process measurements and simple material balance models to estimate material holdups and distribution within unit operations. During simulated run testing, NUMATH-estimated inventories typically produced material balances within 7% of the associated measured material balances for uranium and within 16% of the associated, measured material balance for thorium during steady-state process operation

  14. Nuclear power plant life extension in the United Kingdom

    International Nuclear Information System (INIS)

    Goodison, D.; Seddon, J.W.; Pape, E.M.

    1991-01-01

    The safety cases for the United Kingdom's older nuclear power plant have been reviewed by their utilities in order to justify continued operation of the reactors up to an age of at least 30 year. These 'long term safety reviews' have identified worthwhile plant modifications and aspects where further studies or plant inspections are required. As the plants approach the age of 30 years, 'life extension reviews' are now being undertaken, concentrating on management of ageing, to support operation to at least 40 years. (author)

  15. CINDU: Catalogue of Numerical Neutron Data Available from the IAEA Nuclear Data Unit

    Energy Technology Data Exchange (ETDEWEB)

    Good, W. M.; Attree, P. M.; Konshin, V. A.; Lemmel, H. D.; Lorenz, A. [IAEA, Nuclear Data Unit, Vienna (Austria)

    1967-11-15

    As a consequence of the progress in the field of international data exchange, and in compliance with the recommendations of the International Nuclear Data Committee (INDC) to the Director General of the IAEA, the Nuclear Data Unit has established a neutron data compilation center for the purpose of promoting international acquisition and exchange of basic neutron data. The present issue of CINDU is a Catalog of the current data holdings of the IAEA Nuclear Data Unit as of 1 November 1967. It serves a dual function: to act as an essential aid in the international exchange of data, and second, to inform data users of the current holdings in Vienna. In a worldwide distribution of labor the IAEA Nuclear Data Unit shares its responsibilities of data collection and dissemination with the data centers in Brookhaven, Saclay and Obninsk. As the result of this international cooperation, this CINDU catalog includes not only data collected by the IAEA Nuclear Data Unit from its own service area, but also considerable contributions by the other data centers. The user of CINDU will notice that during the last months, a number of data sets have been received which are completely unpublished or will be published only in 1968. Other data referenced in CINDU, supersede data that have been published earlier. There are even data and experiments which have not been mentioned at all in the literature, not even in progress reports or abstracts. The existence of such data is made public for the first time by this issue of CINDU. Thus, the DASTAR-CINDU system has started acting as a new computerized publication medium. As with other publications, authors receive proof copies of their data as they have been entered in the DASTAR data file. As soon as a set of data is revised, a second version of the DASTAR table is prepared, and all customers who have received the first version in the meantime, will automatically receive the second version. CINDU references only those data which have been

  16. CINDU: Catalogue of Numerical Neutron Data Available from the IAEA Nuclear Data Unit

    International Nuclear Information System (INIS)

    Good, W.M.; Attree, P.M.; Konshin, V.A.; Lemmel, H.D.; Lorenz, A.

    1967-11-01

    As a consequence of the progress in the field of international data exchange, and in compliance with the recommendations of the International Nuclear Data Committee (INDC) to the Director General of the IAEA, the Nuclear Data Unit has established a neutron data compilation center for the purpose of promoting international acquisition and exchange of basic neutron data. The present issue of CINDU is a Catalog of the current data holdings of the IAEA Nuclear Data Unit as of 1 November 1967. It serves a dual function: to act as an essential aid in the international exchange of data, and second, to inform data users of the current holdings in Vienna. In a worldwide distribution of labor the IAEA Nuclear Data Unit shares its responsibilities of data collection and dissemination with the data centers in Brookhaven, Saclay and Obninsk. As the result of this international cooperation, this CINDU catalog includes not only data collected by the IAEA Nuclear Data Unit from its own service area, but also considerable contributions by the other data centers. The user of CINDU will notice that during the last months, a number of data sets have been received which are completely unpublished or will be published only in 1968. Other data referenced in CINDU, supersede data that have been published earlier. There are even data and experiments which have not been mentioned at all in the literature, not even in progress reports or abstracts. The existence of such data is made public for the first time by this issue of CINDU. Thus, the DASTAR-CINDU system has started acting as a new computerized publication medium. As with other publications, authors receive proof copies of their data as they have been entered in the DASTAR data file. As soon as a set of data is revised, a second version of the DASTAR table is prepared, and all customers who have received the first version in the meantime, will automatically receive the second version. CINDU references only those data which have been

  17. Alteration in reactor installation (addition of Unit 2) in Shimane Nuclear Power Station, Chugoku Electric Power Co., Inc. (inquiry)

    International Nuclear Information System (INIS)

    1983-01-01

    An inquiry was made by the Ministry of International Trade and Industry to Nuclear Safety Commission on the addition of Unit 2 in Shimane Nuclear Power Station of The Chugoku Electric Power Co., Inc., concerning the technical capability of Chugoku Electric Power Co., Inc., and the plant safety. The NSC requested the Committee on Examination of Reactor Safety to make a deliberation on this subject. Both the technical capability and the safety of Unit 1 were already confirmed by MITI. Unit 2 to be newly added in the Shimane Nuclear Power Station is a BWR power plant with electric output of 820 MW. The examination made by MITI is described: the technical capability of Chugoku Electric Power Co., Inc., the safety of Unit 2 about its siting, reactor proper, reactor cooling system, radioactive waste management, etc. (J.P.N.)

  18. Indemnification for nuclear damages - recent developments in the United States

    International Nuclear Information System (INIS)

    Shapar, H.K.

    1981-10-01

    Public liability for nuclear damages in the United States is dealt with by a Federal statutory system. The Price-Anderson Act provides a system of compensation for such damages with an overall limit of $560 million. This fund is composed of private insurance, a utility assessment pool, and Federal government indemnity. The 1979 accident at the Three Mile Island nuclear station resulted in a less-than-full-scale test of the system. For the most part, the system has performed as intended although certain problems have been brought to light. Legislative proposal since the accident have focused on increasing the $560 million limitation on liability, but so far none of these proposals has been acted upon by the U.S. Congress. In the next several years, the Nuclear Regulatory Commission and possibly Congress will consider application of the Price-Anderson system to high-level waste facilities. The Commission must file with the Congress within two years a comprehensive report on the Price-Anderson Act, including recommendations for its continuation and amendment. (NEA) [fr

  19. 78 FR 40200 - Duke Energy Carolinas, LLC, Oconee Nuclear Station Units 1, 2, and 3; Independent Spent Fuel...

    Science.gov (United States)

    2013-07-03

    ... NUCLEAR REGULATORY COMMISSION [Docket Nos. 72-1004, 72-40, 50-269, 50-270, and 50-287; NRC-2013-0135] Duke Energy Carolinas, LLC, Oconee Nuclear Station Units 1, 2, and 3; Independent Spent Fuel Storage Installation; Environmental Assessment and Finding of No Significant Impact AGENCY: Nuclear...

  20. 78 FR 45575 - Duke Energy Carolinas, LLC; Oconee Nuclear Station Units 1, 2, and 3; Independent Spent Fuel...

    Science.gov (United States)

    2013-07-29

    ... NUCLEAR REGULATORY COMMISSION [Docket Nos.: 72-1004, 72-40, 50-269, 50-270, 50-287; and NRC-2013- 0135] Duke Energy Carolinas, LLC; Oconee Nuclear Station Units 1, 2, and 3; Independent Spent Fuel Storage Installation AGENCY: Nuclear Regulatory Commission. ACTION: Exemption; issuance. SUMMARY: The NRC...

  1. Experience with respect to dose limitation in nuclear fuel service operations in the United Kingdom supporting civil nuclear power programmes

    International Nuclear Information System (INIS)

    Kennedy, J.W.

    1983-01-01

    Within the United Kingdom, the nuclear power generation programme is supported by nuclear fuel services including uranium enrichment, fuel fabrication and reprocessing, operated by British Nuclear Fuels Limited (BNFL). These have entailed the processing of large quantities of uranium and of plutonium and fission products arising in the course of irradiation of fuel in nuclear power stations and have necessitated substantial programmes for the radiological protection of the public and of the workers employed in the industry. This paper presents and reviews the statistics of doses recorded in the various sectors of nuclear fuel services operations against the background of the standards to which the industry is required to operate. A description is given of the development of BNFL policy in keeping with the objective of being recognized as among those industries regarded as safe and the resource implications of measures to reduce doses received by workers are reviewed in the light of experience. Finally, the paper reviews the epidemiological data which have been, and continue to be, collected for workers who have been employed in these nuclear fuel services. (author)

  2. The Comparison on Treatment Method of Liquid Radioactive Waste in Yonggwang No 3 and 4 and No 5 and 6

    International Nuclear Information System (INIS)

    Yeom, Yu Sun; Kim, Soong Pyung; Lee, Seung Jin

    2004-01-01

    Most of the low-level liquid radioactive wastes generated from PWR plants are classified into high or low total suspended solid(HTDS or LTDS), and into radiochemical and radioactive laundry waste. Although the evaporation process has a high decontamination ability, it has several problems such as corrosion, foam, and congestion. A new liquid waste disposal process using the ion-exchange demineralizer(IED), instead of the current evaporation process, has been introduced into the Yonggwang NPP No 5 and 6. These two methods have been compared to understand the differences in this study. Aspects compared here were the released radioactivity amount of the liquid radioactive wastes, the dose of off-site residents, the decontamination factor, and the amount of the solid radioactive wastes. The IED system is designed to discharge higher radioactivity about 20% than the evaporating system, and the actual radioactivity released from the evaporating and IED system were 0.473 mCi and 1.098 mCi, respectively. The radioactivity released from the IED was 2.32 times higher than that of the evaporating system. The dose of off-site residents was 2.97 x 10 -6 mSv for the evaporating system, and 6.47 x 10 -6 mSv for IED. The decontamination factor(DF) of the evaporator is, in most cases, far lower than the lower limits of detection(LLD) with the Ge-Li detector. Due to the low concentration of the liquid wastes collected from the liquid waste system, the decontamination factor of IED is very low. Since there is not enough data on the amount of solid radioactive wastes generated by the evaporation system, the comparison on these two systems has been conducted on the basis of the design, and the comparison result was that the evaporating system generated more wastes about 40% than IED.

  3. The Comparison on Treatment Method of Liquid Radioactive Waste in Yonggwang No 3 and 4 and No 5 and 6

    Energy Technology Data Exchange (ETDEWEB)

    Yeom, Yu Sun; Kim, Soong Pyung [Chosun University, Gwangju (Korea, Republic of); Lee, Seung Jin [RedTek CO., LTD., Daejeon (Korea, Republic of)

    2004-09-15

    Most of the low-level liquid radioactive wastes generated from PWR plants are classified into high or low total suspended solid(HTDS or LTDS), and into radiochemical and radioactive laundry waste. Although the evaporation process has a high decontamination ability, it has several problems such as corrosion, foam, and congestion. A new liquid waste disposal process using the ion-exchange demineralizer(IED), instead of the current evaporation process, has been introduced into the Yonggwang NPP No 5 and 6. These two methods have been compared to understand the differences in this study. Aspects compared here were the released radioactivity amount of the liquid radioactive wastes, the dose of off-site residents, the decontamination factor, and the amount of the solid radioactive wastes. The IED system is designed to discharge higher radioactivity about 20% than the evaporating system, and the actual radioactivity released from the evaporating and IED system were 0.473 mCi and 1.098 mCi, respectively. The radioactivity released from the IED was 2.32 times higher than that of the evaporating system. The dose of off-site residents was 2.97 x 10{sup -6} mSv for the evaporating system, and 6.47 x 10{sup -6} mSv for IED. The decontamination factor(DF) of the evaporator is, in most cases, far lower than the lower limits of detection(LLD) with the Ge-Li detector. Due to the low concentration of the liquid wastes collected from the liquid waste system, the decontamination factor of IED is very low. Since there is not enough data on the amount of solid radioactive wastes generated by the evaporation system, the comparison on these two systems has been conducted on the basis of the design, and the comparison result was that the evaporating system generated more wastes about 40% than IED.

  4. Concrete works in Igata Nuclear Power Station Unit-2

    International Nuclear Information System (INIS)

    Yanase, Hidemasa

    1981-01-01

    The construction of Igata Nuclear Power Station Unit-2 was started in February, 1978, and is scheduled to start the commercial operation in March, 1982. Construction works are to be finished by August, 1981. The buildings of Igata Nuclear Power Station are composed of large cross section concrete for the purpose of shielding and the resistance to earth quakes. In response to this, moderate heat Portland cement has been employed, and in particular, the heat of hydration has been controlled. In this report, also fine and coarse aggregates, admixtures and chemical admixtures, and further, the techniques to improve the quality are described. Concrete preparation plant was installed in the power station site. Fresh concrete was carried with agitator body trucks from the preparation plant to the unloading point, and from there with pump trucks. Placing of concrete was carried out, striving to obtain homogeneous and dense concrete by using rod type vibrators. Further, concrete was placed in low slump (8 - 15 cm) to reduce water per unit volume, and its temperature was also carefully controlled, e.g., cold water (temperature of mixing water was about 10 deg C) was used in summer season (end of June to end of September). As a result, the control target was almost satisfied. As for testing and inspection, visual appearance test was done as well as material testing in compliance with JIS and other standards. (Wakatsuki, Y.)

  5. Primary water chemistry control at units of Paks Nuclear Power Plant

    International Nuclear Information System (INIS)

    Schunk, J.; Patek, G.; Pinter, T.; Tilky, P.; Doma, A.; Osz, J.

    2010-01-01

    The primary water chemistry of the four identical units of Paks Nuclear Power Plant has been developed based on Western-type PWR units, taking into consideration some Soviet-Russian modifications. The political changes in 90s have also influenced the water chemistry specifications and directions. At PWR units the transition operational modes have been developed while in case of VVER units - in lack of central uniform regulation - this question has become the competence and responsibility of each individual plant. This problem has resulted in separate water chemistry developments with a considerable time delay. The needs for life-time extensions all over the World have made the development of start-up and shut-down chemistry procedures extremely important, since they considerably influence the long term and safe operation of plants. The uniformly structured limit value system, the principles applied for the system development, and the logic schemes for actions to be taken are discussed in the paper, both for normal operation and transition modes. (author)

  6. Primary Water Chemistry Control at Units of Paks Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Schunk, J.; Pinter, G. Patek T.; Tilky, P.; Doma, A. [Paks Nuclear Power Plant Co. Ltd., Paks (Hungary); Osz, J. [Budapest University of Technology and Economics, Budapest (Hungary)

    2013-03-15

    The primary water chemistry of the four identical units of Paks Nuclear Power Plant has been developed based on Western type PWR units, taking into consideration some Russian modifications. The political changes in the 1990s have also influenced the water chemistry specifications and directions. At PWR units the transition operational modes have been developed while in case of WWER units - in lack of central uniform regulation - this question has become the competence and responsibility of each individual plant. This problem has resulted in separate water chemistry developments with a considerable time delay. The need for lifetime extensions worldwide has made the development of startup and shutdown chemistry procedures extremely important, since they considerably influence the long term and safe operation of plants. The uniformly structured limit value system, the principles applied for the system development, and the logic schemes for actions to be taken are discussed in the paper, both for normal operation and transition modes. (author)

  7. A study on the optimal replacement periods of digital control computer's components of Wolsung nuclear power plant unit 1

    International Nuclear Information System (INIS)

    Mok, Jin Il; Seong, Poong Hyun

    1993-01-01

    Due to the failure of the instrument and control devices of nuclear power plants caused by aging, nuclear power plants occasionally trip. Even a trip of a single nuclear power plant (NPP) causes an extravagant economical loss and deteriorates public acceptance of nuclear power plants. Therefore, the replacement of the instrument and control devices with proper consideration of the aging effect is necessary in order to prevent the inadvertent trip. In this paper we investigated the optimal replacement periods of the control computer's components of Wolsung nuclear power plant Unit 1. We first derived mathematical models of optimal replacement periods to the digital control computer's components of Wolsung NPP Unit 1 and calculated the optimal replacement periods analytically. We compared the periods with the replacement periods currently used at Wolsung NPP Unit 1. The periods used at Wolsung is not based on mathematical analysis, but on empirical knowledge. As a consequence, the optimal replacement periods analytically obtained and those used in the field show a little difference. (Author)

  8. Cleaning device for steam units in a nuclear power plant

    International Nuclear Information System (INIS)

    Sasamuro, Takemi.

    1978-01-01

    Purpose: To prevent radioactive contamination upon dismantling and inspection of steam units such as a turbine to a building containing such units and the peripheral area. Constitution: A steam generator indirectly heated by steam supplied from steam generating source in a separate system containing no radioactivity is provided to produce cleaning steam. A cleaning steam pipe is connected by way of a stop valve between separation valve of a nuclear power plant steam pipe and a high pressure turbine. Upon cleaning, the separation valve is closed, and steam supplied from the cleaning steam pipe is flown into a condenser. The water thus condensated is returned by way of a feed water heater and a condenser to a water storage tank. (Nakamura, S.)

  9. 75 FR 14206 - FPL Energy Point Beach, LLC; Point Beach Nuclear Plant, Units 1 and 2; Environmental Assessment...

    Science.gov (United States)

    2010-03-24

    ... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-266 And 50-301; NRC-2010-0123 FPL Energy Point Beach, LLC; Point Beach Nuclear Plant, Units 1 and 2; Environmental Assessment and Finding of No Significant Impact The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an Exemption, pursuant to...

  10. Radiation dose distribution monitoring at neutron radiography facility area, Nuclear Energy Unit, Malaysia

    International Nuclear Information System (INIS)

    Abdul Razak Daud

    1995-01-01

    One experiment was carried out to get the distribution of radiation doses at the neutron radiography facilities, Nuclear Energy Unit, Malaysia. The analysis was done to evaluate the safety level of the area. The analysis was used in neutron radiography work

  11. Use of Planalog at Arkansas Nuclear One, Unit One

    International Nuclear Information System (INIS)

    Holcomb, T.

    1979-01-01

    The outage management system of the Arkansas Nuclear One, Unit one is summarized. With limited manpower the outage procedure must be streamlined but still be able to meet the requirements and needs of both the plant structure and the corporate structure. The functions and responsibilities of the outage coordinator are outlined. Outage preparation and control using the Planalog system are discussed. According to the author, even with the disadvantages of the Planalog system listed, it remains a field-proven, reliable tool for major outage activity control. 6 figures

  12. Nuclear design report for Ulchin nuclear power plant unit 2 cycle 5

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jin Ha; Park, Yong Soo; Cho, Byeong Ho; Zee, Sung Kyun; Lee, Sang Keun; Ahn, Dawk Hwan [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1993-09-01

    This report presents nuclear design calculations for cycle 5 of Ulchin unit it 2. Information is given on fuel loading, power density distributions, reactivity coefficients, control rod worths and operational limits. In addition, the report contains all necessary data for the startup tests including predicted values for the comparison with the measured data. The reload consists of 48 KOFA`s enriched by nominally 3.50 w/o U{sub 235}. Among the KOFA`s, 20 fuel assemblies contain gadolinia rods. The fuel assemblies in the core are arranged in a low leakage loading pattern. The cycle length of cycle 5 amounts to 293 EFPD corresponding to a cycle burnup of 11780 MWD/MTU. (Author) 8 refs., 55 figs., 16 tabs.

  13. An integrated nuclear reactor unit for a floating low capacity nuclear power plant designed for power supply in remote areas with difficult access

    International Nuclear Information System (INIS)

    Achkasov, A.N.; Grechko, G.I.; Gladkov, O.G.; Pavlov, V.L.; Pepa, V.N.; Shishkin, V.A.

    1997-01-01

    The paper describes the conceptual design of an integrated advanced safety nuclear reactor unit for a low capacity floating, NPP designed for power supply in areas which are remote with difficult access. The paper describes the major structural and lay-out components of the steam generator and reactor units with main technical characteristics. (author)

  14. 76 FR 79228 - Combined Licenses at William States Lee III Nuclear Station Site, Units 1 and 2; Duke Energy...

    Science.gov (United States)

    2011-12-21

    ... NUCLEAR REGULATORY COMMISSION [Docket Nos. 52-018 and 52-019; NRC-2008-0170] Combined Licenses at William States Lee III Nuclear Station Site, Units 1 and 2; Duke Energy Carolinas, LLC AGENCY: Nuclear.... SUMMARY: Notice is hereby given that the U.S. Nuclear Regulatory Commission (NRC) and the U.S. Army Corps...

  15. Potential Nuclear Power Plant Siting Issues in the United Arab Emirates

    International Nuclear Information System (INIS)

    Al Hanai, Waddah T.

    2011-01-01

    Based on the need to develop additional sources of electricity to meet future demand and to ensure the rapid growth of its economy, the United Arab Emirates has embarked on a nuclear programme. The Federal Law by Decree No. 6 of 2009, Concerning the Peaceful Uses of Nuclear Energy was signed by the President, last fall. This law created the Federal Authority for Nuclear Regulation (FANR), which is developing the framework of regulations which will guide the UAE programme. This paper reviews the development of the FANR regulation on Siting and the related environmental issues in general and those unique to the area. This will include steps being planned by the Authority to review the license application and the current concepts being looked at for the inspection programme. Among the unique aspects the author will look at are the results from a recent in-depth study performed on dust and sand storms. (author)

  16. The steam generator repair project of the Donald C. Cook Nuclear Plant, Unit 2

    International Nuclear Information System (INIS)

    White, J.D.

    1993-01-01

    Donald C. Cook Nuclear Plant Unit 2 is part of a two unit nuclear complex located in southwestern Michigan and owned and operated by the Indiana Michigan Power Company. The Cook Nuclear Plant is a pressurized water reactor (PWR) plant with four Westinghouse Series 51 steam generators housed in an ice condenser containment. This paper describes the program undertaken by Indiana Michigan Power and the American Electric Power Service Corporation (AEPSC) to repair the Unit 2 steam generators. (Both Indiana Michigan Power and AEPSC arc subsidiaries of American Electric Power Company, Incorporated (AEP). AEPSC provides management and technical support services to Indiana Michigan Power and the other AEP operating companies.) Eddy current examinations, in a series of refueling and forced outages between November 1983 and July 1986 resulted in 763 (5.6%) plugged tubes. In order to maintain adequate reactor core cooling, a limit of 10% is placed on the allowable percentage of steam generator tubes that can be removed from service by plugging. Additionally, sections of tubes were removed for metallurgical analysis and confirmed that the degradation was due to intergranular stress corrosion cracking. In developing the decision on how to repair the steam generators, four alternative actions were considered for addressing these problems: retubing in place, sleeving, operating at 80% reactor power to lower temperature and thus reduce the rate of corrosion, replacing steam generator lower assemblies

  17. Nuclear power in the United States: a new strategy to build on

    International Nuclear Information System (INIS)

    Bayne, Phillip

    1991-01-01

    The aim of this paper is to present the US utility industry's perspective on nuclear power, and to look ahead to what might happen during the 1990s, a time of great uncertainty. The US nuclear industry has, succeeded in taking a strategic approach to nuclear power. Two years ago, the Nuclear Power Oversight Committee (NPOC) started working on a Strategic Plan for Building New Nuclear Power Plants. NPOC is a group of senior executives representing private and public electric utilities, equipment suppliers and architect-engineers. Its role is to give broad policy guidance to the entire industry. NPOC's goal was to develop a comprehensive, integrated list of all the conditions that had to be met and the issues that had to be resolved in order to create an environment in which utilities would feel comfortable considering the nuclear option. The strategic plan, which was published in November 1990, identified fourteen issues, and assigned responsibility to different organisations for managing the issues. It also set timetables and milestones against which progress could be measured. Its goal is to create the conditions under which utilities can place an order or orders for new nuclear plants by the mid-1990s, with the first new unit on line by the turn of the century. The structure and content of the plan are discussed in this paper. (author)

  18. A technical report on YGN-3 and 4 plant computer system I/O point summary

    International Nuclear Information System (INIS)

    Zee, Sung Kyun; Lee, Ki Bog; Song, Jae Woong; Lee, Chang Ho; Kim, Jae Hak

    1994-02-01

    This report contains the results of the operational data analysis for nuclear key parameters in Yonggwang 2 cycle 5. It is verified that that the predicted values not only coincide well with the measured values except the end point boron concentration but also satisfy the safety limits. A quantitative evaluation to understand the discrepancy in the measured and predicted end point boron compared with the values of similar plants. Through this review and comparison, it is verified that the nuclear design and the related safety evaluation are properly executed. This analysis provides a means of validating the current nuclear design methodology. (Author) 12 refs., 54 figs., 6 tabs

  19. A technical report on YGN-3 and 4 plant computer system I/O point summary

    Energy Technology Data Exchange (ETDEWEB)

    Zee, Sung Kyun; Lee, Ki Bog; Song, Jae Woong; Lee, Chang Ho; Kim, Jae Hak [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1994-02-01

    This report contains the results of the operational data analysis for nuclear key parameters in Yonggwang 2 cycle 5. It is verified that that the predicted values not only coincide well with the measured values except the end point boron concentration but also satisfy the safety limits. A quantitative evaluation to understand the discrepancy in the measured and predicted end point boron compared with the values of similar plants. Through this review and comparison, it is verified that the nuclear design and the related safety evaluation are properly executed. This analysis provides a means of validating the current nuclear design methodology. (Author) 12 refs., 54 figs., 6 tabs.

  20. Improving nuclear safety of VVER-440 units

    International Nuclear Information System (INIS)

    Nochev, T.; Sabinov, S.

    2001-01-01

    In this paper authors deals with improvement of nuclear safety of WWER-440 units in Kozloduy NPP. Main directions for improving nuclear safety of WWER-440 units were: - to expand number of the design accident; - to increase reliability of equipment important for the safety; - to decrease the probability of initiating events; - improvements the integrity of the primary circuit (application LBB concept, qualification of the pressure safety valves to avoid pressurized thermal shock); - improvement of the fire protection; - improvement of the operation including upgrading and improvement of operational documents, implementation of new system for training the operators and etc.; - reassessment of the seismic response of the plant. Main actions were made at NPP Kozloduy to increase nuclear safety of VVER-440 units. 1. Modernization of Emergency High Pressure Safety Injection System. The modernization includes dividing of independent channels with reservation of active elements. Pumps were exchanged with more effective and reliable ones. HPSIS was increased reliability in general through decrease number of active elements and exchanged with passive. 2. For the purpose of avoiding fast cooling at the primary circuit and obtaining thermal shock of reactor vessel, Main Safety Insulation Valves are installed at NPP Kozloduy. 3. Modernization of Emergency power supplies AC. Oil breakers VMP-10 are exchanged with gas FS-4. 4. Generator breakers are installed to decrease probability of loss power supply and blackout. They provide reliable power supply to the system important for the safety in case of failure on generator. 5. I and C system has been qualified and optimized. 6. Reassessments of Limiting Conditions of Operation and new scram signals have been introduced. 7. An operators-oriented Informational System has been developed. It includes ensuring and updating of equipment data, new informational support of operator and etc. 8. A new auxiliary independent system for

  1. Engineering assessment of inactive uranium mill tailings: Phillips/United Nuclear site, Ambrosia Lake, New Mexico

    International Nuclear Information System (INIS)

    1981-10-01

    Ford, Bacon and Davis Utah, Inc., has reevaluated the Phillips/United Nuclear site in order to revise the December 1977 engineering assessment of the problems resulting from the existence of radioactive uranium mill tailings at Ambrosia Lake, New Mexico. This engineering assessment has included the preparation of topographic maps, the performance of core drillings and radiometric measurements sufficient to determine areas and volumes of tailings and radiation exposures of individuals and nearby populations, the investigations of site hydrology and meteorology, and the evaluation and costing of alternative corrective actions. Radon gas released from 2.6 million dry tons of tailings at the Phillips/United Nuclear site constitutes the most significant environmental impact, although windblown tailings and external gamma radiation also are factors. The four alternative actions presented in this engineering assessment range from millsite decontamination with the addition of 3 m of stabilization cover material, to removal of the tailings to remote disposal sites and decontamination of the tailings site. Cost estimates for the four options range from about $21,500,000 for stabilization in-place, to about $45,200,000 for disposal at a distance of about 15 mi. Three principal alternatives for the reprocessing of the Phillips/United Nuclear tailings were examined: heap leaching; treatment at an existing mill; and reprocessing at a new conventional mill constructed for tailings reprocessing.The cost of the uranium recovered would be about $87/lb of U 3 O 8 by either heap leach or conventional plant process. The spot market price for uranium was $25/lb early in 1981. Reprocessing the Phillips/United Nuclear tailings for uranium recovery does not appear to be economically attractive under present or foreseeable market conditions

  2. Conformance to Regulatory Guide 1.97, Arkansas Nuclear One, Unit No. 1

    International Nuclear Information System (INIS)

    Stoffel, J.W.

    1985-08-01

    This EG and G Idaho, Inc., report reviews the submittals for Regulatory Guide 1.97 for Unit No. 1 of Arkansas Nuclear One and identifies areas of nonconformance to the regulatory guide. Exceptions to Regulatory Guide 1.97 are evaluated and those areas where sufficient basis for acceptability is not provided are identified

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1996-04-01

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

  4. Safety-evaluation report related to operation of McGuire Nuclear Station, Units 1 and 2. Docket Nos. 50-369 and 50-370

    International Nuclear Information System (INIS)

    1983-05-01

    This report supplements the Safety Evaluation Report Related to the Operation of McGuire Nuclear Station, Units 1 and 2 (SER (NUREG-0422)) issued in March 1978 by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by Duke Power Company, as applicant and owner, for licenses to operate the McGuire Nuclear Station, Units 1 and 2 (Docket Nos. 50-369 and 50-370). The facility is located in Mecklenburg County, North Carolina, about 17 mi north-northwest of Charlotte, North Carolina. This supplement provides information related to issuance of a full-power authorization for Unit 2. The staff concludes that the McGuire Nuclear Station can be operated by the licensee without endangering the health and safety of the public

  5. On economic efficiency of nuclear power unit life extension using steam-gas topping plant

    International Nuclear Information System (INIS)

    Kuznetsov, Y.N.; Lisitsa, F.D.; Smirnov, V.G.

    2001-01-01

    The different options for life extension of the operating nuclear power units have been analyzed in the report with regard for their economic efficiency. A particular attention is given to the option envisaging the reduction of reactor power output and its subsequent compensation with a steam-gas topping plant. Steam generated at its heat-recovery boilers is proposed to be used for the additional loading of the nuclear plant turbine so as to reach its nominal output. It would be demonstrated that the implementation of this option allows to reduce total costs in the period of power plant life extension by 24-29% as compared with the alternative use of the replacing steam-gas unit and the saved resources could be directed, for instance, for decommissioning of a reactor facility. (authors)

  6. Nuclear liability insurance in the United States: an insurer's perspective

    International Nuclear Information System (INIS)

    Quattrocchi, J.

    2000-01-01

    By the mid-1950's the United States recognised that it was in the interest to promote commercial development of nuclear energy. But the uncertainties of the technology and the potential for severe accidents were clear obstacles to commercial development. Exposure to potentially serious uninsured liability inhibited the private sector. These impediments led Congress to enact the Price-Anderson Act in 1957. The Act had several purposes: the first was to encourage private development of nuclear power; the second was to establish a legal framework for handling potential liability claims; and the third was to provide a ready source of funds to compensate injured victims of a nuclear accident. Insurers chose the pooling technique by creating in the US the American Nuclear Insurers. ANI acts as a managing agent for its members insurance companies. The accident of three Miles Island occurred on 28 March 1979 and with came the claims experience in US. The 1988 amendments to the Price-Anderson Act directed the President to establish a Commission for the purpose of developing a means to assure full compensation of victims of a catastrophic nuclear accident that exceeds the limitation on aggregate public liability, or currently just over US$ 9.7 billion. The Presidential Commission issued its report in August 1990, in which it reached a number of conclusions and offered a number of recommendations.The US Congress has not acted on the Commission's report, but may revisit its recommendations as debate begins this year (1999) or next on the renewal of the Price-Anderson Act. (N.C.)

  7. Rewriting the history: a new future for the nuclear energy in United Kingdom?; Reescribiendo la historia: un nuevo futuro para la energia nuclear en Reino Unido?

    Energy Technology Data Exchange (ETDEWEB)

    Woodman, B. [University of Warwick, Coventry CV4 8UW (United Kingdom)

    2009-07-01

    From ends of the ninety, the new nuclear energy has been rejected three times like an option of viable energy generation for United Kingdom: once during the privatization of the electric supply industry and twice during the subsequent revisions to the energy politicians carried out in 2003. Nevertheless, three years more late, a new debate around the energy politics gave an unusual turning in the industry destination, characterized by the firm consideration in the political calendar about the new reactors development, as well as of governmental politicians guided to impel it. This recent interest arises of restlessness regarding the future security of the supply and to the necessity of reducing the carbon dioxide emissions of United Kingdom. With the purpose of obtaining the sufficient support of civil politicians and investors for the new construction project, the industry will have to devise convincing arguments to prove that it has already solved those problems that it suffered in the past and, also that deserves to receive a special treatment in the liberated market of the electricity. This document synthesizes the structure of the nuclear industry in United Kingdom, some recent historical data and the reasons for those that the new nuclear reactors were not very received in the past. It also indicates the measures that have taken in recent times to modify that perspective. Finally, it analyzes the possible future of the nuclear energy at long term in United Kingdom. (Author)

  8. Start-up test of Fukushima Daini Nuclear Power Station Unit No.3

    International Nuclear Information System (INIS)

    Inomata, Toshio; Umezu, Akira; Kajikawa, Makoto; Koibuchi, Hiroshi; Netsu, Nobuhiko.

    1986-01-01

    In Unit 3 of the Fukushima Nuclear Power Station II (daini), a BWR power plant of output 1,100 MW, commercial operation was started in June 1985. Its start-up test was finished successfully in about nine months. That is, new equipments introduced were demonstration tested. Though the items of testing are increased, the start-up test took short time, resulting in construction period only 54.7 months of the Unit 3, the shortest in the world. During the test, there was no scramming other than the planned. Described are the following: an outline of the Unit 3, the items of its improvement and standardization, including the new equipments, preparations for the start-up test, the start-up test and its evaluation. (Mori, K.)

  9. Occupational employment trends in selected nuclear industry segments in the United States of America

    International Nuclear Information System (INIS)

    Blair, L.M.

    1980-01-01

    The United States of America's nuclear energy industry expanded rapidly between 1968 and 1977, with total employment increasing by approximately 60%. Between 1973 and 1977 employment grew at a rate of 6.8% per year. The nuclear industry appears to have reached a mature status with the primary focus on commercial activities. The relative number of workers involved in research and development activities, outside of contract research facilities, has declined considerably since 1968 but appears to have stabilized. The industry labour force still has a relatively high proportion (43%) of scientific, engineering and technical workers. The occupational employment composition appears to have stabilized in the various nuclear segments indicating the emergence of longer run occupational distribution patterns. Employment expanded rapidly between 1968 and 1977 in most nuclear segments, with the exception of the research and development segment, where employment decreased by one-third. The present uncertainties concerning nuclear power development could have substantial impacts on the nuclear-related scientific, engineering, and technical labour force if a sizeable contraction occurs in reactor design and manufacturing and in design of nuclear facilities. (author)

  10. Kozloduy nuclear power plant. Units 1-4. Status of safety improvements. Rev. 2

    International Nuclear Information System (INIS)

    1999-01-01

    This paper presents the results of the safety improvements activities carried out by the Kozloduy Nuclear Power Plant (KNPP) within the period 1990-1998. The steam supply system of this units is based of the reactor WWER-440/ B-230, which is a PWR of russian design developed according to the safety standards in force in USSR in late sixties. Up to now 10 reactor units of this type are in operation in four NPPs. Despite of efforts of the different plants to implement safety improvements measures during first 10-15 years of operation of this type of reactor its major safety problems were not eliminated and were a subject of international concern. The systematic evaluation of the deficiencies of the original design of this type of reactors have been initiated by IAEA in the beginning of 1990 and brought to developing a comprehensive list of safety problems which required urgent implementation of safety measures in all plants. To solve this problems in 1991 KNPP initiated implementation of so called 'short term' safety improvement program, developed with the help of WANO under agreement with Bulgarian Nuclear Safety Authority (BNSA) and consortium RISKAUDIT. The program was based on a stage approach and was foreseen to be implemented by tree stages in very tight time schedule in order to achieve significant and rapid improvements of the level of safety in operation of the units. The Short term program was implemented between from 1991 to 1997 owing to strong safety commitment of NEC and KNPP staff as well as broad international cooperation and financial support. Important part of resources were supplied under PHARE program of CEC, EBRD grant agreement and EDF support. In parallel a special assessment process started in 1995 in order to evaluate the level of safety, achieved by Short Term Program, according to current safety standards and to define the measures, which should be implemented by the Utility to complete the process of improving the safety in future

  11. The development of nuclear law during the third United Nations Conference on the Law of the Sea

    International Nuclear Information System (INIS)

    Welck, S. von

    1976-01-01

    The Third United Nations Conference on the Law of the Sea will influence nuclear law in the following fields: construction and operation of offshore nuclear power plants, dumping of radioactive wastes in the sea, navigation of nuclear ships and maritime transport of radioactive materials. Nuclear law experts should take advantage of the situation of the present conference which may enable them the influence discussions as well as the outcome of the Conference in these fields by their expertise and knowledge. (Auth) [fr

  12. Multi-project, multi-national, geographically dispersed: Challenges for the Nuclear Renaissance in the United States

    International Nuclear Information System (INIS)

    Mathews, T.A.

    2007-01-01

    The nuclear renaissance in the United States is moving at a rapid pace due to the incentives in the Energy Policy Act of 2005, recognition of the environmental benefits of nuclear energy, and the need for stable, reliable, and diverse sources of energy. The U.S. is looking externally to capitalize on French, German, Japanese, and other worldwide experience. A number of challenges to the resurgence of nuclear power are common worldwide, including project management, workforce and supplier availability and large-project construction management experience. For example, AREVA's new plant project teams are comprised of resources drawn from various U.S. centers of technical expertise and backed up by AREVA's worldwide capabilities. However, the challenge lies in having the information infrastructure in place to integrate that expertise and share information across working groups. In another example, the U.S. regulatory process has changed significantly for the better, but the new streamlined combined license process has not been tested. Reactor vendors and utilities have injected new thinking into the process by pursuing Design Certification, Early Site Permit, and Combined License approval in parallel rather than in series. This paper will discuss these and other challenges to licensing and building new nuclear plants, and the approaches being used by AREVA to lead the Nuclear Renaissance in the United States. (author)

  13. 75 FR 75704 - Pacific Gas and Electric Company (Diablo Canyon Nuclear Power Plant, Units 1 And 2); Notice of...

    Science.gov (United States)

    2010-12-06

    ... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-275-LR; 50-323-LR] Pacific Gas and Electric Company (Diablo Canyon Nuclear Power Plant, Units 1 And 2); Notice of Appointment of Adjudicatory Employee... Seismologist, Office of Nuclear Material Safety and Safeguards, has been appointed as a Commission adjudicatory...

  14. 75 FR 53985 - Arizona Public Service Company, et al., Palo Verde Nuclear Generating Station, Unit 3; Temporary...

    Science.gov (United States)

    2010-09-02

    ... NUCLEAR REGULATORY COMMISSION [Docket No. STN 50-530; NRC-2010-0281] Arizona Public Service Company, et al., Palo Verde Nuclear Generating Station, Unit 3; Temporary Exemption 1.0 Background Arizona Public Service Company (APS, the licensee) is the holder of Facility Operating License No. NPF-74, which...

  15. Constraints on nuclear power development in the United States

    International Nuclear Information System (INIS)

    Brandfon, W.W.

    1984-01-01

    The U.S. nuclear option appears, at this time, to be disappearing. Determinants of energy supply seem to be changing from engineering and economic factors to other considerations. Regulatory and financial constraints now appear to be dominating the guidelines for electrical energy expansion. American electric utilities, for the most part, have not been able to obtain sufficient revenues to cover their costs of production. What price increases that they are being allowed to charge their customers come too late to keep up with inflation. They require increasing quantities of outside funding in the form of debt and equity capital. This they can only obtain at record high rates, if at all. Most utilities are not even earning what their regulators have determined are fair returns. Financial problems and regulatory tangles severely affect nuclear power, despite its proven technology and environmental and economic benefits. If the United States loses the nuclear alternative, the economic consequences of limiting fuels for electric base load generation to coal only will be severe; analogous to a monopoly situation in fuel supply. It is doubtful, despite the huge resources of coal, that the coal industry can satisfy even a reduced future demand. The question then becomes whether the technological leader of the world may in the future be faced with blackouts and rationing of electricity

  16. Development of a method to evaluate shared alternate AC power source effects in multi-unit nuclear power plants

    International Nuclear Information System (INIS)

    Jung, Woo Sik; Yang, Joon Eun

    2003-07-01

    In order to evaluate accurately a Station BlackOut (SBO) event frequency of a multi-unit nuclear power plant that has a shared Alternate AC (AAC) power source, an approach has been developed which accommodates the complex inter-unit behavior of the shared AAC power source under multi-unit Loss Of Offsite Power (LOOP) conditions. The approach is illustrated for two cases, 2 units and 4 units at a single site, and generalized for a multi-unit site. Furthermore, the SBO frequency of the first unit of the 2-unit site is quantified. The SBO frequency at a target unit of Probabilistic Safety Assessment (PSA) could be underestimated if the inter-unit dependency of the shared AAC power source is not properly modeled. The effect of the inter-unit behavior of the shared AAC power source on the SBO frequency is not negligible depending on the Common Cause Failure (CCF) characteristics among AC power sources. The methodology suggested in the present report is believed to be very useful in evaluating the SBO frequency and the core damage frequency resulting from the SBO event. This approach is also applicable to the probabilistic evaluation of the other shared systems in a multi-unit nuclear power plant

  17. Emergency planning requirements and short-term countermeasures for commercial nuclear power plants in the United States

    International Nuclear Information System (INIS)

    Kantor, F.; Hogan, R.; Mohseni, A.

    1995-01-01

    Since the accident at the Three Mile Island Unit, the United States Nuclear Regulatory's Commission (NRC's) emergency planning regulations are now considered and an important part of the regulatory framework for protecting the public health and safety. Many aspects of the countermeasures are presented: Emergency Planning Zones (EPZ), off-Site emergency planning and preparedness, responsibilities of nuclear power plants operators and states and local government. Finally, protective action recommendations are given as well as the federal response to an emergency. The authors noted that the use of potassium iodide is not considered as an effective countermeasure for the public protection in the US. (TEC). 1 fig

  18. Planning for decommissioning of Ignalina Nuclear Power Plant Unit-1

    International Nuclear Information System (INIS)

    Poskas, P.; Poskas, R.; Zujus, R.

    2002-01-01

    In accordance to Ignalina NPP Unit 1 Closure Law, the Government of Lithuania approved the Ignalina NPP Unit 1 Decommissioning Program until 2005. For enforcement of this program, the plan of measures for implementation of the program was prepared and approved by the Minister of Economy. The plan consists of two parts, namely technical- environmental and social-economic. Technical-environmental measures are mostly oriented to the safe management of spent nuclear fuel and operational radioactive waste stored at the plant and preparation of licensing documents for Unit 1 decommissioning. Social-economic measures are oriented to mitigate the negative social and economic impact on Lithuania, inhabitants of the region, and, particularly, on the staff of Ignalina NPP by means of creating favorable conditions for a balanced social and economic development of the region. In this paper analysis of planned radioactive waste management technologies, licensing documents for decommissioning, other technical-environmental and also social-economic measures is presented. Specific conditions in Lithuania important for defining the decommissioning strategy are highlighted. (author)

  19. [The Chinese nuclear test and 'atoms for peace' as a measure for preventing nuclear armament of Japan: the nuclear non-proliferation policy of the United States and the introduction of light water reactors into Japan, 1964-1968].

    Science.gov (United States)

    Yamazaki, Masakatsu

    2014-07-01

    Japan and the United States signed in 1968 a new atomic energy agreement through which US light-water nuclear reactors, including those of the Fukushima Daiichi Nuclear Power Plant of Tokyo Electric Power Company, were to be introduced into Japan. This paper studies the history of negotiations for the 1968 agreement using documents declassified in the 1990s in the US and Japan. After the success of the Chinese nuclear test in October 1964, the United States became seriously concerned about nuclear armament of other countries in Asia including Japan. Expecting that Japan would not have its own nuclear weapons, the US offered to help the country to demonstrate its superiority in some fields of science including peaceful nuclear energy to counter the psychological effect of the Chinese nuclear armament. Driven by his own political agenda, the newly appointed Prime Minister Eisaku Sato responded to the US expectation favorably. When he met in January 1965 with President Johnson, Sato made it clear that Japan would not pursue nuclear weapons. Although the US continued its support after this visit, it nevertheless gave priority to the control of nuclear technology in Japan through the bilateral peaceful nuclear agreement. This paper argues that the 1968 agreement implicitly meant a strategic measure to prevent Japan from going nuclear and also a tactic to persuade Japan to join the Nuclear Non -Proliferation Treaty.

  20. Experience in the United States with a secondary resource curriculum on ''Science, society and America's nuclear waste''

    International Nuclear Information System (INIS)

    King, G.P.

    1994-01-01

    The nuclear power and nuclear waste situation in the Usa, is first reviewed. In order to enhance information concerning these topics among pupils and teachers, a resource curriculum, 'Science, society, and America's Nuclear Waste', was developed by teachers for teachers; it consists of four units: nuclear waste, ionizing radiation, the nuclear waste policy act, and the waste management system. It has been well received by teachers. Within nine months after its national introduction, 350000 teacher and student curriculum documents were requested by teachers from all 50 states. Requests have been also received from 250 foreign colleges and universities

  1. Nuclear engineering education in the United States: The first 50 years

    International Nuclear Information System (INIS)

    Brown, G.

    2004-01-01

    Full text: This paper will discuss recent trends in the nuclear engineering education infrastructure in the United States. In the last several years political, economic and technical issues have been addressed and nuclear technology appears poised to resume growing again. It is in this new environment that there has been a confluence of industry, government and academic interests to see that nuclear engineering education retains its vitality and ability to provide technological leadership and a well-educated workforce. In order to understand the current situation it is important to give a brief historical perspective covering the six decades since the inception of 'Atoms for Peace' in 1953. The passage of the Atomic Energy Act of 1954 established the Atomic Energy Commission and the declassification of much nuclear technology and scientific material. There was an understandable optimistic outlook as to the potential for nuclear technology in the areas of power, medicine and other industrial and scientific applications. There were commercial concepts for using nuclear energy to power ships, planes, rockets, and cars. But the must successful application, by far was in the area of electric power production. In only a few years demonstration nuclear power plants were built and the infamous quote - 'two cheap to meter' was reported. In the following decade much progress was made and commercial plant orders increased substantially in number and in size. There were going to light water reactors, gas cooled reactors, liquid metal fast reactors, reprocessing, waste buried in salt mines. There was going to be 'a 1000 reactors in the year 2000'. This was the picture in the United States in the 50's and 60's. And it was in this environment that nuclear engineering education was birthed and grew. The first nuclear engineering academic programs and university research reactors were established in the 1950's at such places as North Carolina State, MIT, Penn State and others

  2. Safety Experts Complete IAEA Nuclear Regulatory Review of the United States

    International Nuclear Information System (INIS)

    2010-01-01

    Full text: An international team of senior nuclear safety experts today completed a two-week International Atomic Energy Agency (IAEA) review of the governmental and regulatory framework for nuclear safety in the United States. The team identified good practices within the U.S. system and offered suggestions for ways the U.S. Nuclear Regulatory Commission (NRC) could improve. The IAEA has conveyed the team's main conclusions to the NRC, and a final report will be submitted to the NRC in about two months. At the request of the United States, the IAEA assembled a team of 19 international experts to conduct an Integrated Regulatory Review Service (IRRS) mission. This mission was a peer review based on the IAEA Safety Standards. It was not an inspection, nor an audit. The experts came from 14 different countries: Canada, China, the Czech Republic, Finland, France, Italy, Japan, Mexico, the Republic of Korea, Slovenia, Spain, Sweden, Switzerland, and the United Kingdom. Team leader Jukka Laaksonen of Finland said: ''We found a comprehensive, consistent, and mature regulatory system run by the NRC, which has a strong drive for continuous improvement.' The scope of the mission included the U.S. regulatory framework and the regulation of the nuclear plant operation. The mission was conducted from 18 to 29 October, mainly at NRC headquarters outside of Washington, D.C. To study U.S. regulatory activities, the mission conducted a series of interviews and discussions with NRC staff and other organizations to help assess the effectiveness of the regulatory system. In addition, the team observed regulatory activities at two operating nuclear power reactors and an emergency preparedness exercise. The IAEA's IRRS coordinator Gustavo Caruso said, ''This mission represents a milestone for the IRRS program because the U.S. regulatory system is the largest in the world and many nations look to it. The IRRS is a useful tool that allows host nations to gain guidance from experienced

  3. 75 FR 13606 - Arizona Public Service Company, Palo Verde Nuclear Generating Station, Units 1, 2, and 3...

    Science.gov (United States)

    2010-03-22

    ... NUCLEAR REGULATORY COMMISSION [Docket Nos. STN 50-528, STN 50-529, and STN 50-530; NRC-2010-0114] Arizona Public Service Company, Palo Verde Nuclear Generating Station, Units 1, 2, and 3; Environmental...-74, issued to Arizona Public Service Company (APS, the licensee), for operation of the Palo Verde...

  4. System and Software Design for the Plant Protection System for Shin-Hanul Nuclear Power Plant Units 1 and 2

    International Nuclear Information System (INIS)

    Hwang, In Seok; Kim, Young Geul; Choi, Woong Seock; Sohn, Se Do

    2015-01-01

    The Reactor Protection System(RPS) protects the core fuel design limits and reactor coolant system pressure boundary for Anticipated Operational Occurrences (AOOs), and provides assistance in mitigating the consequences of Postulated Accidents (PAs). The ESFAS sends the initiation signals to Engineered Safety Feature - Component Control System (ESF-CCS) to mitigate consequences of design basis events. The Common Q platform Programmable Logic Controller (PLC) was used for Shin-Wolsung Nuclear Power Plant Units 1 and 2 and Shin-Kori Nuclear Power Plant Units 1, 2, 3 and 4 since Digital Plant Protection System (DPPS) based on Common Q PLC was applied for Ulchin Nuclear Power Plant Units 5 and 6. The PPS for Shin-Hanul Nuclear Power Plant Units 1 and 2 (SHN 1 and 2) was developed using POSAFE-Q PLC for the first time for the PPS. The SHN1 and 2 PPS was delivered to the sites after completion of Man Machine Interface System Integrated System Test (MMIS-IST). The SHN1 and 2 PPS was developed to have the redundancy in each channel and to use the benefits of POSAFE-Q PLC, such as diagnostic and data communication. The PPS application software was developed using ISODE to minimize development time and human errors, and to improve software quality, productivity, and reusability

  5. System and Software Design for the Plant Protection System for Shin-Hanul Nuclear Power Plant Units 1 and 2

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, In Seok; Kim, Young Geul; Choi, Woong Seock; Sohn, Se Do [KEPCO EnC, Daejeon (Korea, Republic of)

    2015-10-15

    The Reactor Protection System(RPS) protects the core fuel design limits and reactor coolant system pressure boundary for Anticipated Operational Occurrences (AOOs), and provides assistance in mitigating the consequences of Postulated Accidents (PAs). The ESFAS sends the initiation signals to Engineered Safety Feature - Component Control System (ESF-CCS) to mitigate consequences of design basis events. The Common Q platform Programmable Logic Controller (PLC) was used for Shin-Wolsung Nuclear Power Plant Units 1 and 2 and Shin-Kori Nuclear Power Plant Units 1, 2, 3 and 4 since Digital Plant Protection System (DPPS) based on Common Q PLC was applied for Ulchin Nuclear Power Plant Units 5 and 6. The PPS for Shin-Hanul Nuclear Power Plant Units 1 and 2 (SHN 1 and 2) was developed using POSAFE-Q PLC for the first time for the PPS. The SHN1 and 2 PPS was delivered to the sites after completion of Man Machine Interface System Integrated System Test (MMIS-IST). The SHN1 and 2 PPS was developed to have the redundancy in each channel and to use the benefits of POSAFE-Q PLC, such as diagnostic and data communication. The PPS application software was developed using ISODE to minimize development time and human errors, and to improve software quality, productivity, and reusability.

  6. Financing Nuclear Projects. Case Study: Unit 2 Cernavoda NPP

    International Nuclear Information System (INIS)

    Chirica, Teodor; Constantin, Carmencita; Dobrin, Marian

    2003-01-01

    The implementation of a Nuclear Power Plant (NPP) is a major undertaking for all entities involved, due to the necessity of planning work and coordination of the implementation process of the different fields of interest, starting with the governmental authorities and ending with the public. Having in view the specific investment costs (relatively high) for a NPP, finding an adequate financing structure is possible through an iterative process that involves first an assessment of the technical performances of the project and secondly, the mathematical modelling of the financing structure effects on the projects. In this respect, the paper will be focused on the main steps needed in order to promote an investment project in nuclear field, starting with the decision phase, providing the documentation requested by the local and international authorities to promote the project and ending with the negotiation of the contracts (commercial contract, financing contract, purchase contract, etc). The case study will be focused on the phases achieved in order to promote the Unit 2 NPP Cernavoda completion works project. (authors)

  7. Financing nuclear projects. Case study: Unit 2 Cernavoda NPP

    International Nuclear Information System (INIS)

    Chirica, T.; Pall, S.; Lebedev, A.; Dobrin, M.

    2003-01-01

    The implementation of a Nuclear Power Plant (NPP) in a country is a major undertaking for all entities involved, due to the necessity of planning work and co-ordination of the implementation process of the different fields of interest, starting with the governmental authorities and ending with the people. Having in view the specific investment cost (relatively high) for a NPP, to find an adequate financing structure is possible through an iterative process that involves first an assessment of the technical performances of the project and second, the mathematical modelling of the financing structure effects on the project. In this respect, the paper proposed will be focused on the main steps needed in order to promote an investment project in nuclear field, starting with the decision phase, providing the documentations requested by the local and international authorities to promote the project and ending with the negotiation of the contracts (commercial contract, financing contract, power purchase contract, etc.) The case study will be focused on the phases achieved in order to promote the Unit 2 Cernavoda NPP completion works project. (author)

  8. Cross-connected onsite emergency A.C. power supplies for multi-unit nuclear power plant sites

    International Nuclear Information System (INIS)

    Martore, J.A.; Voss, J.D.; Duncil, B.

    1987-01-01

    Recently, utility management, both at the corporate and plant operations levels, have reinforced their commitment to assuring increased plant reliability and availability. One means of achieving this objective involves an effective preventive maintenance program with technical specifications which allow implementation of certain preventive maintenance without plant shutdown. To accomplish this, Southern California Edison Company (SCE) has proposed a design change for San Onofre nuclear generating station (SONGS) units 2 and 3 to permit on emergency diesel generator for one unit to perform as an available AC power source for both units. Technical specifications for SCE's SONGS units 2 and 3, as at most nuclear power plants, currently require plant shutdown should one of the two dedicated onsite emergency AC power sources (diesel generators) become inoperable for more than 72 hours. This duration hinders root cause failure analysis, tends to limit the flexibility of preventive maintenance and precludes plant operation in the event of component failure. Therefore, this proposed diesel generator cross-connect design change offers an innovative means for averting plant shutdown should a single diesel generator become inoperable for longer than 72 hours. (orig./GL)

  9. Re-launching nuclear energy in the United States: the last obstacles to be cleared

    International Nuclear Information System (INIS)

    Babinet, R.

    2006-10-01

    The author discusses the different important events, notably within the context of energy policy and in relationship with economical factors, which concern the nuclear sector and occurred within the past few years in the United States (since 2001). He describes the failure of the 'all-gas' strategy, the strengthening of the nuclear sector since 2001 (evolution of the stock availability, of operators, of production). He discusses the role of the federal State in the re-launching of nuclear energy by facilitating the licensing procedure for new reactors and by addressing the waste storage issue. He comments the adoption of the global bill on energy (EPAct 2005) and the freezing of the Yucca Mountain storage site. This last aspect promotes the interest in waste transmutation and in related programs, and the implementation of the GNEP (global nuclear energy partnership) which notably proposed an international approach to limit an uncontrolled proliferation of nuclear cycle technologies

  10. Large-Scale Combined Heat and Power (CHP) Generation at Loviisa Nuclear Power Plant Unit 3

    International Nuclear Information System (INIS)

    Bergroth, N.

    2010-01-01

    Fortum has applied for a Decision in Principle concerning the construction of a new nuclear power plant unit (Loviisa 3) ranging from 2800-4600 MWth at its site located at the southern coast of Finland. An attractive alternative investigated is a co-generation plant designed for large-scale district heat generation for the Helsinki metropolitan area that is located approximately 75 km west of the site. The starting point is that the district heat generation capacity of 3 unit would be around 1 000 MWth.The possibility of generating district heat for the metropolitan area by Loviisa's two existing nuclear power plant units was investigated back in the 1980s, but it proved unpractical at the time. With the growing concern of the climate change and the subsequent requirements on heat and power generation, the idea is much more attractive today, when recognising its potential to decrease Finland's carbon dioxide emissions significantly. Currently the district heat generation in metropolitan area is based on coal and natural gas, producing some five to seven million tonnes of carbon dioxide emissions annually. Large-scale combined heat and power (CHP) generation at the 3 unit could cut this figure by up to four million tonnes. This would decrease carbon dioxide emissions by as much as six percent. In addition, large-scale CHP generation would increase the overall efficiency of the new unit significantly and hence, reduce the environmental impact on the local marine environment by cutting heat discharges into the Gulf of Nuclear energy has been used for district heating in several countries both in dedicated nuclear heating plants and in CHP generation plants. However, the heat generation capacity is usually rather limited, maximum being around 250 MWth per unit. Set against this, the 3 CHP concept is much more ambitious, not only because of the much larger heat generation output envisaged, but also because the district heating water would have to be transported over a

  11. A regulatory perspective of the role of construction in revitalizing the United States nuclear industry

    International Nuclear Information System (INIS)

    Stello, V. Jr.

    1983-01-01

    Technical and managerial experience in nuclear power plant construction is presented from the perspective of the United States Nuclear Regulatory Commission (NRC). In the context of actions that would contribute to revitalizing the nuclear industry in the United States of America, greater effectiveness of utility management during construction is proposed. The reasons why management effectiveness is so important are developed beginning with summaries of defects that were built into several US plants under construction. The root causes of these significant defects were management failures. In terms of benefits, effective management is important because of its effects on nuclear safety, project construction costs, and future reliability of the plant after commissioning. Actions that would enhance good management include emphasizing the inseparable nature of production and quality, that quality cannot be inspected into a plant, and that a strong construction management staff and exchanges of experience and information are essential. Techniques that have been used successfully in construction management are discussed. NRC and industry initiatives are in progress to improve management responsibility and learning from experience. Projects include Owner's Certification, assessments of licensee performance, fostering good practices across the industry, and improving the NRC inspection programme. Revitalization will not be easy, but it is achievable. (author)

  12. NSSS design and cycle 1 operating history data for Arkansas Nuclear One, Unit-2. Final report

    International Nuclear Information System (INIS)

    Gagne, P.A.

    1981-03-01

    This report contains design and cycle 1 operating data for the Arkansas Nuclear One, Unit-2 nuclear steam supply system. The design data include descriptions of the reactor core, reactor coolant system, and control systems which are a part of the nuclear steam supply system. Operating history data are provided for the period of December 1978 through January 1980. The most important operating history data provided include reactor power, cumulative fuel burnup, control rod position, primary coolant temperature, and a series of power distribution state points

  13. The public information aspects of nuclear regulatory inspection in the United States

    International Nuclear Information System (INIS)

    Volgenau, E.

    1977-01-01

    The public information aspects of the regulation of nuclear power present a unique set of problems. Not only must the regulators communicate often complex technical information to the public, they must also assure the public, the press and the legislative bodies of the adequacy of the regulatory process and the safety of power plant operations. The United States Nuclear Regulatory Commission (NRC), recognizing the importance of a continuing, open dialogue with the public, has placed particular emphasis on informing the public of its operations. NRC's experiences have been both good and bad. On balance, however, the NRC believes it is following the best course by conducting its operations openly and candidly. (author)

  14. Assessment of potential risk of environmental radioactive contamination in northern Europe from terrestrial nuclear units in north-west Russia

    International Nuclear Information System (INIS)

    Lisovsky, I.; Baklanov, A.; Jacovlev, V.; Prutskov, V.; Bergman, R.

    1999-05-01

    This Technical Report, being part of the INTAS project 96-1802, constitutes a comprehensive presentation - covering basic results from separate contributions as specified below - of work performed during the first period (February 1998- February 1999). The aim of the INTAS project 96-1802: 'Assessment of potential risk of environmental radioactive contamination in northern Europe from terrestrial nuclear units in north-west Russia' is to assess the potential risk of environmental radioactive contamination from nuclear units in north-west Russia and resulting impacts on population and terrestrial ecosystems in the north. The work focuses mainly on airborne radioactive contamination, but some case studies also deal with accidental leakage from terrestrial nuclear sites to soil and coastal waters. The present material comprises in more detail the contributions from participants no.4 and no.5 based on the four internal reports referred to below: (1) Assessment of potential risk of environmental radioactive contamination in Northern Europe from terrestrial nuclear units in north-west Russia: 'Determination of the list of typical sources of danger emergency radioactive releases in an environment in connection with military activity in the North of Russia.' Technical report no.1 of the team no.5. St.-Petersburg State Technical University, St.-Petersburg. July 1998. 43 p.; (2) Assessment of potential risk of environmental radioactive contamination in Northern Europe from terrestrial nuclear units in North-west Russia: 'Analysis and description of source-term characteristics for accident linked with airborne radioactive releases from Kola Nuclear Power Plant. Establishing a network facility at INEP for communication among the INTAS Project participants.' Technical report no.1 of the team no.4. Kola Science Centre, Apatity. August 1998. 56 p.; (3) Assessment of potential risk of environmental radioactive contamination in Northern Europe from terrestrial nuclear units in

  15. Assessment of potential risk of environmental radioactive contamination in northern Europe from terrestrial nuclear units in north-west Russia

    Energy Technology Data Exchange (ETDEWEB)

    Lisovsky, I. [St. Petersburg State Technical Univ. (Russian Federation); Baklanov, A. [Inst. of the Northern Ecology Problems (INEP) (Russian Federation); Jacovlev, V. [St. Petersburg State Technical Univ. (Russian Federation); Prutskov, V. [Ministry of Defence (Russian Federation). First Central Research Inst. of Naval Shipbuilding; Tarasov, I. [Ministry of Defence (Russian Federation). 23 State Marine Project Inst.; Blecher, A. [State Unitary Enterprise (Russian Federation). Research Inst. of Industrial and Marine Medicine; Zvonariev, B.; Kuchin, N.; Rubanov, S.; Sergeiev, I. [State Scientific Centre (Russian Federation). Central Research Inst. of A. Krylov; Morozov, S.; Koshkin, V.; Fedorenko, Yu.; Rigina, O. [Inst. of the Northern Ecology Problems (INEP) (Russian Federation); Bergman, R. [ed.] [Defence Research Establishment, Umeaa (Sweden). Div. of NBC Defence

    1999-05-01

    This Technical Report, being part of the INTAS project 96-1802, constitutes a comprehensive presentation - covering basic results from separate contributions as specified below - of work performed during the first period (February 1998- February 1999). The aim of the INTAS project 96-1802: `Assessment of potential risk of environmental radioactive contamination in northern Europe from terrestrial nuclear units in north-west Russia` is to assess the potential risk of environmental radioactive contamination from nuclear units in north-west Russia and resulting impacts on population and terrestrial ecosystems in the north. The work focuses mainly on airborne radioactive contamination, but some case studies also deal with accidental leakage from terrestrial nuclear sites to soil and coastal waters. The present material comprises in more detail the contributions from participants no.4 and no.5 based on the four internal reports referred to below: (1) Assessment of potential risk of environmental radioactive contamination in Northern Europe from terrestrial nuclear units in north-west Russia: `Determination of the list of typical sources of danger emergency radioactive releases in an environment in connection with military activity in the North of Russia.` Technical report no.1 of the team no.5. St.-Petersburg State Technical University, St.-Petersburg. July 1998. 43 p.; (2) Assessment of potential risk of environmental radioactive contamination in Northern Europe from terrestrial nuclear units in North-west Russia: `Analysis and description of source-term characteristics for accident linked with airborne radioactive releases from Kola Nuclear Power Plant. Establishing a network facility at INEP for communication among the INTAS Project participants.` Technical report no.1 of the team no.4. Kola Science Centre, Apatity. August 1998. 56 p.; (3) Assessment of potential risk of environmental radioactive contamination in Northern Europe from terrestrial nuclear units in

  16. Economic impacts of electricity liberalization on the status of nuclear power generation in the United States

    International Nuclear Information System (INIS)

    Hattori, Toru

    2015-01-01

    This paper discusses the economic impact of electricity liberalization on the status of nuclear power generation in the United States. Nuclear power plants have been treated equally with other types of power plants in the liberalized electricity market. The existing nuclear power plants were thought to be competitive in liberalized wholesale electricity market. Competitive pressure from the market also facilitated efficiency improvement among the existing nuclear power plants. Although it was difficult to build new reactor, the U.S. nuclear power generators expanded capacity through up rates. In recent years, however, nuclear power plants suffer from the decline in wholesale power prices and some of them are forced to retire early. Although there are some market design issues that could be improved to maintain the efficient nuclear power plants in competitive environment, it is now argued that some additional arrangements to mitigate the investment risks of the nuclear power plants are necessary. (author)

  17. Comparison between Japan and the United States in the frequency of events in equipment and components at nuclear power plants

    International Nuclear Information System (INIS)

    Shimada, Yoshio

    2007-01-01

    The Institute of Nuclear Safety System, Incorporated (INSS) conducted trend analyses until 2005 to compare the frequency of events in certain electrical components and instrumentation components at nuclear power plants between Japan and the United States. The results revealed that events have occurred approximately an order of magnitude less often in Japan than in the United States. This paper compared Japan and the United States in more detail in terms of how often events - events reported under the reporting standards of the Nuclear Information Archive (NUCIA) or the Institute of Nuclear Power Operations (INPO) - occurred in electrical components, instrumentation components and mechanical components at nuclear power plants. The results were as follows: (1) In regard to electrical components and instrumentation components, events have occurred one-eighth less frequently in Japan than in the United States, suggesting that the previous results were correct. (2) Events have occurred more often in mechanical components than electrical components and instrumentation components in both Japan and the United States, and there was a smaller difference in the frequency of events in mechanical components between the two countries. (3) Regarding mechanical components, it was found that events in the pipes for critical systems and equipment, such as reactor coolant systems, emergency core cooling systems, instrument and control systems, ventilating and air-conditioning systems, and turbine equipment, have occurred more often in Japan than in the United States. (4) The above observations suggest that there is little scope for reducing the frequency of events in electrical components and instrumentation components, but that mechanical components such as pipes for main systems like emergency core cooling systems and turbine equipment in the case of PWRs, could be improved by re-examining inspection methods and intervals. (author)

  18. Science, Society, and America's Nuclear Waste: The Waste Management System, Unit 4. Teacher Guide. Second Edition.

    Science.gov (United States)

    Department of Energy, Washington, DC. Office of Civilian Radioactive Waste Management, Washington, DC.

    This guide is Unit 4 of the four-part series, Science, Society, and America's Nuclear Waste, produced by the U.S. Department of Energy's Office Civilian Radioactive Waste Management. The goal of this unit is to explain how transportation, a geologic repository, and the multi-purpose canister will work together to provide short-term and long-term…

  19. Inherent safety features in balance-of-plant layout

    International Nuclear Information System (INIS)

    Wattelet, P.L.; Green, K.J.

    1992-01-01

    Future nuclear units must be more economical to construct and operate, and, at the same time, clearly incorporate advances in safety over the current generation of light water reactors. To achieve these goals, the root causes of safety issues must be addressed. In this way, global, cost-effective solutions can be implemented. With simple, direct design approaches, the licensing risk is minimized and configuration control is enhanced. With proper planning in the early stages of plant design, postulated accidents and events can often be mitigated by passive features inherent in the basic structure and layout, eliminating expensive added protective structures and components often found in current designs. Korea Electric Power Corporation's Yonggwang (YGN) Units 3 and 4, shown in an artist's rendering in Figure 1, are now under construction in Korea. Engineering is more than 85% complete, and Unit 3 construction is more than 50% complete. Significant steps toward design simplification and safety enhancement have been made by addressing safety concerns very early in the design effort. The tools used to achieve this were improved symmetry and separation, isolation of potential hazards, and an improved design process

  20. WPPSS, now in technical default, moves to mothball nuclear unit 3 amidst opposition

    International Nuclear Information System (INIS)

    Utroska, D.

    1983-01-01

    Involved in a number of lawsuits and court challenges, the Washington Public Power Supply System (WPPSS) executive board voted in late May to suspend construction on nuclear unit 3 (underwritten by Bonneville Power Administration) unless additional funding were obtained. (Unit 1 previously was mothballed, and units 4 and 5 are canceled.) WPPSS also failed to pay its $15.6 million May bill to the bond trustee of units 4 and 5. With this monthly amount, the trustee aggregates funds to pay investor's interest of $93.6 million twice a year. Some of the 88 public power participants oppose paying the bond interest of $93.6 million twice a year. Some of the 88 public power participants oppose paying the bond interest and have gone to court. The trustee has been restrained from declaring WPPSS in default. The future of the units will be affected by the Washington Supreme Court decision on the contracts between public utility participants and WPPSS

  1. Smart Soft-Sensing for the Feedwater Flowrate at PWRs Using a GMDH Algorithm

    Science.gov (United States)

    Lim, Dong Hyuk; Lee, Sung Han; Na, Man Gyun

    2010-02-01

    The thermal reactor power in pressurized water reactors (PWRs) is typically assessed using secondary system calorimetric calculations based on accurate measurements of the feedwater flowrate. Therefore, precise measurements of the feedwater flowrate are essential. In most PWRs, Venturi meters are used to measure the feedwater flowrate. However, the fouling phenomena of the Venturi meter deteriorate the accuracy of the existing hardware sensors. Consequently, it is essential to resolve the inaccurate measurements of the feedwater flowrate. In this study, in order to estimate the feedwater flowrate online with high precision, a smart soft sensing model for monitoring the feedwater flowrate was developed using a group method of data handling (GMDH) algorithm combined with a sequential probability ratio test (SPRT). The uncertainty of the GMDH model was also analyzed. The proposed sensing and monitoring algorithm was verified using the acquired real plant data from Yonggwang Nuclear Power Plant Unit 3.

  2. Nuclear reactors built, being built, or planned in the United States as of December 31, 1980

    International Nuclear Information System (INIS)

    1981-04-01

    Nuclear Reactors Built, Being Built, or Planned contains unclassified information about facilities built, being built, or planned in the United States for domestic use or export as of December 31, 1980, which are capable of sustaining a nuclear chain reaction. Information is presented in five parts, each of which is categorized by primary function or purpose: civilian, military, production, export, and critical assembly facilities

  3. Nuclear reactors built, being built, or planned in the Unites States as of June 30, 1981

    International Nuclear Information System (INIS)

    Goulden, A.M.

    1983-01-01

    Nuclear Reactors Built, Being Built, or Planned contains unclassified information about facilities built, being built, or planned in the United States for domestic use or export as of June 30, 1981, which are capable of sustaining a nuclear chain reaction. Information is presented in five parts, each of which is categorized by primary function or pupose: civilian, military, production, export, and critical assembly facilities

  4. Technical cooperation on nuclear security between the United States and China : review of the past and opportunities for the future.

    Energy Technology Data Exchange (ETDEWEB)

    Pregenzer, Arian Leigh

    2011-12-01

    The United States and China are committed to cooperation to address the challenges of the next century. Technical cooperation, building on a long tradition of technical exchange between the two countries, can play an important role. This paper focuses on technical cooperation between the United States and China in the areas of nonproliferation, arms control and other nuclear security topics. It reviews cooperation during the 1990s on nonproliferation and arms control under the U.S.-China Arms Control Exchange, discusses examples of ongoing activities under the Peaceful Uses of Technology Agreement to enhance security of nuclear and radiological material, and suggests opportunities for expanding technical cooperation between the defense nuclear laboratories of both countries to address a broader range of nuclear security topics.

  5. Automatic examination of nuclear reactor vessels with focused search units. Status and typical application to inspections performed in accordance with ASME code

    International Nuclear Information System (INIS)

    Verger, B.; Saglio, R.

    1981-05-01

    The use of focused search units in nuclear reactor vessel examinations has significantly increased the capability of flaw indication detection and characterization. These search units especially allow a more accurate sizing of indications and a more efficient follow up of their history. In this aspect, they are a unique tool in the area of safety and reliability of installations. It was this type of search unit which was adopted to perform the examinations required within the scope of inservice inspections of all P.W.R. reactors of the French nuclear program. This paper summarizes the results gathered through the 4l examinations performed over the last five years. A typical application of focused search units in automated inspections performed in accordance with ASME code requirements on P.W.R. nuclear reactor vessels is then described

  6. Quality control of radiopharmaceutical dose calibrators in nuclear medicine unit

    International Nuclear Information System (INIS)

    Oliveira, C.F.M.; Lucindo Junior, C.R.; Lopes Filho, F.J.

    2015-01-01

    As part of the program to ensure quality in nuclear medicine unit, in addition to diagnostic procedures, are evaluated activity meters, which is intended to measure the aliquot of radiation of radionuclides and / or radiopharmaceuticals that are administered to patients undergoing diagnostic investigation and / or therapeutic treatment. The good operating condition of dose calibrators is essential to ensure efficiency, safety and reliability of the measurements, once the lack of accuracy in the responses of these equipments can cause significant errors in the activity administered to the patient and may result in poor quality images resulting in the repetition of examis and interference in the successful treatment of the patient. This study aims to, considering the need for constant evaluation of the functioning of the activity meters and the fact that this issue be part the responsibilities of the professional of radiology, perform quality control testing of these instruments in relation to the most recent norm of National Commission of nuclear Energy (CNEN-NN 3:05) in Brazil, that is also in according to the international standards and reference values established during acceptance testing of these instruments in a nuclear medicine service. For this, was made a review of specific literature and the use of barium, cobalt and cesium to the tests in a nuclear medicine service of the state of Pernambuco in Brazil. The obtained results of the specific tests utilized to verify the correct working of the dose calibrators show coherency with the resolutions of the CNEN-NN 3:05 and are also in agreement with the international standards to that the measurement of activities be made with accurate results and thereby contribute to the proper functioning of nuclear medicine service. (authors)

  7. Integrated plant safety assessment, Systematic Evaluation Program: Dresden Nuclear Power Station, Unit 2 (Docket No. 50-237)

    International Nuclear Information System (INIS)

    1989-10-01

    The US Nuclear Regulatory Commission (NRC) has prepared Supplement 1 to the final Integrated Plant Safety Assessment Report (IPSAR) (NUREG-0823), under the scope of the Systematic Evaluation Program (SEP), for the Commonwealth Edison Company (CECo) Dresden Nuclear Power Station, Unit 2 located in Grundy County, Illinois. The NRC initiated the SEP to provide the framework for reviewing the design of older operating nuclear reactor plants to reconfirm and document their safety. This report documents the review completed by means of the SEP for those issues that required refined engineering evaluations or the continuation of ongoing evaluations subsequent to issuing the final IPSAR for Dresden Unit 2. The review was provided for (1) an assessment of the significance of differences between current technical positions on selected issues and those that existed when Dresden Unit 2 was licensed, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. The final IPSAR and this supplement forms part of the bases for considering the conversion of the existing provisional operating license to a full-term operating license. 83 refs., 9 tabs

  8. Integrating industry nuclear codes and standards into United States Department of Energy facilities

    Energy Technology Data Exchange (ETDEWEB)

    Jacox, J.

    1995-02-01

    Recently the United States Department of Energy (DOE) has mandated facilities under their jurisdiction use various industry Codes and Standards developed for civilian power reactors that operate under U.S. Nuclear Regulatory Commission License. While this is a major step forward in putting all our nuclear facilities under common technical standards there are always problems associated with implementing such advances. This paper will discuss some of the advantages and problems experienced to date. These include the universal challenge of educating new users of any technical documents, repeating errors made by the NRC licensed facilities over the years and some unique problems specific to DOE facilities.

  9. Controlling engineering project changes for multi-unit, multi-site standardized nuclear power plants

    International Nuclear Information System (INIS)

    Randall, E.; Boddeker, G.; McGugin, H.; Strother, E.; Waggoner, G.

    1978-01-01

    Multibillioin dollar multiple nuclear power plant projects have numerous potential sources of engineering changes. The majority of these are internally generated changes, client generated changes, and changes from construction, procurement, other engineering organizations, and regulatory organizations. For multiunit, multisite projects, the use of a standardized design is cost effective. Engineering changes can then be controlled for a single standardized design, and the unit or site unique changes can be treated as deviations. Once an effective change procedure is established for change control of the standardized design, the same procedures can be used for control of unit or site unique changes

  10. Nuclear Regulatory Commission Issuances, September 1981

    International Nuclear Information System (INIS)

    1981-01-01

    Contents include: Issuances of the Nuclear Regulatory Commission--Commonwealth Edison Company (Dresden Nuclear Power Station, Unit 1), Consolidated Edison Company of New York (Indian Point, Unit 2), Metropolitan Edison Company, et al. (Three Mile Island Nuclear Station, Unit 1), Pacific Gas and Electric Company (Diablo Canyon Nuclear Power Plant, Units 1 and 2), Pacific Gas and Electric Company (Diablo Canyon Nuclear Power Plant, Units 1 and 2), Power Authority of the State of New York (Indian Point, Unit 3), Texas Utilities Generating Company, et al. (Comanche Peak Steam Electric Station, Units 1 and 2); Issuances of Atomic Safety and Licensing Appeal Boards--Pacific Gas and Electric Company (Diablo Canyon Nuclear Power Plant, Units 1 and 2), Philadelphia Electric Company, et al. (Peach Bottom Atomic Power Statin, Units 2 and 3), Metropolitan Edison Company, et al. (Three Mile Island Nuclear Statin, Unit No. 2), Public Service Electric and Gas Company (Hope Creek Generating Station, Units 1 and 2), The Toledo Edison Company, et al. (Davis-Besse Nuclear Power Station, Units 2 and 3); Issuances of the Atomic Safety Licensing Boards--Cleveland Electric Illuminating Company, et al. (Perry Nuclear Power Plant, Units 1 and 2), Commonwealth Edison Company (Dresden Station, Units 2 and 3), Houston Lighting and Power Company (Allens Creek Nuclear Generating Station, Unit 1), Southern California Edison Company, et al. (San Onofre Nuclear Generating Station, Units 2 and 3), Texas Utilities Generating Company, et al. (Comanche Peak Steam Electric Station, Units 1 and 2), Texas Utilities Generating Company, et al

  11. The radioactive waste debate in the United States and nuclear technology for peaceful purposes

    Science.gov (United States)

    Tehan, Terrence Norbert

    Many ethical, cultural, and economic concerns have accompanied the rapid growth of Western technology. Nuclear technology in particular has experienced considerable opposition because of its perceived dangers, especially disposal of atomic waste. While this field of science remains in its infancy, many legal, political and ecological groups oppose any further application of nuclear technology--including the significant medical, environmental, and economic benefits possible from a safe and responsible application of nuclear energy. Complete and objective knowledge of this technology is needed to balance a healthy respect for the danger of atomic power with its many advantages. This study focuses on one aspect of nuclear technology that has particularly aroused political and social controversy: nuclear waste. Finding ways of disposing safely of nuclear waste has become an extremely volatile issue because of the popular misconception that there is no permanent solution to this problem. This investigation will demonstrate that the supposedly enduring waste problem has been resolved in several industrial countries that now outstrip the United States in safe commercial applications of nuclear science. This dissertation offers a reasoned and objective contribution to the continuing national debate on the peaceful uses of nuclear technology. This debate becomes more crucial as the nation seeks a dependable substitute for the non-renewable sources of energy now rapidly being exhausted.

  12. Major alternatives for government policies, organizational structures, and actions in civilian nuclear reactor emergency management in the United States

    International Nuclear Information System (INIS)

    1980-01-01

    The purpose of this report is to identify and assess major alternatives for governmental policies, organizational structures, and actions in civilian nuclear reactor emergency management in the United States. The National Academy of Public Administration agreed to identify and evaluate alternatives for governmental policies, organizational structures, and actions in civilian nuclear reactor emergency management. It agreed to review present policies and practices in civilian nuclear reactor emergency management, to review selected experiences and practices of governmental agencies other than the Nuclear Regulatory Commission, and industries other than the nuclear power industry, and to identify alternatives to the present nuclear emergency system

  13. Institutional aspects of siting nuclear waste disposal facilities in the United States

    International Nuclear Information System (INIS)

    Stewart, John Cameron.; Prichard, Clark. W.

    1987-01-01

    This chapter deals with the institutional issues associated with the disposal of nuclear waste in the United States of America. These include socio-economic, financial, land use and especially, political factors. Institutional issues must, however, be resolved, as well as the technological problems of engineering and geology. The general issues are first examined, then the organisation and financing, land use, community acceptance, transport problems and finally, local economic impacts. (UK)

  14. Gas reactor international cooperative program interim report: United States/Federal Republic of Germany nuclear licensing comparison

    International Nuclear Information System (INIS)

    1978-09-01

    In order to compare US and FRG Nuclear Licensing, a summary description of United States Nuclear Licensing is provided as a basis. This is followed by detailed information on the participants in the Nuclear Licensing process in the Federal Republic of Germany (FRG). FRG licensing procedures are described and the rules and regulations imposed are summarized. The status of gas reactor licensing in both the U.S. and the FRG is outlined and overall conclusions are drawn as to the major licensing differences. An appendix describes the most important technical differences between US and FRG criteria

  15. Technical specifications for Grand Gulf Nuclear Station, Unit 1 (Docket No. 50-416). Appendix A to License No. NPF-13

    International Nuclear Information System (INIS)

    1984-08-01

    The Grand Gulf Nuclear Station, Unit 1 Technical Specifications were prepared by the US Nuclear Regulatory Commission to set forth the limits, operating conditions and other requirements applicable to a nuclear facility as set forth in Section 50.36 of 10 CFR part 50 for the protection of the health and safety of the public

  16. Development of reliability database for safety-related I and C component based on operating experience of KSNP

    International Nuclear Information System (INIS)

    Jang, S. C.; Han, S. H.; Min, K. R.

    2001-01-01

    Reliability database for safety-related I and C components has been developed, based on domestic operating experience of total 8.63 years from four units-Yonggwang Units 3 and 4, and Ulchin Units 3 and 4. This plant-specific data of safety-related I and C components has compared with operating experience for CE-supplied plants in U.S.A. As a results, we found that on the whole the domestic reliability data was similar to CE-supplied plants in USA, through lots of failures occurred early in the commercial operation were included in our analyses without percolation

  17. Integrated Level 3 risk assessment for the LaSalle Unit 2 nuclear power plant

    International Nuclear Information System (INIS)

    Payne, A.C. Jr.; Brown, T.D.; Miller, L.A.

    1991-01-01

    An integrated Level 3 probabilistic risk assessment (PRA) was performed on the LaSalle County Station nuclear power plant using state-of-the-art PRA analysis techniques. The objective of this study was to provide an estimate of the risk to the offsite population during full power operation of the plant and to include a characterization of the uncertainties in the calculated risk values. Uncertainties were included in the accident frequency analysis, accident progression analysis, and the source term analysis. Only weather uncertainties were included in the consequence analysis. In this paper selected results from the accident frequency, accident progression, source term, consequence, and integrated risk analyses are discussed and the methods used to perform a fully integrated Level 3 PRA are examined. LaSalle County Station is a two-unit nuclear power plant located 55 miles southwest of Chicago, Illinois. Each unit utilizes a Mark 2 containment to house a General Electric 3323 MWt BWR-5 reactor. This PRA, which was performed on Unit 2, included internal as well as external events. External events that were propagated through the risk analysis included earthquakes, fires, and floods. The internal event accident scenarios included transients, transient-induced LOCAs (inadvertently stuck open relief valves), anticipated transients without scram, and loss of coolant accidents

  18. System Definition Document: Reactor Data Necessary for Modeling Plutonium Disposition in Catawba Nuclear Station Units 1 and 2

    International Nuclear Information System (INIS)

    Ellis, R.J.

    2000-01-01

    The US Department of Energy (USDOE) has contracted with Duke Engineering and Services, Cogema, Inc., and Stone and Webster (DCS) to provide mixed-oxide (MOX) fuel fabrication and reactor irradiation services in support of USDOE's mission to dispose of surplus weapons-grade plutonium. The nuclear station units currently identified as mission reactors for this project are Catawba Units 1 and 2 and McGuire Units 1 and 2. This report is specific to Catawba Nuclear Station Units 1 and 2, but the details and materials for the McGuire reactors are very similar. The purpose of this document is to present a complete set of data about the reactor materials and components to be used in modeling the Catawba reactors to predict reactor physics parameters for the Catawba site. Except where noted, Duke Power Company or DCS documents are the sources of these data. These data are being used with the ORNL computer code models of the DCS Catawba (and McGuire) pressurized-water reactors

  19. Safety-evaluation report related to the operation of Shoreham Nuclear Power Station, Unit No. 1 (Docket No. 50-322)

    International Nuclear Information System (INIS)

    1983-09-01

    Supplement 4 (SSER 4) to the Safety Evaluation Report on Long Island Lighting Company's application for a license to operate the Shoreham Nuclear Power Station, Unit 1, located in Suffolk County, New York, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement addresses several items that have been reviewed by the staff since the previous supplement was issued

  20. Safety evaluation report related to the operation of Shoreham Nuclear Power Station, Unit No. 1. Docket No. 50-322

    International Nuclear Information System (INIS)

    1983-02-01

    Supplement No. 3 to the Safety Evaluation Report of Long Island Lighting Company's application for a license to operate the Shoreham Nuclear Power Station, Unit 1, located in Suffolk County, New York, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement addresses several items that have come to light since the previous supplement was issued

  1. Safety Evaluation Report related to the operation of Shoreham Nuclear Power Station, Unit No. 1 (Docket No. 50-322)

    International Nuclear Information System (INIS)

    1989-04-01

    Supplement 10 (SSER 10) to the Safety Evaluation Report on Long Island Lighting Company's application for a license to operate the Shoreham Nuclear Power Station, Unit 1, located in Suffolk County, New York, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement addresses several items that have been reviewed by the staff since the previous supplement was issued

  2. Reload safety evaluation of boron dilution accident related to shutdown margin proportional to boron concentration

    International Nuclear Information System (INIS)

    Zee, Sung Kyun; Lee, Ki Bog; Song, Jae Woong

    1993-06-01

    This report investigates the efficient safety evaluation method and analysis procedure on Boron Dilution Accident(BDA) under the proportional shutdown margin to boron concentration. Also investigated are problems caused by applying this shutdown margin limit. Through this investigation, the safety of Kori-3 Cycle-8, Yonggwang-2 Cycle-7, Kori-4 Cycle-8 and Yonggwang-1 Cycle-8 with respect to BDA is verified. In order to satisfy the shutdown margin requirement in the Technical Specifications, it is shown that the High Flux Alarm at Shutdown Setting for Kori-4 Cycle-8 and Yonggwang-1 Cycle-8 at Mode 5 should be set at 2 or the Technical Specification should be revised. (Author)

  3. Nuclear Education & Training — Showcasing the Best Practices of the United Kingdom and France

    International Nuclear Information System (INIS)

    Dato Syed Ahmad Idid, S.N. K. A.-I.

    2015-01-01

    Skilled, competent and sufficient human resources is fundamental for the safe and successful implementation and expansion of a nuclear power programme (NPP). As nuclear education and training (E&T) stakeholders deliberate and discuss to identify suitable syllabus and courses to offer for education and training to support NPP, it is critical that the nuclear fuel cycle as well as the nuclear power value-chain is taken into consideration in the selection and introduction of relevant courses by Universities and Institutions to nurture and educate skilled manpower for the nuclear power industry. This paper strives to share with the education and training stakeholders, that the task of educating and training students is not solely to prepare them to work in a nuclear power plant, but importantly also to train human resources to support other organizations that require skilled and competent personnel in nuclear related field including Government agencies and Ministries, Business and Industry, Financial sector, International agencies and media agencies, amongst others. Additionally this paper aims to dovetail that a critical mass of skilled manpower along the entire value-chain or scope of nuclear power sector covering planning, construction, manufacturing, commissioning, operation and maintenance and decommissioning must be trained to implement the related tasks required to support NPP competently. Thus, it is within this context, that this paper will outline best practices in nuclear education and training offered by the United Kingdom and France which trains students, professionals, technicians as well as craftsmen not only for employment in a nuclear power plant but also for supporting the nuclear policy formulation in Government Agencies and for supporting nuclear power industry sectors including engineering, construction, manufacturing and services. This paper will offer recommendations for enhancing cooperation in nuclear education and training aimed at building

  4. In core reload design for cycle 4 of Daya Bay nuclear power station both units

    International Nuclear Information System (INIS)

    Zhang Zongyao; Liu Xudong; Xian Chunyu; Li Dongsheng; Zhang Hong; Liu Changwen; Rui Min; Wang Yingming; Zhao Ke; Zhang Hong; Xiao Min

    1998-01-01

    The basic principles and the contents of the reload design for Daya Bay nuclear power station are briefly introduced. The in core reload design results, and the comparison between the calculated values and the measured values of both units the fourth cycle are also given. The reload design results of the two units satisfy all the economic requirements and safety criteria. The experimented results shown that the predicated values are tally good with all the measurement values

  5. Ultimate disposition of aluminum clad spent nuclear fuel in the United States

    International Nuclear Information System (INIS)

    Messick, C.E.; Clark, W.D.; Clapper, M.; Mustin, T.P.

    2001-01-01

    Treatment and disposition of spent nuclear fuel (SNF) in the United States has changed significantly over the last decade due to change in world climate associated with nuclear material. Chemical processing of aluminum based SNF is ending and alternate disposition paths are being developed that will allow for the ultimate disposition of the enriched uranium in this SNF. Existing inventories of aluminum based SNF are currently being stored primarily in water-filled basins at the Savannah River Site (SRS) while these alternate disposition paths are being developed and implemented. Nuclear nonproliferation continues to be a worldwide concern and it is causing a significant influence on the development of management alternatives for SNF. SRS recently completed an environmental impact statement for the management of aluminum clad SNF that selects alternatives for all of the fuels in inventory. The U.S. Department of Energy and SRS are now implementing a dual strategy of processing small quantities of 'problematic' SNF while developing an alternative technology to dispose of the remaining aluminum clad SNF in the proposed monitored geologic repository. (author)

  6. Communications Received from the United States of America Regarding the Supply of Nuclear Material Through the Agency

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1975-08-29

    On 17 April 1975 the Director General received a letter dated 15 April from the Resident Representative of the United States of America to the Agency providing information in connection with contracts and other agreements signed by or on behalf of the United States Atomic Energy Commission for the supply of nuclear material through the Agency.

  7. Upgrade of Control and Protection System of the Ignalina Nuclear Power Plant Units 1 and 2

    International Nuclear Information System (INIS)

    Wright, Ronald E.; Fletcher, Norman; Sidnev, Victor E.; Bickel, John H.; Vianello, Aldo; Pearsall, Raymond D.

    2003-01-01

    The Ignalina nuclear power plant (NPP) Units 1 and 2 are Soviet-designed, RBMK (Reaktor Bolshoi Moschnosti Kipyashchiy), channelized, large power-type reactors. The original-design electrical capacity for each unit was 1500 MW. Unit 1 began operating in 1983, and Unit 2 was started up in 1987. In 1994, the government of Lithuania agreed to accept grant support for the Ignalina NPP Safety Improvement Program with funding supplied by the Nuclear Safety Account of the European Bank for Reconstruction and Development (EBRD). As conditions for receiving this funding, the Ignalina NPP agreed to prepare a comprehensive safety analysis report that would undergo independent peer review after it was issued. The EBRD Safety Panel oversaw preparation and review of the report. In 1996, the safety analysis report for Unit 1 was completed and delivered to the EBRD. Part of the analyses covered anticipated transients without scram (ATWS). The analysis showed that some ATWS scenarios could lead to unacceptable consequences in <1 min. The EBRD Safety Panel recommended to the government of Lithuania that the Ignalina NPP develop and implement a program of compensatory measures for the control and protection system before the unit would be allowed to return to operation following its 1998 maintenance outage. A compensatory control and protection system that would mitigate the unacceptable consequences was designed, procured, manufactured, tested, and installed. The project was funded by U.S. Department of Energy

  8. Final environmental statement for Shoreham Nuclear Power Station, Unit 1: (Docket No. 50-322)

    International Nuclear Information System (INIS)

    1977-10-01

    The proposed action is the issuance of an Operating License to the Long Island Lighting Company (LILCO) for the startup and operation of the Shoreham Nuclear Power Station, Unit 1 (the plant) located on the north shore of Long Island, the State of New York, County of Suffolk, in the town of Brookhaven. The Shoreham station will employ a boiling-water reactor (BWR), which will operate at a thermal output of 2436 MW leading to a gross output of 846 MWe and a net output of about 820 MWe. The unit will be cooled by once-through flow of water from the Long Island Sound. One nuclear unit with a net capacity of 820 MWe will be added to the generating resources of the Long Island Lighting Company. This will have a favorable effect on reserve margins and provide a cost savings of approximately $62.1 million (1980 dollars) in production costs in 1980 if the unit comes on line as scheduled; additional cost savings will be realized in subsequent years. Approximately 100 acres (40 hectares) of the 500-acre (202-hectare) site of rural (mostly wooded) land owned by the applicant have been cleared. Most of this will be unavailable for other uses during at least the 40-year life of the plant. No offsite acreage has been or will be cleared. Land in the vicinity of the site has undergone some residential development that is typical for all of this area of Long Island. The operation of Shoreham Unit 1 will have insignificant impacts on this and other types of land uses in the vicinity of the site. 33 figs., 56 tabs

  9. A comparison between regulation of nuclear power in Canada and the United States

    International Nuclear Information System (INIS)

    Ahearne, J.F.

    1988-01-01

    The agencies that regulate commercial nuclear power in Canada and the United States differ in five significant characteristics: size and responsibility; use of legalism and formality; inspection and enforcement approaches; relationships to the government, public and industry; and the basic philosophy of regulation. Examination shows strengths and weaknesses in each approach, tied to basic differences in philosophy of government. (author)

  10. Nuclear design report for Kori nuclear power plant unit 1, cycle 14

    Energy Technology Data Exchange (ETDEWEB)

    Park, Chan Oh; Kim, Joo Young; Park, Sang Yoon; Song, Jae Woong; Lee, Chong Chul; Baik, Joo Hyun [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1994-06-01

    This report presents nuclear design calculations for cycle 14 of Kori unit 1. Information is given on fuel loading, power density distributions, reactivity coefficients, control rod worths and operational limits. In addition, the report contains all necessary data for the startup tests including predicted values for the comparison with the measured data. The reload consists of 44 KOFA`s enriched by nominally 3.70 w/o U{sub 235}. Among the KOFA`s, 16 fuel assemblies contain gadolinia rods. The fuel assemblies in the core are arranged in a low leakage loading pattern. The cycle length of cycle 14 amounts to 366 EFPD corresponding to a cycle burnup of 13680 MWD/MTU. (Author) 8 refs., 55 figs., 16 tabs. nozzle by vortex formation during mid-loop operation condition are experimentally investigated. The critical submergence is determined for various types of suction nozzle, and the measurements of velocity distribution are performed in the flow fields near the t-shaped suction nozzle. (Author) 11 refs., 41 figs., 13 tabs.

  11. The United Kingdom Law on the authorisation of nuclear power stations

    International Nuclear Information System (INIS)

    Savinson, R.

    1977-01-01

    This paper explains the requirements of the law of the United Kingdom as to the authorisations needed to construct and operate nuclear power plants in Great Britain. For simplicity, the texts referred to apply to England and Wales, Scottish law differing in detail but not in principle. Implementation of this legal system is studied in particular from the viewpoint of the Central Electricity Generating Board (CEGB) which is at present the body exclusively responsible for generating and supplying electricity in England and Wales. (NEA) [fr

  12. Nuclear Regulatory Commission issuances. Volume 17, No. 3

    International Nuclear Information System (INIS)

    1983-03-01

    This report contains the Issuances received during March 1983 from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors Decisions (DD), and the Denials of Petition for Rulemaking (DPRM). The Issuances concerned the following facilities: Three Mile Island Nuclear Station, Unit No. 1; Comanche Peak Steam Electric Station, Units 1 and 2; Vallecitos Nuclear Center; Floating Nuclear Power Plants; San Onofre Nuclear Generating Station, Units 2 and 3; Point Beach Nuclear Plant, Unit 1; Perry Nuclear Power Plant, Units 1 and 2; Shoreham Nuclear Power Station, Unit 1; Western New York Nuclear Service Center; Limerick Generating Station, Units 1 and 2; Seabrook Station, Units 1 and 2; Black Fox Station, Units 1 and 2; WmH Zimmer Nuclear Power Station, Unit 1; WPPSS Nuclear Project No. 1; Zion Nuclear Plant, Units 1 and 2; and South Texas Project, Units 1 and 2

  13. Review of nuclear liability compensation systems applicable to reactors outside the United States

    International Nuclear Information System (INIS)

    McIntosh, C.

    1985-01-01

    The review, which summarizes the Paris Convention and the Brussels Supplementary Convention, as well as the laws of Canada, France, Federal Republic of Germany, Japan, Spain, Sweden, Switzerland, and the United Kingdom, notes that the Price-Anderson program has a number of common points with the laws of Western Europe. The points of similarly are the goal of ensuring simple and equitable compensation for victims without burdening the nuclear industry with an uneconomic load. Price-Anderson differs in the higher amounts fixed for nuclear operators' liability, although the limits are now closer together. The purpose of the comparisons is to help those concerned with US programs of third-party liability and indemnification with a broader perspective

  14. United States Program on Spent Nuclear Fuel and High-Level Radioactive Waste Management

    International Nuclear Information System (INIS)

    Stewart, L.

    2004-01-01

    The President signed the Congressional Joint Resolution on July 23, 2002, that designated the Yucca Mountain site for a proposed geologic repository to dispose of the nation's spent nuclear fuel (SNF) and high-level radioactive waste (HLW). The United States (U.S.) Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM) is currently focusing its efforts on submitting a license application to the U.S. Nuclear Regulatory Commission (NRC) in December 2004 for construction of the proposed repository. The legislative framework underpinning the U.S. repository program is the basis for its continuity and success. The repository development program has significantly benefited from international collaborations with other nations in the Americas

  15. The United States foreign research reactor spent nuclear fuel acceptance program: Proposal to modify the program

    International Nuclear Information System (INIS)

    Messick, C.E.

    2005-01-01

    The United States Department of Energy (DOE), in consultation with the Department of State (DOS), adopted the Nuclear Weapons Nonproliferation Policy Concerning Foreign Research Reactor Spent Nuclear Fuel in May 1996. The policy was slated to expire in May 2009. However, in October 2003, a petition requesting a program extension was delivered to the United States Secretary of Energy from a group of research reactor operators from foreign countries. In April 2004, the Secretary directed DOE undertake an analysis, as required by the National Environmental Policy Act (NEPA), to consider potential extension of the Program. On December 1, 2004, a Federal Register Notice was issued approving the program extension. This paper discusses the findings from the NEPA analysis and the potential changes in the program that may result from implementation of the proposed changes. (author)

  16. Safety evaluation report related to the operation of Diablo Canyon Nuclear Power Plant, Units 1 and 2 (Docket Nos. 50-275 and 50-323)

    International Nuclear Information System (INIS)

    1983-12-01

    Supplement 20 to the Safety Evaluation Report for Pacific Gas and Electric Company's application for licenses to operate Diablo Canyon Nuclear Power Plant, Unit 1 and Unit 2 (Docket Nos. 50-275 and 50-323), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports on the verification effort for Diablo Canyon Unit 1 that was performed between November 1981 and the present in response to Commission Order CLI-81-30 and an NRC letter of November 19, 1981 to the licensee. Specifically, Supplement 20 addresses those issues and other matters identified in Supplements 18 and 19 that must be resolved prior to Unit 1 achieving criticality and operating at power levels up to 5% of rated full power. This SER Supplement applies only to Diablo Canyon Unit 1

  17. The unit cost factors and calculation methods for decommissioning - Cost estimation of nuclear research facilities

    International Nuclear Information System (INIS)

    Kwan-Seong Jeong; Dong-Gyu Lee; Chong-Hun Jung; Kune-Woo Lee

    2007-01-01

    Available in abstract form only. Full text of publication follows: The uncertainties of decommissioning costs increase high due to several conditions. Decommissioning cost estimation depends on the complexity of nuclear installations, its site-specific physical and radiological inventories. Therefore, the decommissioning costs of nuclear research facilities must be estimated in accordance with the detailed sub-tasks and resources by the tasks of decommissioning activities. By selecting the classified activities and resources, costs are calculated by the items and then the total costs of all decommissioning activities are reshuffled to match with its usage and objectives. And the decommissioning cost of nuclear research facilities is calculated by applying a unit cost factor method on which classification of decommissioning works fitted with the features and specifications of decommissioning objects and establishment of composition factors are based. Decommissioning costs of nuclear research facilities are composed of labor cost, equipment and materials cost. Of these three categorical costs, the calculation of labor costs are very important because decommissioning activities mainly depend on labor force. Labor costs in decommissioning activities are calculated on the basis of working time consumed in decommissioning objects and works. The working times are figured out of unit cost factors and work difficulty factors. Finally, labor costs are figured out by using these factors as parameters of calculation. The accuracy of decommissioning cost estimation results is much higher compared to the real decommissioning works. (authors)

  18. Personnel involved in the development of nuclear standards in the United States, 1975

    International Nuclear Information System (INIS)

    Johnson, E.B.

    1976-05-01

    The development of voluntary nuclear standards in the United States is an active and necessary endeavor of the technical community concerned with the safe, orderly, and economic development of the nuclear potential. There are almost 8000 people presently involved either in writing voluntary standards and codes or in the management and processing roles necessary for their approval and promulgation. This document records the current participation of these people as member, chairman, or secretary of about 900 identified committees and projects. The standards projects are identified with the organizations that are responsible for the preparation, review, and maintenance of the standards and that provide support through supervisory committees and headquarters staff. The Directory has four major sections: personnel, employers, committees, and a KWIC Index of committee titles. The Directory can be used to identify those nuclear standards projects currently active, to indicate the participation of employers, and to recognize the contributions of individuals to these often interdisciplinary activities

  19. Personnel involved in the development of nuclear standards in the United States, 1976

    International Nuclear Information System (INIS)

    Johnson, E.B.

    1977-03-01

    The development of voluntary nuclear standards in the United States is an active and necessary endeavor of the technical community concerned with the safe, orderly, and economic development of the nuclear potential. There are almost 8000 people presently involved either in writing voluntary standards and codes or in the management and processing roles necessary for their approval and promulgation. This document records the current participation of these people as member, chairman, or secretary of about 900 identified committees and projects. The standards projects are identified with the organizations that are responsible for the preparation, review, and maintenance of the standards and that provide support through supervisory committees and headquarters staff. The directory has four major sections: personnel, employers, committees, and a KWIC index of committee titles. The directory can be used to identify those nuclear standards projects currently active, to indicate the participation of employers, and to recognize the contributions of individuals to these often interdisciplinary activities

  20. Personnel involved in the development of nuclear standards in the United States, 1976

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, E.B. (ed.)

    1977-03-01

    The development of voluntary nuclear standards in the United States is an active and necessary endeavor of the technical community concerned with the safe, orderly, and economic development of the nuclear potential. There are almost 8000 people presently involved either in writing voluntary standards and codes or in the management and processing roles necessary for their approval and promulgation. This document records the current participation of these people as member, chairman, or secretary of about 900 identified committees and projects. The standards projects are identified with the organizations that are responsible for the preparation, review, and maintenance of the standards and that provide support through supervisory committees and headquarters staff. The directory has four major sections: personnel, employers, committees, and a KWIC index of committee titles. The directory can be used to identify those nuclear standards projects currently active, to indicate the participation of employers, and to recognize the contributions of individuals to these often interdisciplinary activities.

  1. Personnel involved in the development of nuclear standards in the United States, 1975

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, E.B. (ed.)

    1976-05-01

    The development of voluntary nuclear standards in the United States is an active and necessary endeavor of the technical community concerned with the safe, orderly, and economic development of the nuclear potential. There are almost 8000 people presently involved either in writing voluntary standards and codes or in the management and processing roles necessary for their approval and promulgation. This document records the current participation of these people as member, chairman, or secretary of about 900 identified committees and projects. The standards projects are identified with the organizations that are responsible for the preparation, review, and maintenance of the standards and that provide support through supervisory committees and headquarters staff. The Directory has four major sections: personnel, employers, committees, and a KWIC Index of committee titles. The Directory can be used to identify those nuclear standards projects currently active, to indicate the participation of employers, and to recognize the contributions of individuals to these often interdisciplinary activities.

  2. Analysis of the Radio-Ecological State of Units and Installations Involved in Nuclear Submarine Decommissioning in the Northwest Region of Russia

    National Research Council Canada - National Science Library

    Sarkissov, A

    2003-01-01

    .... in the first section of the report, all nuclear-powered units and installations involved in the process of nuclear submarine utilization in the northwest region of Russia are listed and considered in detail...

  3. Nuclear safety inspection in treatment process for SG heat exchange tubes deficiency of unit 1, TNPS

    International Nuclear Information System (INIS)

    Zhang Chunming; Song Chenxiu; Zhao Pengyu; Hou Wei

    2006-01-01

    This paper describes treatment process for SG heat exchange tubes deficiency of Unit 1, TNPS, nuclear safety inspection of Northern Regional Office during treatment process for deficiency and further inspection after deficiency had been treated. (authors)

  4. Nuclear Regulatory Commission issuances, March 1975

    International Nuclear Information System (INIS)

    1975-04-01

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

  5. 'Kazmer' a complex noise diagnostic system for 1000 MWe PWR WWER type nuclear power units

    International Nuclear Information System (INIS)

    Por, G.

    1992-06-01

    Noise diagnostic systems have previously been developed and installed for the WWER-440 type reactors at the Paks Nuclear Power Plant, Hungary. Based on the experiences, the system has been extended and modified for use in 1000 MWe, WWER-1000 type units. KAZMER consists of three subsystem, the KARD reactor noise diagnostic system, ARGUS vibration monitoring system for rotation machinery, and ALMOS acoustic monitoring system. The installation of the KAZMER system at the Kalinin Nuclear Power Station, Russia, and the first operational experiences are outlined. (R.P.) 15 refs.; 9 figs

  6. Use mobile pumps and liquid chilling water units to provide chilled water for nuclear reactor during nuclear power plant accident

    International Nuclear Information System (INIS)

    Zhang Guobin; Feng Jiaxuan

    2012-01-01

    From the nuclear accident in Japan Fuksuhima in March this year, despite a shut down of the reactor, the residue heat inside the reactor was not able to remove due to the failure of the cooling system and it finally caused the catastrophe. It was observed that when the failure of the cooling system after an earthquake of magnitude 9 and a tsunami of 28 meters height, the containment vessel for the reactor core was still able to maintain its integrity in the first 24 hours before the first explosion was happened. A backup emergency heat removal system for nuclear power plants using mo- bile pumps and liquid chilling units has been proposed 20 years ago by Cheung [Ref. 1]. Due to the fact that there are more than 400 nuclear power plants around the world and 10% of them are located in earthquake active zone, together with the aging of some of the power plants which were built more than 30 years ago, the risk of another nuclear accident becomes high. An emergency safety measure has to be designed in order to deal with the unforeseen scenario. This re- port re-visits the proposal again; to re-design to the suit the need and to integrate with the current situation of the nuclear industry. (authors)

  7. A regulatory view of the seismic assessment of existing nuclear structures in the United Kingdom

    International Nuclear Information System (INIS)

    Inkester, J.E.

    2001-01-01

    The paper describes the background to the seismic assessment of existing nuclear structures in the United Kingdom. Nuclear installations in this country were not designed specifically to resist earthquakes until the nineteen-seventies, although older plants were robustly constructed. The seismic capability of these older installations is now being evaluated as part of the periodic safety reviews which nuclear licensees are required to carry out. The regulatory requirements which set the framework for these studies are explained. The licensees' processes of hazard appraisal and examination of the response of the structure are briefly summarized. Regulatory views on some of the criteria used to judge the adequacy of safety are discussed. Finally the paper provides some comments on future initiatives and possible areas of development. (author)

  8. Probabilistic fire risk assessment for Koeberg Nuclear Power Station Unit 1

    International Nuclear Information System (INIS)

    Grobbelaar, J.F.; Foster, N.A.S.; Luesse, L.J.

    1995-01-01

    A probabilistic fire risk assessment was done for Koeberg Nuclear Power Station Unit 1. Areas where fires are likely to start were identified. Equipment important to safety, as well as their power and/or control cable routes were identified in each fire confinement sector. Fire confinement sectors where internal initiating events could be caused by fire were identified. Detection failure and suppression failure fault trees and event trees were constructed. The core damage frequency associated with each fire confinement sector was calculated, and important fire confinement sectors were identified. (author)

  9. Fuzzy algorithm for an automatic reactor power control in a PWR

    International Nuclear Information System (INIS)

    Hah, Yung Joon; Song, In Ho; Yu, Sung Sik; Choi, Jung In; Lee, Byong Whi

    1994-01-01

    A fuzzy algorithm is presented for automatic reactor power control in a pressurized water reactor. Automatic power shape control is complicated by the use of control rods because it is highly coupled with reactivity compensation. Thus, manual shape controls are usually employed even for the limited capability for the load - follow operation including frequency control. In an attempt to achieve automatic power shape control without any design modification of the core, a fuzzy power control algorithm is proposed. For the fuzzy control, the rule base is formulated based on a multi - input multi - output system. The minimum operation rule and the center of area method are implemented for the development of the fuzzy algorithm. The fuzzy power control algorithm has been applied to the Yonggwang Nuclear Unit 3. The simulation results show that the fuzzy control can be adapted as a practical control strategy for automatic reactor power control of the pressurized water reactor during the load - follow operation

  10. Fuzzy power control algorithm for a pressurized water reactor

    International Nuclear Information System (INIS)

    Hah, Y.J.; Lee, B.W.

    1994-01-01

    A fuzzy power control algorithm is presented for automatic reactor power control in a pressurized water reactor (PWR). Automatic power shape control is complicated by the use of control rods with a conventional proportional-integral-differential controller because it is highly coupled with reactivity compensation. Thus, manual shape controls are usually employed even for the limited capability needed for load-following operations including frequency control. In an attempt to achieve automatic power shape control without any design modifications to the core, a fuzzy power control algorithm is proposed. For the fuzzy control, the rule base is formulated based on a multiple-input multiple-output system. The minimum operation rule and the center of area method are implemented for the development of the fuzzy algorithm. The fuzzy power control algorithm has been applied to Yonggwang Nuclear Unit 3. The simulation results show that the fuzzy control can be adapted as a practical control strategy for automatic reactor power control of PWRs during the load-following operations

  11. Inferential smart sensing for feedwater flowrate in PWRs

    International Nuclear Information System (INIS)

    Na, M. G.; Hwang, I. J.; Lee, Y. J.

    2006-01-01

    The feedwater flowrate that is measured by Venturi flow meters in most pressurized water reactors can be over-measured because of the fouling phenomena that make corrosion products accumulate in the Venturi meters. Therefore, in this work, two kinds of methods, a support vector regression method and a fuzzy modeling method, combined with a sequential probability ratio test, are used in order to accurately estimate online the feedwater flowrate, and also to monitor the status of the existing hardware sensors. Also, the data for training the support vector machines and the fuzzy model are selected by using a subtractive clustering scheme to use informative data from among all acquired data. The proposed inferential sensing and monitoring algorithm is verified by using the acquired real plant data of Yonggwang Nuclear Power Plant Unit 3. In the simulations, it was known that the root mean squared error and the relative maximum error are so small and the proposed method early detects the degradation of an existing hardware sensor. (authors)

  12. Analysis methodology for the post-trip return to power steam line break event

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Chul Shin; Kim, Chul Woo; You, Hyung Keun [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1996-06-01

    An analysis for Steam Line Break (SLB) events which result in a Return-to-Power (RTP) condition after reactor trip was performed for a postulated Yonggwang Nuclear Power Plant Unit 3 cycle 8. Analysis methodology for post-trip RTP SLB is quite different from that of non-RTP SLB and is more difficult. Therefore, it is necessary to develop a methodology to analyze the response of the NSSS parameters to the post-trip RTP SLB events and the fuel performance after the total reactivity exceeds the criticality. In this analysis, the cases with and without offsite power were simulated crediting 3-D reactivity feedback effect due to a local heatup in the vicinity of stuck CEA and compared with the cases without 3-D reactivity feedback with respect to post-trip fuel performance. Departure-to Nucleate Boiling Ratio (DNBR) and Linear Heat Generation Rate (LHGR). 36 tabs., 32 figs., 11 refs. (Author) .new.

  13. Internal event analysis of Laguna Verde Unit 1 Nuclear Power Plant. System Analysis

    International Nuclear Information System (INIS)

    Huerta B, A.; Aguilar T, O.; Nunez C, A.; Lopez M, R.

    1993-01-01

    The Level 1 results of Laguna Verde Nuclear Power Plant PRA are presented in the I nternal Event Analysis of Laguna Verde Unit 1 Nuclear Power Plant , CNSNS-TR-004, in five volumes. The reports are organized as follows: CNSNS-TR-004 Volume 1: Introduction and Methodology. CNSNS-TR-004 Volume 2: Initiating Event and Accident Sequences. CNSNS-TR-004 Volume 3: System Analysis. CNSNS-TR-004 Volume 4: Accident Sequence Quantification and Results. CNSNS-TR-004 Volume 5: Appendices A, B and C. This volume presents the results of the system analysis for the Laguna Verde Unit 1 Nuclear Power Plant. The system analysis involved the development of logical models for all the systems included in the accident sequence event tree headings, and for all the support systems required to operate the front line systems. For the Internal Event analysis for Laguna Verde, 16 front line systems and 5 support systems were included. Detailed fault trees were developed for most of the important systems. Simplified fault trees focusing on major faults were constructed for those systems that can be adequately represent,ed using this kind of modeling. For those systems where fault tree models were not constructed, actual data were used to represent the dominant failures of the systems. The main failures included in the fault trees are hardware failures, test and maintenance unavailabilities, common cause failures, and human errors. The SETS and TEMAC codes were used to perform the qualitative and quantitative fault tree analyses. (Author)

  14. Safety Evaluation Report related to the operation of Diablo Canyon Nuclear Power Plant, Units 1 and 2 (Docket Nos. 50-275 and 50-323)

    International Nuclear Information System (INIS)

    1984-07-01

    Supplement 27 to the Safety Evaluation Report for Pacific Gas and Electric Company's application for a license to operate Diablo Canyon Nuclear Power Plant, Unit 1 (Docket No. 50-275), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement addresses the revisions to the license conditions and to the Technical Specifications as they relate to Amendment 10 to Diablo Canyon, Unit 1 Facility Operating License, DPR-76

  15. Analysis of internal events for the Unit 1 of the Laguna Verde Nuclear Power Station. Appendixes

    International Nuclear Information System (INIS)

    Huerta B, A.; Lopez M, R.

    1995-01-01

    This volume contains the appendices for the accident sequences analysis for those internally initiated events for Laguna Verde Unit 1, Nuclear Power Plant. The appendix A presents the comments raised by the Sandia National Laboratories technical staff as a result of the review of the Internal Event Analysis for Laguna Verde Unit 1 Nuclear Power Plant. This review was performed during a joint Sandia/CNSNS multi-day meeting by the end 1992. Also included is a brief evaluation on the applicability of these comments to the present study. The appendix B presents the fault tree models printed for each of the systems included and.analyzed in the Internal Event Analysis for LVNPP. The appendice C presents the outputs of the TEMAC code, used for the cuantification of the dominant accident sequences as well as for the final core damage evaluation. (Author)

  16. Analysis of internal events for the Unit 1 of the Laguna Verde Nuclear Power Station. Appendixes

    International Nuclear Information System (INIS)

    Huerta B, A.; Lopez M, R.

    1995-01-01

    This volume contains the appendices for the accident sequences analysis for those internally initiated events for Laguna Verde Unit 1, Nuclear Power Plant. The appendix A presents the comments raised by the Sandia National Laboratories technical staff as a result of the review of the Internal Event Analysis for Laguna Verde Unit 1 Nuclear Power Plant. This review was performed during a joint Sandia/CNSNS multi-day meeting by the end 1992. Also included is a brief evaluation on the applicability of these comments to the present study. The appendix B presents the fault tree models printed for each of the systems included and analyzed in the Internal Event Analysis for LVNPP. The appendice C presents the outputs of the TEMAC code, used for the cuantification of the dominant accident sequences as well as for the final core damage evaluation. (Author)

  17. Application of flow-controllable accumulator and performance analysis in Korean Nuclear Power Plants

    International Nuclear Information System (INIS)

    Jung, Byung-Ryul; Lee, Un-Chul

    1997-01-01

    The Korean Yonggwang Nuclear Power Plants 3 ampersand 4(YGN 3 ampersand 4) are the two-loop pressurized water reactor (PWR) nuclear steam supply systems, rated at 2,815 MW(thermal). They incorporate the safety injection system (SIS) consisting of the two high pressure (HPSI) pumps, two low pressure safety injection (LPSI) pumps, and four accumulators. The SIS is two headered arrangements, each to four cold legs injection (CLI) type which provides cooling to the core in the highly unlikely event of a loss-of-coolant accident (LOCA). In the current SIS, the LPSI pumps automatically start during a LOCA, and also provide the residual heat removal capability during the shutdown cooling. This paper presents the feasibility of the removal of the LPSI from the existing SIS with minor system changes, including the increase up to four in the HPSI pumps, direct vessel injection(DVI), and the flow-controllable accumulators. A double-ended rupture of one of the four cold legs in the YGN 3 ampersand 4 was simulated using RELAP5/MOD3.1 to determine the feasibility of the application of this new SIS design to the current nuclear power plants. As a result, the calculated reflooding peak cladding surface temperature(PCT) was comparable to that of original base calculation, and the downcomer and the core collapsed liquid level during reflooding were also comparable to those in the current safety system design. This large break, cold-leg LOCA analysis addresses the reflooding capability without credit for a LPSI pump system and the applicability of the new flow-controllable accumulator. Also this analysis confirms that the combination of new flow-controllable accumulators, DVI and the increased HPSI pumps maintain the peak cladding temperature below the prescribed limits. 14 refs., 4 figs., 3 tabs

  18. Nuclear energy policy in the United States 1990–2010: A federal or state responsibility?

    International Nuclear Information System (INIS)

    Heffron, Raphael J.

    2013-01-01

    This paper examines from a policy perspective nuclear energy policy in the United States (US) from 1990 to 2010 and questions whether it is or has become a Federal or State responsibility. The present study, as befits policy research, engages with many disciplines (for example, in particular, law and politics) and hence the contributions move beyond that of nuclear energy policy literature and in particular to that on nuclear new build and other assessments of large infrastructure projects. Several examples at the Federal level are identified that demonstrate that the nuclear industry has evolved to a stage where it requires a focus on the power of actions at a more localised (state) level in order to re-ignite the industry. The research concludes that there remains a misunderstanding of the issue of project management for complex construction projects, and it is highly arguable whether many of its issues have been resolved. Further, the research asserts that the economics of nuclear energy are not the most influential reason for no nuclear new build in the US. -- Highlights: •Examines the US nuclear energy sector, 1990–2010. •Nuclear industry has evolved to a stage where an individual state is the key driver. •Misunderstanding of the project management and public administration. •Potential of the power of more localised (state) actions to re-ignite the industry

  19. Selection of a new nuclear unit for Slovakia: possibilities and key technical issues

    International Nuclear Information System (INIS)

    Misak, J.

    2009-01-01

    Plans for construction of new nuclear unit at Jaslovske Bohunice brings forward the issue of selection of reactor design. This paper compares technical characteristics (safety and operational) of pressurized water reactors that are at present available in the market, such as AP 1000 (WEC), EPR (AREVA), AES 2006 (ASE), APWR 1700 (Mitsubishi) and APR 1400 (Korea Hydro and Nuclear). Selected parameters that require close attention in future negotiations with potential suppliers are discussed in detail. Compared are parameters as type of the reactor, reactor output power, quantified level of safety, compliance with national legislature and international safety requirements, operational flexibility in meeting requirements of the grid, using of verified technology, measures for coping with severe accidents, resistance against extreme external conditions etc. (authors)

  20. Evaluation of DNBR calculation methods for advanced digital core protection system

    International Nuclear Information System (INIS)

    Ihn, W. K.; Hwang, D. H.; Pak, Y. H.; Yoon, T. Y.

    2003-01-01

    This study evaluated the on-line DNBR calculation methods for an advanced digital core protection system in PWR, i.e., subchannel analysis and group-channel analysis. The subchannel code MATRA and the four-channel codes CETOP-D and CETOP2 were used here. CETOP2 is most simplified DNBR analysis code which is implemented in core protection calculator in Korea standard nuclear power plants. The detailed subchannel code TORC was used as a reference calculation of DNBR. The DNBR uncertainty and margin were compared using allowable operating conditions at Yonggwang nuclear units 3-4. The MATRA code using a nine lumping-channel model resulted in smaller mean and larger standard deviation of the DNBR error distribution. CETOP-D and CETOP2 showed conservatively biased mean and relatively smaller standard deviation of the DNBR error distribution. MATRA and CETOP-D w.r.t CETOP2 showed significant increase of the DNBR available margin at normal operating condition. Taking account for the DNBR uncertainty, MATRA and CETOP-D over CETOP2 were estimated to increase the DNBR net margin by 2.5%-9.8% and 2.5%-3.3%, respectively

  1. An evaluation on the design optimization of large capacity tanks in the chemical and volume control system for YGN 3 and 4

    International Nuclear Information System (INIS)

    Park, Byung Ho; Kim, Eun Ki; Ko, Deuk Yoon; Ko, Yong Sang; Kim, Seok Bum

    1996-06-01

    The design of Yonggwang nuclear power plant units 3 and 4 (YGN 3 and 4) is referenced to that of Palo Verde nuclear power plant (Palo Verde NPP) in Arizona, USA. The reactor vessel and steam generator of YGN 3 and 4 are smaller than that of Palo Verde NPP because Palo Verde NPP produces 1,300 Mw electricity, on the other hand, YGN 3 and 4 produces 1,000 Mw electricity. However, other components and systems of YGN 3 and 4 are the same as those of Palo verde NPP. The oversized system components may be considered to ensure the safety and operability by providing sufficient design margin, but it requires unnecessary cost burden to the owner of the plant. This report focuses on the optimization of the volume of the large tanks (i.e., above 400,000 gallons) in CVCS. These tanks are refueling water tank (RWT), reactor makeup water tank (RMWT) and holdup tank (HT). It has been performed that the calculation on the required tank volume based on design requirements, comparison on the calculation results with as-built design, and estimation on the instrumentation setpoint. 19 tabs., 12 figs., 13 refs. (Author)

  2. Nuclear Regulatory Commission Issuances, August 1981

    International Nuclear Information System (INIS)

    1981-01-01

    Contents include: Issuances of the Nuclear Regulatory Commission--Metropolitan Edison Company (Three Mile Island Nuclear Station, Unit No. 1), Metropolitan Edison Company, et al. (Three Mile Island Nuclear Station, Unit 1), Westinghouse Electric Corp. (Export of LEU to the Philippines); Issuances of Atomic Safety and Licensing Appeal Boards--Duke Power Company (Amendment to Materials License SNM-1773--Transportation of Spent Fuel from Oconee Nuclear Station for Storage at McGuire Nuclear Station); Issuances of the Atomic Safety Licensing Boards--Commonwealth Edison Company (Byron Station, Units 1 and 2), Dairyland Power Cooperative (La Crosse Boiling Water Reactor, Operating License and Show Cause), Florida Power and Light Company (St. Lucie Plant, Unit No. 2), Florida Power and Light Company (Turkey Point Nuclear Generating, Units 3 and 4), Metropolitan Edison Company (Three Mile Island Nuclear Station, Unit 1) Pacific Gas and Electric Company (Diablo Canyon Nuclear Power Plant, Units 1 and 2), The Regents of the University of California (UCLA Research Reactor), The Toledo Edison Company, et al. (Davis-Besse Nuclear Power Station, Units 2 and 3: Terminiation of Proceedings); Issuances of the Directors Denial--Florida Power and Light Company

  3. Nuclear containment systems and in-service inspection status of Korea nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Jihong, Park; Jaekeun, Hong; Banuk, Park [Korea Institute of Machinery and Materials, Dept. of Authorized Test and Evaluation, Kyungnam (Korea, Republic of)

    2007-07-01

    20 unit nuclear power plants in Korea have been operated and maintained since the first unit started in commercial service in 1978. Most recently 4 units were under construction and several units were planned to be constructed. by industries. 4 types of nuclear containment systems have been constructed until now: first, metal containments, then pre-stressed concrete containments with grouted tendon systems, followed by pre-stressed concrete containments with un-grouted tendon systems, and Korea standard nuclear containments. All the nuclear containments should be inspected periodically. Therefore for periodic in-service inspection, several appropriate technical requirements should be applied differently depending on the specific nuclear containment types. With the changes of times, nuclear containment systems have undergone a remarkable change, and finally nuclear containment system of Korea standard nuclear power plant was settled down, and as a matter of course it dominates the trend of present and future nuclear containment systems. Overall in-service inspection results of most Korea nuclear containments have not showed any serious evidence of degradation.

  4. Summary of the engineering assessment of inactive uranium mill tailings: Phillips/United Nuclear site, Ambrosia Lake, New Mexico

    International Nuclear Information System (INIS)

    1981-10-01

    Ford, Bacon and Davis Utah, Inc., has reevaluated the Phillips/United Nuclear site in order to revise the December 1977 engineering assessment of the problems resulting from the existence of radioactive uranium mill tailings at Ambrosia Lake, New Mexico. This engineering assessment has included the preparation of topographic maps, the performance of core drillings and radiometric maps, the performance of core drillings and radiometric measurements sufficient to determine areas and volumes of tailings and radiation exposures of individuals and nearby populations, the investigations of site hydrology and meteorology, and the evaluation and costing of alternative corrective actions. Radon gas released from the 2.6 million dry tons of tailings at the Phillips/United Nuclear site constitutes the most significant environmental impact, although windblown tailings and external gamma radiation also are factors. The four alternative actions presented in this engineering assessment range from millsite decontamination with the addition of 3 m of stabilization cover material, to removal of the tailings to remote disposal sites and decontamination of the tailings site. Cost estimates for the four options range from about $21,500,000 for stabilization in-place, to about $45,200,000 for disposal at a distance of about 15 mi. Three principal alternatives for the reprocessing of the Phillips/United Nuclear tailings were examined: heap leaching; treatment at an existing mill; reprocessing at a new conventional mill constructed for tailings reprocessing. The cost of the uranium recovered would be about $87/lb of U 3 O 8 by either heap leach or conventional plant process. The spot market price for uranium was $25/lb early in 1981. Reprocessing the Phillips/United Nuclear tailings for uranium recovery does not appear to be economically attractive under present or foreseeable market conditions

  5. Nuclear Facility Accident (NFAC) Unit Test Report For HPAC Version 6.3

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Ronald W. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Computational Sciences and Engineering Division; Morris, Robert W. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Computational Sciences and Engineering Division; Sulfredge, Charles David [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Computational Sciences and Engineering Division

    2015-12-01

    This is a unit test report for the Nuclear Facility Accident (NFAC) model for the Hazard Prediction and Assessment Capability (HPAC) version 6.3. NFAC’s responsibility as an HPAC component is three-fold. First, it must present an interactive graphical user interface (GUI) by which users can view and edit the definition of an NFAC incident. Second, for each incident defined, NFAC must interact with RTH to create activity table inputs and associate them with pseudo materials to be transported via SCIPUFF. Third, NFAC must create SCIPUFF releases with the associated pseudo materials for transport and dispersion. The goal of NFAC unit testing is to verify that the inputs it produces are correct for the source term or model definition as specified by the user via the GUI.

  6. Nuclear Facility Accident (NFAC) Unit Test Report For HPAC Version 6.3

    International Nuclear Information System (INIS)

    Lee, Ronald W.; Morris, Robert W.; Sulfredge, Charles David

    2015-01-01

    This is a unit test report for the Nuclear Facility Accident (NFAC) model for the Hazard Prediction and Assessment Capability (HPAC) version 6.3. NFAC's responsibility as an HPAC component is three-fold. First, it must present an interactive graphical user interface (GUI) by which users can view and edit the definition of an NFAC incident. Second, for each incident defined, NFAC must interact with RTH to create activity table inputs and associate them with pseudo materials to be transported via SCIPUFF. Third, NFAC must create SCIPUFF releases with the associated pseudo materials for transport and dispersion. The goal of NFAC unit testing is to verify that the inputs it produces are correct for the source term or model definition as specified by the user via the GUI.

  7. APPLICATION FEATURES OF SPATIAL CONDUCTOMETRY SENSORS IN MODELLING OF COOLANT FLOW MIXING IN NUCLEAR POWER UNIT EQUIPMENT

    Directory of Open Access Journals (Sweden)

    A. A. Barinov

    2016-01-01

    Full Text Available Coolant flow mixing processes with different temperatures and concentrations of diluted additives widely known in nuclear power units operation. In some cases these processes make essential impact on the resource and behavior of the nuclear unit during transient and emergency situations. The aim of the study was creation of measurement system and test facility to carry out basic tests and to embed spatial conductometry method in investigation practice of turbulent coolant flows. In the course of investigation measurement system with sensors and experimental facility was designed, several first tests were carried out. A special attention was dedicated to calibration and clarification of conductometry sensor application methodologies in studies of turbulent flow characteristics. Investigations involved method of electrically contrast tracer jet with concurrent flow in closed channel of round crosssection. The measurements include both averaged and unsteady realizations of measurement signal. Experimental data processing shows good agreement with other tests acquired from another measurement systems based on different physical principles. Calibration functions were acquired, methodical basis of spatial conductometry measurement system application was created. Gathered experience of spatial sensor application made it possible to formulate the principles of further investigation that involve large-scale models of nuclear unit equipment. Spatial wire-mesh sensors proved to be a perspective type of eddy resolving measurement devices.

  8. Promoting Safe, Secure, and Peaceful Growth of Nuclear Energy: Next Steps for Russia and the United States

    OpenAIRE

    Bunn, Matthew G.; Vyacheslav P. Kuznetzov

    2010-01-01

    Russia, the United States and other countries must cooperate to enable large-scale growth of nuclear energy around the world while achieving even higher standards of safety, security, and nonproliferation than are in place today. This will require building a new global framework for nuclear energy, including new or strengthened global institutions. The Belfer Center's Managing the Atom (MTA) Project and the Russian Research Center's Kurchatov Institute developed these and additional recommend...

  9. 75 FR 15745 - Arizona Public Service Company, et al. Palo Verde Nuclear Generating Station, Units 1, 2, and 3...

    Science.gov (United States)

    2010-03-30

    ...] Arizona Public Service Company, et al. Palo Verde Nuclear Generating Station, Units 1, 2, and 3; Exemption 1.0 Background The Arizona Public Service Company (APS, the licensee) is the holder of Facility... Generating Station (PVNGS), Units 1, 2, and 3, respectively. The licenses provide, among other things, that...

  10. Millstone Unit 1 plant vulnerabilities during postulated severe nuclear accidents

    International Nuclear Information System (INIS)

    Khalil, Y.F.

    1993-01-01

    Generic Letter 88-20, Supplement No. 1 (Ref. 1), issued by the Nuclear Regulatory Commission (NRC) requested all licensees holding operating licenses and construction permits for nuclear power reactor facilities to perform Individual Plant Examinations (IPE) of their plant(s) for severe accident vulnerabilities and to submit the results to the Commission. This paper summarizes the major Front-End (Level-1 PRA) and Back-End (Level-2 PRA) insights gained from the Millstone Unit 1 (MP-1) IPE study. No major plant vulnerabilities have been identified from a Front-End perspective. The Back-End analysis, however, has identified two potential containment vulnerabilities during postulated events that progress beyond the Design Basis Accidents (DBAs), namely, (1) MP-1 is dominated by early source term releases that would occur within a six-hour time frame from time of accident initiation, or reactor trip, and (2) MP-1 containment is somewhat vulnerable to leak-type failure through the drywell head. As a result of the second finding, a recommendation currently under evaluation, has been made to increase the drywell head bolt's preload from 54 Kips to resist the containment design pressure value (62 psig)

  11. Computation code TEP 1 for automated evaluation of technical and economic parameters of operation of WWER-440 nuclear power plant units

    International Nuclear Information System (INIS)

    Zadrazil, J.; Cvan, M.; Strimelsky, V.

    1987-01-01

    The TEP 1 program is used for automated evaluation of the technical and economic parameters of nuclear power plant units with WWER-440 reactors. This is an application program developed by the Research Institute for Nuclear Power Plants in Jaslovske Bohunice for the KOMPLEX-URAN 2M information system, delivered by the USSR to the V-2 nuclear power plants in Jaslovske Bohunice and in Dukovany. The TEP 1 program is written in FORTRAN IV and its operation has two parts. First the evaluation of technical and economic parameters of operation for a calculation interval of 10 mins and second, the control of the calculation procedure, follow-up on input data, determination of technical and economic parameters for a lengthy time interval, and data printout and storage. The TEP 1 program was tested at the first unit of the V-2 power plant and no serious faults appeared in the process of the evaluation of technical and economic parameters. A modification of the TEP 1 programme for the Dukovany nuclear power plant is now being tested on the first unit of the plant. (Z.M.)

  12. Safety evaluation report related to the operation of Millstone Nuclear Power Station, Unit No. 3 (Docket No. 50-423). Supplement No. 5

    International Nuclear Information System (INIS)

    1986-01-01

    This report supplements the Safety Evaluation Report (NUREG-1031) issued in July 1984, Supplement 1 issued in March 1985, Supplement 2 issued in September 1985, Supplement 3 issued in November 1985, and Supplement 4 issued in November 1985 by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by Northeast Nuclear Energy Company (licensee and agent for the owners) for a license to operate Millstone Nuclear Power Station, Unit No. 3 (Docket 50-423). The supplement provides more recent information regarding resolution of license conditions identified in the SER. Because of the favorable resolution of the items discussed in this report, the staff concludes that Millstone Nuclear Power Station, Unit No. 3, can be operated by the licensee at power levels greater than 5% without endangering the health and safety of the public. 13 refs

  13. The civil design of the Angra Nuclear power plant, units 2 and 3

    International Nuclear Information System (INIS)

    Zuegel, L.C.; Diaz, B.E.; Cunha, M.T.

    1988-01-01

    The civil design of the Angra Nuclear Power Plant, Units 2 and 3 represents an important step in the technological development of Brazil, correlated to high technology enterprises. This design was developed in Brazil, by Brazilian technicians, in a comprehensive way. In all individual and global phases of the design, a full participation of the Brazilian state and private companies has been observed. In order to proceed with the design in this way, a group of Nuclen engineers has stayed for a while in Germany, in KWU's office, for a proper training. The Brazilian design companies, on the other hand, have received a special consulting support given by engineers of German construction companies, especialized in nuclear power plant construction. For the nuclear civil design, as well as for the dynamic analyses and structural design of reinforced concrete and steel structures, the design job assumes an important position in the Brazilian technical experience. The structural design of the reinforced concrete structures of the nuclear power plant, for instance, is the largest one ever performed in Brazil in terms of difficulty, complexity and amount of man-hours expediture. A summary of the civil design steps will be described in this paper. (author) [pt

  14. Efficient erection of a piping unit in a nuclear power station

    International Nuclear Information System (INIS)

    Halstrick, V.; Peters, G.

    1986-01-01

    In consideration of the negative experience gathered in the past extensive project logistics are required for the erection of piping units in a nuclear power station in order to be able to recognize and master the numerous influences and different marginal conditions with reasonable certainty and at an early stage. The utilization of requirements from the analysis of experience for the conception of project management begins with the erection planning and results in check lists for the execution of erection. During production planning these check lists are verified for realization. Because of the extensive data, EDP-aided systems are applied for checking and controlling the flow of information and material. A dialogue-aided system is presented for project planning and controlling which enables a transparent and farsighted execution of a project. By means of comparable piping units it is demonstrated that due to the created controlling system a great success becomes obvious in relation to the past. (orig.) [de

  15. Environmental impact assessments of a fifth nuclear power plant unit in Finland

    International Nuclear Information System (INIS)

    Aurela, Jorma; Koivisto, Katarina

    2000-01-01

    This paper presents the results of president questionnaires and media monitoring of press cuttings concerned with siting of the new fifth in a row Finnish NPP. Two years ago both Fortum Power and Heat Oy and Teollisuuden Voima Oy (TVO) launched their Environmental impact assessment (EIA) procedures of a new nuclear power unit in Finland. The EIA procedures were launched to investigate the environmental impacts of a fifth nuclear power plant which possibly will be built in Loviisa or at Olkiluoto. In Finland there are four operating NPP units, two in Loviisa (Fortum) and two in Eurajoki, Olkiluoto (TVO). In the EIA procedure citizens and various associations and authorities have an opportunity to express their views on the matters related to the project. The Ministry of Trade and Industry (MTI) as the coordination authority arranges the organisation of the EIA hearings and the collection of statements and opinions. The EIA procedure in Finland takes place in two stages. The first stage i.e. the EIA programme describes the project and presents the plan on how the environmental effects are investigated and assessed. In the second stage the actual assessment of the environmental effects of the project will be submitted. Both Fortum and Teollisuuden Voima Oy (TVO) launched in spring 1998 their EIA procedures. The main alternatives are the Loviisa 3 project includes two plant type alternatives. The size of the plant is between 1000 and 1700 MWe, and the extension project of the Olkiluoto NPP to build a NPP unit of about 1000-1500 MWe at Olkiluoto. The EIA reports were submitted to the MTI in August 1999 and after that they were on display for two months for opinions and statements

  16. Nuclear Regulatory Commission Issuances, May 81

    International Nuclear Information System (INIS)

    1981-05-01

    Contents: Issuances of the Nuclear Regulatory Commission--Consolidated Edison Company of New York, Inc. (Indian Point, Unit No. 2), Power Authority of the State of New York (Indian Point, No. 3 Nuclear Power Plant), Pacific Gas and Electric Company (Diablo Canyon Nuclear Power Plant, Units 1 and 2), Statement of Policy on Conduct of Licensing Proceedings, Uranium Mill Licensing Requirements; Issuances of Atomic Safety and Licensing Appeal Boards--Houston Lighting and Power Company, et al. (South Texas Project, Units 1 and 2), Metropolitan Edison Company, et al. (Three Mile Island Nuclear Station, Unit No. 2), Pennsylvania Power and Light Company and Allegheny Electric Cooperative, Inc. (Susquehanna Steam Electric Station, Units 1 and 2), Philadelphia Electric Company et al. (Peach Bottom Atomic Power Station, Units 2 and 3), Public Service Electric and Gas Company (Hope Creek Generating Station, Units 1 and 2); Issuances of the Atomic Safety and Licensing Boards--Duke Power Company (William B. McGuire Nuclear Station, Units 1 and 2), Florida Light and Power Company (Turkey Point Nuclear Generating, Units 3 and 4), Illinois Power Company, et al. (Clinton Power Station, Units 1 and 2), Sacramento Municipal Utility District (Rancho Seco Nuclear Generating Station); Issuances of the Directors Denial--Commonwealth Edison Company (Byron Station, Units 1 and 2), Consolidated Edison Company of New York, Inc. (Indian Point Unit No. 2), Gulf States Utilities Company (River Bend Station Units 1 and 2), Petition to Suspend All Operating Licenses for Pressurized Water Reactors (River Bend Station Units 1 and 2), Portland General Electric Company (Trojan Nuclear

  17. Immediate tasks in realization of 52-53 Sessions of United Nations Organization General Assembly resolution on Semipalatinsk nuclear test site

    International Nuclear Information System (INIS)

    Ibraev, S.

    2000-01-01

    The author points out, that ecological heritage of Semipalatinsk test site is not studied, scattered investigations does not give objective assessment about radiation situation in the region. Only operations of close down of wells on the base of inter-state agreement between Republic of Kazakhstan and the United States of America were carried out. There are following main rehabilitation measures on liquidation of nuclear tests consequences in the region: study, deactivation and re-cultivation of populated territories; study of radioactive contamination level in underground waters and definition radionuclides migration by biological chain for taking preventative measures. It is noted, that citizens of the region with gratitude took solution of 52-53 Sessions of United Nations Organization General Assembly 'On liquidation of nuclear tests consequences on Semipalatinsk nuclear test site

  18. Economics of nuclear power projects

    International Nuclear Information System (INIS)

    Chu, I.H.

    1985-01-01

    Nuclear power development in Taiwan was initiated in 1956. Now Taipower has five nuclear units in smooth operation, one unit under construction, two units under planning. The relatively short construction period, low construction costs and twin unit approach had led to the significant economical advantage of our nuclear power generation. Moreover betterment programmes have further improved the availability and reliability factors of our nuclear power plants. In Taipower, the generation cost of nuclear power was even less than half of that of oil-fired thermal power in the past years ever since the nuclear power was commissioned. This made Taipower have more earnings and power rates was even dropped down in March 1983. As Taiwan is short of energy sources and nuclear power is so well-demonstrated nuclear power will be logically the best choice for Taipower future projects

  19. Safety Evaluation Report related to the operation of Diablo Canyon Nuclear Power Plant, Units 1 and 2 (Docket Nos. 50-275 and 50-323). Supplement No. 30

    International Nuclear Information System (INIS)

    1985-04-01

    Supplement 30 to the Safety Evaluation Report for the application by the Pacific Gas and Electric Company (PG and E) to operate the Diablo Canyon Nuclear Power Plant - Unit 2 (Docket No. 50-323) has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. SSER 30 reports on the staff's technical review and evaluation of the design and analysis of Unit 2 piping systems and pipe supports. The staff effort includes an evaluation of PG and E's treatment of issues raised during the Unit 1 design verification, actions resulting from low power License Condition 2.C.(11) in the Unit 1 low power license DPR-76 and the Unit 2 applicability and resolution of certain allegations related to piping and supports

  20. Dictionary of nuclear energy termination

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1983-04-15

    This book lists termination of nuclear energy such as abbreviation, symbol, unit of nuclear energy, radiological unit, the symbol for element, isotope chart and the periodic table. This book contains about 5500 words involving to nuclear energy with index in Korean and English. It arranges alphabetically. So, with this book, it is easy and fast to find out the glossary, unit and symbol on nuclear energy.

  1. Dictionary of nuclear energy termination

    International Nuclear Information System (INIS)

    1983-04-01

    This book lists termination of nuclear energy such as abbreviation, symbol, unit of nuclear energy, radiological unit, the symbol for element, isotope chart and the periodic table. This book contains about 5500 words involving to nuclear energy with index in Korean and English. It arranges alphabetically. So, with this book, it is easy and fast to find out the glossary, unit and symbol on nuclear energy.

  2. Integrated safety assessment report: Integrated Safety Assessment Program: Millstone Nuclear Power Station, Unit 1 (Docket No. 50-245): Draft report

    International Nuclear Information System (INIS)

    1987-04-01

    The Integrated Safety Assessment Program (ISAP) was initiated in November 1984, by the US Nuclear Regulatory Commission to conduct integrated assessments for operating nuclear power reactors. The integrated assessment is conducted in a plant-specific basis to evaluate all licensing actions, licensee initiated plant improvements and selected unresolved generic/safety issues to establish implementation schedules for each item. In addition, procedures will be established to allow for a periodic updating of the schedules to account for licensing issues that arise in the future. This report documents the review of Millstone Nuclear Power Station, Unit No. 1, operated by Northeast Nuclear Energy Company (located in Waterford, Connecticut). Millstone Nuclear Power Station, Unit No. 1, is one of two plants being reviewed under the pilot program for ISAP. This report indicates how 85 topics selected for review were addressed. This report presents the staff's recommendations regarding the corrective actions to resolve the 85 topics and other actions to enhance plant safety. The report is being issued in draft form to obtain comments from the licensee, nuclear safety experts, and the Advisory Committee for Reactor Safeguards (ACRS). Once those comments have been resolved, the staff will present its positions, along with a long-term implementation schedule from the licensee, in the final version of this report

  3. Application of ASME code AG-1 to YGN 3 ampersand 4 plants, South Korea

    International Nuclear Information System (INIS)

    Kim, Y.K.; Porco, R.D.; York, Y.D.

    1993-01-01

    Yonggwang Nuclear Power Plant Units 3 ampersand 4 are located on the southwestern coast of South Korea on the Yellow Sea. The plant is owned by Korea Electric Power Corp. (KEPCO), with the engineering being performed by Korea Power Engineering Co., Inc. (KOPEC) and Sargent and Lundy under a technology transfer agreement. The plants are both 950 Megawatt (electric) pressurized water reactors of US design. Under contract to KEPCO, Korea Heavy Industries and Construction Co., Ltd. and Ellis and Watts, Division of Dynamics Corporation of America, Batavia, Ohio, supplied major components to the YGN plants in compliance to ASME AG-1. These components included safety related Air Cleaning Units, Reactor containment Fan Cooler Units, Air Handling Units, Cubicle Coolers, Duct Electric Heaters, and fans. This paper details the extent of applicability of ASME Code AG-1 to the specific equipment, description of the equipment, conformance, testing, and design required. The paper also discusses the problems encountered in implementing ASME AG-1, working around Code sections that were not complete at contract inception, conflicts in project documents and related problems. Also discussed are the logistics problems, material availability, and quality assurance aspects complicating the applications of ASME AG-1, due to the required Korean content for some components. Based on successfully supplying the equipment referenced above, it has been concluded that AG-1 is a working document and can be successfully implemented. It provides the requirements necessary for performance, design, construction, acceptance testing, and quality assurance of equipment used as components in nuclear air and gas treatment systems in nuclear facilities. The paper also addresses lessons learned and aspects of mixing US design and US built components in Korean built assemblies

  4. Impact of hazardous waste handling legislation on nuclear installations and radioactive waste management in the United States

    International Nuclear Information System (INIS)

    Trosten, L.M.

    1988-01-01

    The United States has enacted complex legislation to help assure proper handling of hazardous waste and the availability of funds to cover the expenditures. There are a number of uncertainties concerning the impact of this legislation, and regulations promulgated by the Environmental Protection Agency and the states, upon nuclear installations and radioactive waste management. This report provides an overview of the U.S. hazardous waste legislation and examines the outlook for its application to the nuclear industry (NEA) [fr

  5. An Improved Methodology of Monetary Values of the Unit Collective Dose for Intervention Against Long-Term Exposure Following a Nuclear Accident

    International Nuclear Information System (INIS)

    Hwang, Won Tae; Kim, Eun Han; Suh, Kyung Suk; Choi, Young Gil; Han, Moon Hee

    2002-01-01

    A more practice approach for the determination of monetary values of the unit collective dose for intervention against long-term exposure following a nuclear accident was proposed. In addition, the monetary values of the unit collective dose estimated from the proposed approach were compared with those estimated from the previous model, which are derived from assumptions of routine exposure and the same values are applied in a nuclear accident without modification, using Korea economic data. The monetary values based on the proposed approach showed a distinct difference depending on inequity in the distribution of individual doses. The discounting rate was also an important factor in determination of monetary values of the unit collective dose

  6. An Improved Methodology of Monetary Values of the Unit Collective Dose for Intervention Against Long-Term Exposure Following a Nuclear Accident

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, Won Tae; Kim, Eun Han; Suh, Kyung Suk; Choi, Young Gil; Han, Moon Hee [KAERI, Daejeon (Korea, Republic of)

    2002-06-15

    A more practice approach for the determination of monetary values of the unit collective dose for intervention against long-term exposure following a nuclear accident was proposed. In addition, the monetary values of the unit collective dose estimated from the proposed approach were compared with those estimated from the previous model, which are derived from assumptions of routine exposure and the same values are applied in a nuclear accident without modification, using Korea economic data. The monetary values based on the proposed approach showed a distinct difference depending on inequity in the distribution of individual doses. The discounting rate was also an important factor in determination of monetary values of the unit collective dose.

  7. Safety-Evaluation Report related to the operation of Grand Gulf Nuclear Station, Units 1 and 2. Docket Nos. 50-416 and 50-417

    International Nuclear Information System (INIS)

    1983-05-01

    Supplement 4 to the Safety Evaluation Report for Mississippi Power and Light Company, et. al., joint application for licenses to operate the Grand Gulf Nuclear Station, Units 1 and 2, located on the east bank of the Mississippi River near Port Gibson in Claiborne County, Mississippi, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status on the resolution of those issues that required further evaluation before authorizing operation of Unit 1 above 5% rated power and other issues that were to be evaluated during the first cycle of power operation

  8. U.S. Job Creation Due to Nuclear Power Resurgence in The United States — Volumes 1 and 2

    Energy Technology Data Exchange (ETDEWEB)

    Catherine M. Plowman

    2004-11-01

    The recent revival of interest in nuclear power is causing a reexamination of the role of nuclear power in the United States. This renewed interest has led to questions regarding the capability and capacity of current U.S. industries to support a renewal of nuclear power plant deployment. This study was conducted to provide an initial estimate of jobs to be gained in the U.S. through the repatriation of the nuclear manufacturing industry. In the course of the study, related job categories were also modeled to provide an additional estimate of the potential expansion of existing industries (i.e., plant construction and operations) in conjunction with the repatriation of manufacturing jobs.

  9. Design of chemical treatment unit for radioactive liquid wastes in Serpong nuclear facilities

    International Nuclear Information System (INIS)

    Salimin, Z.; Walman, E.; Santoso, P.; Purnomo, S.; Sugito; Suwardiyono; Wintono

    1996-01-01

    The chemical treatment unit for radioactive liquid wastes arising from nuclear fuel fabrication, radioisotopes production and radiometallurgy facility has been designed. The design of chemical processing unit is based on the characteristics of liquid wastes containing fluors from uranium fluoride conversion process to ammonium uranyl carbonate on the fuel fabrication. The chemical treatment has the following process steps: coagulation-precipitation of fluoride ion by calcium hydroxide coagulant, separation of supernatant solution from sludge, coagulation of remaining fluoride on the supernatant solution by alum, separation of supernatant from sludge, and than precipitation of fluors on the supernatant by polymer resin WWS 116. The processing unit is composed of 3 storage tanks for raw liquid wastes (capacity 1 m 3 per tank), 5 storage tanks for chemicals (capacity 0.5 m 3 per tank), 2 mixing reactors (capacity 0.5 m 3 per reactor), 1 storage tank for supernatant solution (capacity 1 m 3 ), and 1 storage tank for sludge (capacity 1 m 3 )

  10. Europe's nuclear dominos

    International Nuclear Information System (INIS)

    Sharp, J.

    1993-01-01

    As long as the United States continues to play a leading role in NATO, the incentive for European powers to acquire independent nuclear weapons is virtually zero. Most European power, however, have relatively sophisticated nuclear establishments and could easily manufacture nuclear explosives if they judged that their security required an independent capability. They might judge so if the United States pulls out of Europe and out of NATO. It is the opinion of the author that if the United States withdraws, and if France and Britain insist on maintaining their current status as independent nuclear weapons powers, they will encourage proliferation by example. The likelihood of different countries deciding to manufacture nuclear weapons under these cicumstances is evaluated. The future of NATO is assessed. The conclusions of and future structure of the Conference on Cooperation and Security in Europe (CSCE) is discussed. The impact of United Nations involvement in preventing proliferation is evaluated. Recommendations are proposed for the utilization of existing organizations to deter proliferation in Europe

  11. Dynamic model of YGN 3 and 4 steam generators for natural circulation mode

    International Nuclear Information System (INIS)

    Sohn, Jong Joo

    1995-02-01

    A dynamic model for the secondary side of Yonggwang nuclear power plant units 3 and 4 (YGN 3 and 4) steam generator model is developed to improve the accuracy of the present performance analysis code. The new model is based on the one-dimensional three region model to predict the local quality and void fraction distribution along the U-tube length. The local quality concept is used instead of the Wilson bubble rise correlation to simulate the steam generators in the natural circulation mode. The new model can be applicable to the plants in the power operation modes such as load maneuvering transients in which the steam generator internal flow is maintained in the natural circulation mode. To validate the new model, the code predictions are compared with the actual plant data measured for the selected load maneuvering tests performed during the YGN units 3 power ascension test period. The results from the improved model show better agreement with the plant data than those from the present code. Especially, the new model's capability of accurately simulating the steam generator water level behavior during the fast transients such as a large load rejection event is demonstrated

  12. Nuclear power. Its development in the United Kingdom

    International Nuclear Information System (INIS)

    Pocock, R.F.

    1977-01-01

    The subject is covered chronologically in chapters, entitled: from war to peace; the Atomic Energy Authority and the first nuclear power station; a civil power programme; Windscale - the need for caution; research for the future; the new (Magnox) power stations; revision of the nuclear power programme; supply of nuclear fuels; nuclear power for ship propulsion; completion of first programme; Dungeness B and second programme, political assessment of (nuclear) industry's structure; reorganization of the industry; nuclear power in the environment; completion of second programme; the energy crisis; decision on third programme. (U.K.)

  13. A new concept for filtration units for trapping radioactive aerosols and iodine in the ventilation systems of nuclear power plants with WWER reactors

    International Nuclear Information System (INIS)

    Foerster, V.; Slanina, S.

    1985-01-01

    The paper describes a concept for new filtration units in the ventilation systems of nuclear power plants with WWER reactors. The new units are characterized by more stringent requirements on the efficiency of air purification (removal of radioactive contaminants) and various requirements for the quality of air purification in the ventilation systems. Work performed at the Scientific Research Institute for Air Technology has resulted in filtration units of a universal modular type, the structural design of which permits a high degree of variation in their component parts. A brief description is given of the filtration units, their basic technical characteristics and examples of their use in nuclear power plant ventilation systems. (author)

  14. United States Department of Energy Nuclear Materials Stewardship

    International Nuclear Information System (INIS)

    Newton, J. W.

    2002-01-01

    The Department of Energy launched the Nuclear Materials Stewardship Initiative in January 2000 to accelerate the work of achieving integration and cutting long-term costs associated with the management of the Department's nuclear materials, with the principal focus on excess materials. Management of nuclear materials is a fundamental and enduring responsibility that is essential to meeting the Department's national security, nonproliferation, energy, science, and environmental missions into the distant future. The effective management of nuclear materials is important for a set of reasons: (1) some materials are vital to our national defense; (2) the materials pose physical and security risks; (3) managing them is costly; and (4) costs are likely to extend well into the future. The Department currently manages nuclear materials under eight programs, with offices in 36 different locations. Through the Nuclear Materials Stewardship Initiative, progress was during calendar year 20 00 in achieving better coordination and integration of nuclear materials management responsibilities and in evaluating opportunities to further coordinate and integrate cross-program responsibilities for the treatment, storage, and disposition of excess nuclear materials. During CY 2001 the Departmental approach to nuclear materials stewardship changed consistent with the business processes followed by the new administration. This paper reports on the progress of the Nuclear Materials Stewardship Initiative in evaluating and implementing these opportunities, and the remaining challenges in integrating the long-term management of nuclear materials

  15. 'Newcomer' nuclear nation leads way into new nuclear year

    Energy Technology Data Exchange (ETDEWEB)

    Shepherd, John [nuclear 24, St George' s Redditch (United Kingdom)

    2018-01-15

    At the start of a new year, it is appropriate that a 'newcomer' nuclear nation has launched work on building its first nuclear power plant. First nuclear safety-related concrete has been poured for the plant at Rooppur in Bangladesh - making the South Asia nation the first in 30 years to start building its first commercial reactor unit following the United Arab Emirates in 2012 and Belarus in 2013. Despite setbacks that nuclear has endured in recent years, there are nearly 60 reactors under construction around the world, mostly in Asia. Some 447 commercial reactor units are in operation in 30 countries.

  16. Modelling and simulation of containment on full scope simulator for Qinshan 300 MW Nuclear Power Unit

    International Nuclear Information System (INIS)

    Zou Tingyun

    1996-01-01

    A multi-node containment thermal-hydraulic model has been developed and adapted in Full Scope Simulator for Qinshan 300 MW Nuclear Power Unit with good realtime simulation effects. Containment pressure for LBLOCA calculated by the model is well agreed with those of CONTEMPT-4/MOD3

  17. Common cause failure analysis of the rodded scram system of the Arkansas Nuclear One-Unit 1 Plant

    International Nuclear Information System (INIS)

    Montague, D.F.; Campbell, D.J.; Flanagan, G.F.

    1986-10-01

    This study demonstrates the use of a formal method for common cause failure analysis in a reliability analysis of the Arkansas Nuclear One - Unit 1 rodded scram system. The scram system failure of interest is loss of capability of the system to shut the reactor down when required. The results of this analysis support the ATWS program sponsored by the US Nuclear Regulatory Commission. The methods used in this analysis support the NRC's Risk Methods Integration and Evaluation Program (RMIEP)

  18. Calculation of radioactive inventory of activated parts for nuclear power unit and analysis of influence factors

    International Nuclear Information System (INIS)

    Liu Yang; Cai Qi; Lin Xiaoling

    2011-01-01

    Based on the operation characteristics of the nuclear power unit, the radioactive inventory of activated parts was calculated by ORIGEN2, and the effects of bum-up, operation mode and power change on the radioactive inventory for activated parts were analyzed. The results indicated that the radioactive inventory grew with the increasing of burn-up, and when the actual operation time was longer than the effective operation time, the increasing rate of nuclide activity approximated the burn-up increasing; Radioactive inventory of activated parts was influenced directly by the operation modes of the nuclear power unit, and under same reactor load, operation power and bum-up, the radioactive inventory for non-continuous operation mode is less than that for the continuous operation mode. Effects of operation modes on radioactive inventory reversed with half life of nuclides. Under same bum-up and longer operation time, the effect of operation power change on the radioactive inventory is not obvious, (authors)

  19. Application of controllable unit approach (CUA) to performance-criterion-based nuclear material control and accounting

    International Nuclear Information System (INIS)

    Foster, K.W.; Rogers, D.R.

    1979-01-01

    The Nuclear Regulatory Commission is considering the use of maximum-loss performance criteria as a means of controlling SNM in nuclear plants. The Controllable Unit Approach to material control and accounting (CUA) was developed by Mound to determine the feasibility of controlling a plant to a performance criterion. The concept was tested with the proposed Anderson, SC, mixed-oxide plant, and it was shown that CUA is indeed a feasible method for controlling a complex process to a performance criterion. The application of CUA to an actual low-enrichment plant to assist the NRC in establishing performance criteria for uranium processes is discussed. 5 refs

  20. Safety evaluation report related to the operation of Millstone Nuclear Power Station, Unit No. 3 (Docket No. 50-423)

    International Nuclear Information System (INIS)

    1984-07-01

    The Safety Evaluation Report for the application filed by Northeast Nuclear Energy Company, as applicant and agent for the owners, for a license to operate the Millstone Nuclear Power Station Unit 3 (Docket No. 50-423), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in the town of Waterford, New London County, Connecticut, on the north shore of Long Island Sound. Subject to favorable resolution of the items discussed in this report, the NRC staff concludes that the facility can be operated by the applicant without endangering the health and safety of the public

  1. The Status and Inspection of Bottom Mounted Instrumentation Nozzle in Korea

    International Nuclear Information System (INIS)

    Doh, Euisoon; Kim, Yoonwon; Kim, Jaeyoon; Lee, Tacksu; Lee, Changhun

    2012-01-01

    The PWSCC Cracking of Alloy 600 material has been issued since CRDM Penetration cracking of Bugey in France in 1990's. And J-groove weld cracking of CRDM at Oconee and PCR Nozzle cracking at Wolf Creek in USA were raising concern of the integrity for Dissimilar Metal Weld of Alloy 600. BMI(Bottom Mounted Instrumentation) Nozzle cracks were found at Takahama unit 1 in Japan and South Texas Project unit 1 in USA in 2003. And recent cracks of Reactor Head Vent line at Yonggwang unit 3 in Korea are enough to cause worry about the integrity for BMI Nozzles in Korea. BMI inspections of Westinghouse type plant were performed by KPS for Kori unit 1 in 2006, Ulchin unit 2 in 2007, and Kori unit 3 in 2008. The first inspection of OCR-1000 plant was carried out on May 2011 at Yonggwang unit 3. KPS developed the inspection technique of OCR-1000 plant for End Effector Module and controller, a quarterly actual sized Bottom head Mock up, Inspection probes meeting the regulatory guide lines and typical configuration of OCR-1000 plant. Two specimens with actual PWSCC cracks were used to demonstrate the Inspection technique of Detection and Sizing. and the quarterly actual sized Bottom head Mock up was very meaningful to check the Interference during the inspection by narrow gap between newly developments led to a successful inspection of the BMI Inspection. And the inspection was concurrently performed with 10 year Reactor Vessel ICI without hurting any critical path of the outage. This BMI inspection is contributing to keep Operational Safety of plants by prevention of Leakage at BMI nozzle and weld. And performing 10 Year ISI for BMI nozzle is very effective to prevent BMI nozzle Break by detecting PWSCC Initiation per PFM Sensitivity study

  2. Startup of Pumping Units in Process Water Supplies with Cooling Towers at Thermal and Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Berlin, V. V., E-mail: vberlin@rinet.ru; Murav’ev, O. A., E-mail: muraviov1954@mail.ru; Golubev, A. V., E-mail: electronik@inbox.ru [National Research University “Moscow State University of Civil Engineering,” (Russian Federation)

    2017-03-15

    Aspects of the startup of pumping units in the cooling and process water supply systems for thermal and nuclear power plants with cooling towers, the startup stages, and the limits imposed on the extreme parameters during transients are discussed.

  3. Safety evaluation report related to the operation of Catawba Nuclear Station, Units 1 and 2 (Docket Nos. 50-413 and 50-414)

    International Nuclear Information System (INIS)

    1984-07-01

    The report supplements the Safety Evaluation Report (NUREG-0954) issued in February 1983 by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by Duke Power Company, North Carolina Municipal Power Agency Number 1, North Carolina Membership Corporation, and Saluda River Electric Cooperative, Inc. as applicants and owners, for licenses to operate the Catawba Nuclear Station, Units 1 and 2 (Docket Nos. 50-413 and 50-414, respectively). The facility is located in York County, South Carolina, approximately 9.6 km (6 mi) north of Rock Hill and adjacent to Lake Wylie. This supplement provides additional information supporting the license for fuel loading and precriticality testing for Unit 1

  4. The Arabidopsis Nuclear Pore and Nuclear Envelope

    OpenAIRE

    Meier, Iris; Brkljacic, Jelena

    2010-01-01

    The nuclear envelope is a double membrane structure that separates the eukaryotic cytoplasm from the nucleoplasm. The nuclear pores embedded in the nuclear envelope are the sole gateways for macromolecular trafficking in and out of the nucleus. The nuclear pore complexes assembled at the nuclear pores are large protein conglomerates composed of multiple units of about 30 different nucleoporins. Proteins and RNAs traffic through the nuclear pore complexes, enabled by the interacting activities...

  5. United States experience in environmental cost-benefit analysis for nuclear power plants with implications for developing countries

    International Nuclear Information System (INIS)

    Spangler, M.B.

    1980-08-01

    Environmental cost-benefit analysis in the United States involves a comparison of diverse societal impacts of the proposed developments and its alternatives. Regarding nuclear power plant licensing actions, such analyses include the need for base-load electrical generating capacity versus the no-action alternative; alternative sources of energy; alternative sites for the proposed nuclear plants; and alternative technologies for mitigating environmental impacts. Many U.S. experiences and environmental assessment practices and comparative resource requirements presented in this report will not provide a wholly reliable reflection of the precise situation of each country. Nevertheless, the procedural and substantive issues encountered by the United States in nuclear power plant licensing may exhibit a number of important, if rough, parallelisms for other countries. Procedural issues dealt with include: the scoping of alternatives and impact issues; the problem of balancing incommensurable impacts; and treating uncertainty in measuring or forecasting certain kinds of environmental impacts. Although substantive environmental impact issues will vary appreciably among nations, it is to be expected that many of the substantive impact issues such as impacts on biota, community-related effects, and aesthetic impacts will also have some measure of universal interest to other countries

  6. The Analysis of the System of special water purification of Beloyarskaya Nuclear Power Plant unit BN-800

    Science.gov (United States)

    Valtseva, A. I.; Bibik, I. S.

    2017-11-01

    This article discusses how the latest system of special water purification KPF-30, designed specifically for the fourth power unit of Beloyarskaya nuclear power plant, which has a number of advantages over other water purification systems as chemical-physical and technical-economic, environmental, and other industrial indicators. The scheme covered in this article systems of special water purification involves the use of a hydrocyclone at the preliminary stage of water treatment, as a worthy alternative to ion-exchange filters, which can significantly reduce the volume of toxic waste. The world community implements the project of closing the nuclear fuel cycle, there is a need to improve the reliability of the equipment for safe processes and development of critical and supercritical parameters in the nuclear industry. Essentially, on operated NPP units, the only factor that can cost-effectively optimize to improve the reliability of equipment is the water chemistry. System KPF30 meets the principles and criteria of ecological safety, demonstrating the justification for reagent less method of water treatment on the main stages, in which no formation of toxic wastes, leading to irreversible consequences of environmental pollution and helps to conserve water.

  7. The enforcement program of the nuclear regulatory commission in the United States

    International Nuclear Information System (INIS)

    Thornburg, H.D.

    1977-01-01

    The enforcement program of the United States Nuclear Regulatory Commission consists of a clearly spelled out, evenly applied program of deterrents which escalate according to the nature of the offense and the past history of the licensee's noncompliances. Ninety-eight percent of all enforcement actions are normally handled by the five Regional offices. Only one percent of noncompliances have been classed as violations where significant safety consequences occurred. A strong and timely enforcement program is essential to insure that licensees fulfill their obligations to protect the public and the environment. (Auth.) [fr

  8. Critical evaluation of the nonradiological environmental technical specifications. Volume 4. San Onofre Nuclear Generating Station, Unit 1

    Energy Technology Data Exchange (ETDEWEB)

    Adams, S.M.; Cunningham, P.A.; Gray, D.D.; Kumar, K.D.

    1976-08-10

    A comprehensive study of the data collected as part of the environmental Technical Specifications program for Unit 1 of the San Onofre Nuclear Generating Station (SONGS 1) was conducted for the Office of Nuclear Regulatory Research of the U.S. Nuclear Regulatory Commission. The program included an analysis of the hydrothermal and ecological monitoring data collected during 1975. The hydrothermal analysis includes a discussion of models used in plume predictions prior to plant operation and an evaluation of the present hydrothermal monitoring program. The ecological evaluation was directed toward reviewing the strengths and weaknesses of the various sampling programs designed to monitor the planktonic, benthic, and nektonic communities inhabiting the inshore coastal area in the vicinity of San Onofre.

  9. Critical evaluation of the nonradiological environmental technical specifications. Volume 4. San Onofre Nuclear Generating Station, Unit 1

    International Nuclear Information System (INIS)

    Adams, S.M.; Cunningham, P.A.; Gray, D.D.; Kumar, K.D.

    1976-01-01

    A comprehensive study of the data collected as part of the environmental Technical Specifications program for Unit 1 of the San Onofre Nuclear Generating Station (SONGS 1) was conducted for the Office of Nuclear Regulatory Research of the U.S. Nuclear Regulatory Commission. The program included an analysis of the hydrothermal and ecological monitoring data collected during 1975. The hydrothermal analysis includes a discussion of models used in plume predictions prior to plant operation and an evaluation of the present hydrothermal monitoring program. The ecological evaluation was directed toward reviewing the strengths and weaknesses of the various sampling programs designed to monitor the planktonic, benthic, and nektonic communities inhabiting the inshore coastal area in the vicinity of San Onofre

  10. The virtual digital nuclear power plant: A modern tool for supporting the lifecycle of VVER-based nuclear power units

    Science.gov (United States)

    Arkadov, G. V.; Zhukavin, A. P.; Kroshilin, A. E.; Parshikov, I. A.; Solov'ev, S. L.; Shishov, A. V.

    2014-10-01

    The article describes the "Virtual Digital VVER-Based Nuclear Power Plant" computerized system comprising a totality of verified initial data (sets of input data for a model intended for describing the behavior of nuclear power plant (NPP) systems in design and emergency modes of their operation) and a unified system of new-generation computation codes intended for carrying out coordinated computation of the variety of physical processes in the reactor core and NPP equipment. Experiments with the demonstration version of the "Virtual Digital VVER-Based NPP" computerized system has shown that it is in principle possible to set up a unified system of computation codes in a common software environment for carrying out interconnected calculations of various physical phenomena at NPPs constructed according to the standard AES-2006 project. With the full-scale version of the "Virtual Digital VVER-Based NPP" computerized system put in operation, the concerned engineering, design, construction, and operating organizations will have access to all necessary information relating to the NPP power unit project throughout its entire lifecycle. The domestically developed commercial-grade software product set to operate as an independently operating application to the project will bring about additional competitive advantages in the modern market of nuclear power technologies.

  11. Radiation litigation and the nuclear industry--the experience in the United Kingdom.

    Science.gov (United States)

    Leigh, W J; Wakeford, R

    2001-12-01

    In the United Kingdom, the Nuclear Installations Act 1965 places a "strict" statutory duty on the operators of nuclear facilities to ensure that any exposure to radiation resulting from operations does not cause injury or damage. A claimant does not have to prove fault to receive compensation under the Act, only causation. The 1965 Act has been fundamental in shaping litigation involving the nuclear industry in the UK. Civil law cases brought under the Act will be heard before a single judge (with no jury or technical assessor) who must present his or her decision in a reasoned judgment. This process leads to a considerable volume of expert evidence being presented to the court and extensive cross-examination of witnesses. The expense and uncertain outcome of cases involving claims by nuclear workers that occupational exposure to radiation had caused the development of cancer has led to employers and trade unions setting up the voluntary Compensation Scheme for Radiation-linked Diseases as an alternative to litigation. This Scheme has worked well and is held up as a model of alternative dispute resolution. However, a few cases concerning personal injury or damage to property have come before the courts when the defendant nuclear operator considered that the claims were technically unjustified and where settlement was not a policy option. As anticipated, these cases were lengthy, complex, and expensive. The radiation doses assessed to have been received by the individuals who were the subject of claims, whether workers or members of the public, have been crucial to the outcome. The technical expertise of health physicists and allied specialists has been vital in establishing defensible estimates of dose, and this contribution can be expected to remain of high importance in radiation litigation in the UK.

  12. Nuclear Power Plant Control and Instrumentation activities in the United Kingdom

    International Nuclear Information System (INIS)

    Goodings, A.

    1990-01-01

    The paper describes the status of the NPP control and instrumentation in the United Kingdom. The general technology underlying most aspects of power reactor C and I in the UK has not altered since the last progress report although there have been many improvements in detail. In one field, however, that of computer applications, the change has almost been one of kind rather than degree. The following fields are briefly described: The status of nuclear power in the UK, the development of sensors, the development of electronic equipment, signal processing - information technology, quality assurance and the validation and verification of software, expert systems, training simulators. (author). 1 ref

  13. Joining the Nuclear Renaissance with the Engineering Business Unit of AREVA

    Energy Technology Data Exchange (ETDEWEB)

    Hubert, Nathalie; Menguy, Stephane [SGN, AREVA Group, 1 rue des Herons, 78182 Saint-Quentin en Yvelines Cedex (France); Valery, Jean-Francois [AREVA NC, AREVA Group, Tour AREVA, 1 place de la Coupole, 92084 Paris La Defense Cedex (France)

    2008-07-01

    The reality of the nuclear renaissance is no longer a question. All over the world, new nuclear plants are going to be deployed; the whole fuel cycle has to be adjusted to fulfil their needs, the front-end to produce the fuel and the back-end to properly manage radioactive waste. AREVA fuel cycle engineering teams have been involved in the design of a variety of industrial plants covering the entire fuel cycle for 50 years. The consistency of the French nuclear policy has been a major factor to acquire and renew the competencies and workforce of AREVA Engineering Business Unit. Our partnership with our customers, French ones but also Japanese, Americans and from other countries, has led us to develop a comprehensive approach of the services that we can deliver, in order to give them the best answer. SGN teams have been involved in the R and D phases in order to take into account the industrialisation aspects as early as possible, and our work does not end with the delivery of the plants; it includes assistance to the operators to optimise and keep their facilities in line with the changing rules and constraints, which ensures the integration of a wide operational experience feedback and the ability to design flexible facilities. This paper will present through our experience how this global approach has been developed and continuously improved and how we are preparing our teams to be ready to answer to the coming needs. (authors)

  14. Joining the Nuclear Renaissance with the Engineering Business Unit of AREVA

    International Nuclear Information System (INIS)

    Hubert, Nathalie; Menguy, Stephane; Valery, Jean-Francois

    2008-01-01

    The reality of the nuclear renaissance is no longer a question. All over the world, new nuclear plants are going to be deployed; the whole fuel cycle has to be adjusted to fulfil their needs, the front-end to produce the fuel and the back-end to properly manage radioactive waste. AREVA fuel cycle engineering teams have been involved in the design of a variety of industrial plants covering the entire fuel cycle for 50 years. The consistency of the French nuclear policy has been a major factor to acquire and renew the competencies and workforce of AREVA Engineering Business Unit. Our partnership with our customers, French ones but also Japanese, Americans and from other countries, has led us to develop a comprehensive approach of the services that we can deliver, in order to give them the best answer. SGN teams have been involved in the R and D phases in order to take into account the industrialisation aspects as early as possible, and our work does not end with the delivery of the plants; it includes assistance to the operators to optimise and keep their facilities in line with the changing rules and constraints, which ensures the integration of a wide operational experience feedback and the ability to design flexible facilities. This paper will present through our experience how this global approach has been developed and continuously improved and how we are preparing our teams to be ready to answer to the coming needs. (authors)

  15. A closed Brayton power conversion unit concept for nuclear electric propulsion for deep space missions

    International Nuclear Information System (INIS)

    Joyner, Claude Russell II; Fowler, Bruce; Matthews, John

    2003-01-01

    In space, whether in a stable satellite orbit around a planetary body or traveling as a deep space exploration craft, power is just as important as the propulsion. The need for power is especially important for in-space vehicles that use Electric Propulsion. Using nuclear power with electric propulsion has the potential to provide increased payload fractions and reduced mission times to the outer planets. One of the critical engineering and design aspects of nuclear electric propulsion at required mission optimized power levels is the mechanism that is used to convert the thermal energy of the reactor to electrical power. The use of closed Brayton cycles has been studied over the past 30 or years and shown to be the optimum approach for power requirements that range from ten to hundreds of kilowatts of power. It also has been found to be scalable to higher power levels. The Closed Brayton Cycle (CBC) engine power conversion unit (PCU) is the most flexible for a wide range of power conversion needs and uses state-of-the-art, demonstrated engineering approaches. It also is in use with many commercial power plants today. The long life requirements and need for uninterrupted operation for nuclear electric propulsion demands high reliability from a CBC engine. A CBC engine design for use with a Nuclear Electric Propulsion (NEP) system has been defined based on Pratt and Whitney's data from designing long-life turbo-machines such as the Space Shuttle turbopumps and military gas turbines and the use of proven integrated control/health management systems (EHMS). An integrated CBC and EHMS design that is focused on using low-risk and proven technologies will over come many of the life-related design issues. This paper will discuss the use of a CBC engine as the power conversion unit coupled to a gas-cooled nuclear reactor and the design trends relative to its use for powering electric thrusters in the 25 kWe to 100kWe power level

  16. Technical specifications, Shoreham Nuclear Power Station, Unit No. 1 (Docket No. 50-322): Appendix ''A'' to License No. NPF-82

    International Nuclear Information System (INIS)

    1989-04-01

    The Shoreham, Unit 1, Technical Specifications were prepared by the US Nuclear Regulatory Commission to set forth the limits, operating conditions, and other requirements applicable to a nuclear facility as set forth in Section 50.36 of 10 CFR Part 50 for the protection of the health and safety of the public. 20 figs., 75 tabs

  17. Nuclear war-fighting strategy for the United States

    International Nuclear Information System (INIS)

    Martel, W.C.

    1981-01-01

    This dissertation concerns a strategy for fighting and winning a nuclear war. Despite the conventional wisdom that nuclear war is suicidal and occurs only as a result of irrationality, this study analyzes nuclear war as a rational policy option. It is necessary to suggest the radical proposition that nuclear war, like traditional military campaigns, is a political action. Thus, nuclear war can be in the national interest. Further, the countervalue strategy of Mutually Assured Destruction is questioned because city destruction serves no conceivable political or military objective

  18. Safety Evaluation Report related to the operation of Diablo Canyon Nuclear Power Plant, Units 1 and 2 (Docket Nos. 50-275 and 50-323)

    International Nuclear Information System (INIS)

    1991-06-01

    Supplement 34 to the Safety Evaluation Report for the application by Pacific Gas and Electric Company (PG ampersand E) for licenses to operate Diablo Canyon Nuclear Power Plant, Unit Nos. 1 and 2 (Docket Nos. 50-275 and 50-323, respectively) has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement documents the NRC staff review of the Long-Term Seismic Program conducted by PG ampersand E in response to License Condition 2.C.(7) of Facility Operating License DPR-80, the Diablo Canyon Unit 1 operating license. 111 refs., 20 figs., 31 tabs

  19. Nuclear Systems (NS): Technology Demonstration Unit (TDU)

    Data.gov (United States)

    National Aeronautics and Space Administration — The Nuclear Systems Project demonstrates nuclear power technology readiness to support the goals of NASA's Space Technology Mission Directorate. To this end, the...

  20. Brief introduction to project management of full scope simulator for Qinshan 300 MW Nuclear Power Unit

    International Nuclear Information System (INIS)

    Chen Jie

    1996-01-01

    The key points in development and engineering project management of full scope simulator for Qinshan 300 MW Nuclear Power Unit are briefly introduced. The Gantt chart, some project management methods and experience are presented. The key points analysis along with the project procedure will be useful to the similar project